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Radiation Safety Manual
March 2006
Table of Contents
About This Manual . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii
CHAPTER 1 – Natural Resources Canada Radiation Safety Program Framework
1.1 Mandate of the Natural Resources Canada Radiation Safety Program for the
Nuclear Substances and Radiation Devices Licence Issued for the Consolidated Use of
Nuclear Substances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.2 Organizational Management Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.3 Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.3.1 Duties and Responsibilities of the Radiation Safety Committee . . . . . . . . . . . . . . . . . . . . .
1.3.2 Radiation Safety Committee Members . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.4 Duties and Responsibilities of the Radiation Safety Officer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.4.1 Institutional Duties and Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.4.2 Radiation Safety Committee Duties and Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . .
1.5 Duties and Responsibilities of the Site Radiation Safety Officer . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.6 Duties and Responsibilities of Permit Holders . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.7 Duties and Responsibilities of Users Working with Radioisotopes . . . . . . . . . . . . . . . . . . . . . . . . . .
1-1
1-2
1-2
1-3
1-4
1-4
1-4
1-5
1-5
1-6
1-6
CHAPTER 2 – Licensing and Administration
2.1
2.2
2.3
2.4
2.5
2.6
2.7
2.8
2.9
2.10
2.11
2.12
2.13
2.14
2.15
Nuclear Substances and Radiation Devices Licence Issued for the Consolidated Use of
Nuclear Substances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.1.1 Application for the Nuclear Substances and Radiation Devices Licence . . . . . . . . . . . . . .
Internal Permit Application . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Internal Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Status of Permit Holder on Long-Term Leave . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Amendment of an Existing Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Renewal of an Existing Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Radioisotope Laboratory Approval . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Cancellation of an Internal Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Purchasing and Receiving Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Special Orders . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Inventory Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Compliance Inspection Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.12.1 Major Offences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.12.2 Moderate Offences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.12.3 Minor Offences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Compliance Enforcement Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.13.1 Major Offence Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.13.2 Moderate and Minor Offence Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Annual Compliance Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
CNSC Approval for Special Projects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2-1
2-1
2-1
2-2
2-2
2-2
2-3
2-3
2-4
2-4
2-4
2-4
2-5
2-5
2-6
2-6
2-6
2-6
2-7
2-7
2-7
CHAPTER 3 – Policies and Procedures
3.1
3.2
3.3
3.4
3.5
3.6
New Policies and Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
ALARA Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Designation of Nuclear Energy Workers Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Food and Drinks in a Radioisotope Laboratory Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Room Designating and Posting Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Access, Control and Security Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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3-1
3-1
3-1
3-1
3-2
3-2
3.7
3.8
3.9
3.10
3.11
3.12
3.13
3.14
3.6.1 Basic Laboratories . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2
3.6.2 Intermediate Laboratories . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2
3.6.3 Control of Nuclear Substances Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3
3.6.4 Theft of Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3
X-ray Producing Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3
Receiving Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-3
3.8.1 Responsibilities for Receiving Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-4
3.8.2 Procedures for Receiving Packages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-4
Packaging and Transporting Radioactive Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-4
Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-5
3.10.1 Personal Dose Monitoring Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-5
3.10.2 Dosimetry During Pregnancy for Non-NEWs Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6
3.10.3. Leak Testing of Sealed Sources Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6
3.10.4 Action Levels Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-6
Radioactive Contamination Control Policies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-7
3.11.1 General Rules and Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-7
3.11.2. Surface Contamination Measurements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-8
3.11.2.1 Wipe Test Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-8
3.11.2.2 Direct Measurement of Surface Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . 3-9
3.11.3 Procedures for Decontamination of Areas and Equipment . . . . . . . . . . . . . . . . . . . . . . . . 3-10
Decommissioning Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-10
3.12.1 Decommissioning Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-11
Emergency Response Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-12
3.13.1 Radioactive Material Spills . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-13
3.13.2 Radioactive Contamination of Skin or Clothing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-14
3.13.3 Treatment of Skin Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-14
3.13.3.1 If the skin is intact . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-14
3.13.3.2 In case of minor wounds not requiring hospitalization . . . . . . . . . . . . . . . . . . . . 3-15
3.13.3.3 In case of serious injuries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-15
3.13.4 Treatment of Clothing Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-15
3.13.5 Internal Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-15
3.13.6 Emergency Procedures for Portable Nuclear Gauges . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-16
3.13.7 Fire or Explosion Involving Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-16
Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-17
3.14.1 Classification of Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-17
3.14.2 Responsibility for Labelling and Packaging Radioactive Waste . . . . . . . . . . . . . . . . . . . . 3-17
3.14.3 Location of Radioactive Waste Containers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-18
3.14.4 Waste Disposal Streams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-18
3.14.5 Specific Waste Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-18
3.14.5.1 Solid Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-18
3.14.5.2 Liquids Containing Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-19
3.14.5.3 Liquid Scintillation Counting Vials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-19
3.14.5.4 Radioactive Material Containing a Biological Agent . . . . . . . . . . . . . . . . . . . . . . 3-19
3.14.5.5 Liquid Scintillation Counters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-19
3.14.5.6 Gas Chromatography Units . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-20
3.14.5.7 Miscellaneous Sealed Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-20
3.14.5.8 Refrigerators, Freezers and Other Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . 3-20
CHAPTER 4 – Radioactivity
4.1
Radiation Physics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4.1.1 Fundamental Particles . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4.1.2 The Atom . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4.1.3 Isotopes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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4-1
4-1
4-1
4-1
4.1.4
4.1.5
4.1.6
4.2
4.3
Radioisotopes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2
Radiation Energy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2
Nuclear Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2
4.1.6.1 Alpha Particle Emission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2
4.1.6.2 Negative Beta Particle Emission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3
4.1.6.3 Positive Beta Particle Emission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3
4.1.6.4 Gamma Ray Emission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4
4.1.6.5 Electron Capture (EC) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4
4.1.6.6 Internal Conversions (IC) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4
4.1.6.7 Neutron Emissions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4
4.1.6.8 X-rays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-5
4.1.7 Activity
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-5
4.1.8 Half-life . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-6
Radiation Measurement
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-8
4.2.1 Measurement of Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-8
4.2.1.1 Radiation Exposure Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-8
4.2.1.2 Radiation Absorbed Dose (rad) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-8
4.2.1.3 Relative Biological Effectiveness (RBE) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-9
4.2.1.4 Radiation Weighting Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-9
4.2.1.5 Equivalent Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-10
4.2.2 External Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-10
4.2.2.1 The ALARA Principle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-11
4.2.2.2 Nuclear Energy Workers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-11
4.2.2.3 Members of the General Public . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-12
4.2.3 Internal Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-12
4.2.3.1 Surface Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-12
4.2.3.2 Ingestion or Inhalation of Radioisotopes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-13
4.2.3.3 Intakes Occurring from an Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-13
Principles of Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-13
4.3.1 Objective of Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-14
4.3.2 "Rules of Thumb" for Radioactive Material . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-15
4.3.2.1 Alpha . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-15
4.3.2.2 Beta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-15
4.3.2.3 Gamma . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-15
4.3.2.4 Neutrons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-16
4.3.2.5 Radioactive Decay . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-16
4.3.3 External Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-17
4.3.3.1 Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-17
4.3.3.2 Distance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-17
4.3.3.3 Shielding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-17
4.3.4 Internal Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-18
4.3.4.1 Bioassay . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-19
4.3.4.2 Bioassay Requirements - Radioiodine . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-19
4.3.5 Radiation Dose Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-21
4.3.5.1 Survey Monitors for External Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . 4-21
4.3.5.2 Personal Dosimeters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-21
4.3.6 Requirements During Pregnancy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-21
4.3.7 Surface Contamination Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-22
CHAPTER 5 – Training
5.1
5.2
5.3
Worker Training and Authorization Policy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1
Short-Term Employees, Including Students and Volunteers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1
Site Radiation Safety Officers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2
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5.4
5.5
5.6
Other Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
NRCan's Radiation Safety Course . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Training Scheduling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.6.1 Retraining . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.7 Administering the Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.7.1 Training Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.7.2 Written Exam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.7.3 Certification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.8 Radiation Safety Training Modules . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.9 Other Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.10 Workplace Hazardous Materials Information System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.11 NRCan Radiation Safety Training Matrix . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5-2
5-2
5-2
5-3
5-3
5-3
5-3
5-3
5-3
5-8
5-8
5-8
CHAPTER 6 – Forms
Form 1
Form 2
Form 3
Form 4
Form 5
Form 6
Form 7
Form 8
Form 9
Form 10
Form 11
Open Source Inventory Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-2
Sealed Source Inventory Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-3
User Radiation Safety-Related Training Record . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4
Application for Internal Permit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5
Application for Internal Permit Amendment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-11
Application for Internal Permit Renewal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13
Decommissioning Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-15
Design Compliance Form for Laboratories . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18
Waste Disposal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-23
Wipe Test Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-25
Short-Term Employee Radiation Safety Training Record . . . . . . . . . . . . . . . . . . . . . . . . . 6-26
CHAPTER 7 – Glossary of Terms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1
CHAPTER 8 – Special Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1
CHAPTER 9 – CNSC Legislative Documents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-1
Annex A
Radiation Safety Committee Terms of Reference . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A–1
Annex B
Internal Inspection Checklist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B–1
Annex C
Emergency Contact Lists . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C–1
Annex D
Measurement Units Conversion Table . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D–1
Annex E
Laboratory Classification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E–1
Annex F
Periodic Table . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F–1
Annex G
NRCan Internal Permits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G–1
Annex H
Exemption Quantities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H–1
Annex I
Regulatory Quantities for Typical Radionuclides . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I–1
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Annex J
Information on Elements at NRCan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J–1
Annex K
List of Radiation Protection Service Companies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K–1
Annex L
List of Leak Test Measurement and Instrument Calibration Agencies . . . . . . . . . . . . L–1
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Natural Resources Canada Radiation Safety Manual
About This Manual
This manual was developed to provide information to all Permit Holders on the policies, practices,
procedures and training programs in place related to the occupational use of radioactive materials and
ionizing radiation-producing equipment at Natural Resources Canada.
This manual also provides information on licencing requirements and how they are administered within the
scope of the Radiation Safety Program for the Nuclear Substances and Radiation Devices Licence issued
for the consolidated use of nuclear substances at Natural Resources Canada.
Most procedures and rules apply wherever radiation sources are used. However, the diversity of radiation
sources and devices used at Natural Resources Canada is such that additional procedures and
regulations may be required in specially designated areas. These special procedures and
recommendations are listed under Chapter 8 of this manual and are available upon request.
Permit Holders must ensure that this manual is read and integrated in their in-house laboratory training for
all users.
If you have any questions, please contact either the Site Radiation Safety Officer or the Radiation Safety
Officer.
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Chapter 1:
Natural Resources Canada Radiation Safety Program Framework
1.1
Mandate of the Natural Resources Canada Radiation Safety Program for the Nuclear
Substances and Radiation Devices Licence Issued for the Consolidated Use of Nuclear
Substances
The Natural Resources Canada (NRCan) Radiation Safety Program for the Nuclear Substances and
Radiation Devices Licence is charged with the total overall program of radiation protection for the
consolidated licence at NRCan at all sites where nuclear substances are being used and stored. The
control exercised is complete and all-embracing, having the necessary executive power delegated to it by
the Assistant Deputy Minister (ADM), Corporate Management Sector (CMS), to enforce and maintain the
required standards of radiation protection necessary for NRCan.
This program has, as its foundation, federal regulations issued by the Canadian Nuclear Safety
Commission (CNSC), Health Canada and the Human Resources and Skills Development Canada—
Labour Program, and environmental legislation.
The responsibilities of the NRCan Radiation Safety Committee includes all sources of ionizing radiation
(both materials and devices), for whatever use, on all properties occupied by NRCan employees.
The ADM, CMS, delegates to the Chair of the NRCan Radiation Safety Committee power to sign on behalf
of NRCan for all matters within the jurisdiction of the committee. The Radiation Safety Committee reports
to the Deputy Minister (DM) through the ADM, CMS.
The Radiation Safety Committee considers and advises on the establishment of radiation emergency
measures within NRCan facilities, and co-operation and integration with other programs. The committee
also conducts educational programs as required with respect to radiation hazards.
The Radiation Safety Committee has the authority to consult with appropriate persons or institutions to
revise the administrative procedures for the use of radioactive materials as circumstances warrant.
The Permit Holders will be held responsible at all times for all aspects of radiation safety in areas under
their supervision. Assistance from the Site Radiation Safety Officers (SRSOs) and the Radiation Safety
Officer (RSO) will be available for monitoring and inspection, including procedures such as laboratory
relocation and decommissioning.
Permit Holders must also provide adequate training for employees under their supervision in the proper
use, handling and storage of radioactive materials.
Permit Holders must conform to conditions of the internal permit and the Radiation Safety Manual issued
by the RSO and the Radiation Safety Committee, and maintain adequate security of all laboratories under
their supervision. Failure to comply will result in the cancellation of the permit by NRCan's Radiation
Safety Committee.
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1.2
Organizational Management Structure
1.3
Radiation Safety Committee
The members of the NRCan Radiation Safety Committee are, in part, SRSOs who are appointed by senior
management in each building site. Special advisors will also sit on the Radiation Safety Committee to
provide technical advice as required by the committee on such areas as training, radiation safety
information, monitoring for contaminates and other issues as they develop. All members will have
professional experience and expertise in the use of radioactive materials.
The RSO will provide secretarial support for the committee and co-chair the committee with the sector
senior management appointee.
Research work using radioactive material is carried out and devices capable of producing ionizing
radiation are used at NRCan facilities. All work with ionizing radiation, regardless of how small a radiation
dose is received, is regarded as a potential risk to health. The rules and regulations established are
designed to minimize exposure to ionizing radiation, ensure safe working conditions and provide for the
protection of the environment. The NRCan Radiation Safety Committee is committed to the concept of
ALARA where all radiation exposures are kept As Low As Reasonably Achievable.
In Canada, the possession and the use of radioactive materials is governed by the Canadian Nuclear
Safety and Control Act administered by the CNSC. The CNSC has requested that NRCan be granted a
Nuclear Substances and Radiation Devices Licence for the consolidated use of nuclear substances. The
ADM, CMS, authorizes the Radiation Safety Committee for NRCan to administer this licence and to be
responsible to the ADM for all aspects of radiation safety at NRCan.
Ensuring compliance with the terms of federal regulations for the procurement and management of
radioactive materials within NRCan is therefore the exclusive responsibility of the NRCan Radiation Safety
Committee.
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1.3.1
Duties and Responsibilities of the Radiation Safety Committee
Regulations require that each licence have a Radiation Safety Committee with sufficient authority to
implement and enforce the radiation safety program encompassing the department's ordering, usage,
handling, monitoring, storage and disposal of radioactive materials. The committee shall also have the
authority to recommend the suspension, when necessary, of the use of any radioisotope or
radiation-producing devices regardless of the source of authorization. The Radiation Safety Committee
shall be appointed by the ADM and have the following responsibilities:
1. Establish and review the training and experience requirements for users of radioactive materials to
ensure that they are able to perform their duties safely and in accordance with the licensee's radiation
safety program and regulatory requirements;
2. Ensure that appropriate equipment and facilities exist and are in compliance with CNSC regulatory
requirements;
3. Ensure that there are sufficient resources allocated to the radiation safety program;
4. Ensure that the doses of ionizing radiation received by any person involved with the use of
radioisotopes do not exceed the limits specified in the Radiation Safety Regulations and be kept as
low as reasonably achievable (ALARA principle);
5. Develop policies with respect to the safe use of radioactive materials and techniques capable of
producing hazardous emissions, including X-rays, lasers, electromagnetic radiations, such as
microwave, and other potentially hazardous emissions such as ultrasound;
6. Advise the Permit Holder of the committee's policies and of the special requirements relating to
research and transport of the above materials and devices;
7. Receive reports from the RSO and make recommendations concerning the actions to be taken on
specific aspects of radiation matters as they arise or any remedial action to correct any deficiencies;
8. Advise on the development of appropriate procedures for the handling of emergency situations
relating to radiation within the department;
9. Serve on behalf of the department as reviewing agency for all permits for radioisotopes;
10. Provide, as required to the department and to external agencies, reports on
(a) situations and activities involving radiation, and
(b) all radiation incidents and accidents that require reports on safety aspects;
11. Maintain a program to ensure that all persons whose duties may require them to work in the vicinity of
radioactive material are properly instructed;
12. Review the designation of any person to be considered as a "nuclear energy worker" under the
regulations that has occurred on a semi-annual basis;
13. Be available for consultation on problems dealing with radioactive materials and radiation hazards;
14. Review the entire radiation safety program at least annually to determine that all activities are being
conducted safely and in accordance with the Canadian Nuclear Safety and Control Act and the
conditions of the licence;
15. Maintain written records of all meetings, actions, incidents or unusual occurrences, recommendations
and decisions, and supply the CNSC with a copy of these, as well as an annual report; and
16. Invoke sanction, including suspension or revocation of internal permits, as necessary.
See Annex A, "Radiation Safety Committee Terms of Reference."
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1.3.2
Radiation Safety Committee Members
Currently, the committee is composed of the members listed on the NRCan intranet
<wwwint.nrcan.gc.ca/ci/ems/3/r-ssemdc-e.htm#rad-com>.
1.4
Duties and Responsibilities of the Radiation Safety Officer
The RSO shall administer the Nuclear Substances and Radiation Devices Licence issued to NRCan by
CNSC by overseeing and managing all aspects of radiation safety within the institution. The RSO will act
as the liaison for NRCan with other organizations, as well as the Radiation Safety Committee and users.
1.4.1
Institutional Duties and Responsibilities
With respect to the institution, the RSO shall
1. act as the agent of the institution with respect to licensing matters;
2. be available to radioisotope users as a backup to the SRSOs and Permit Holders; this information will
be provided to all Permit Holders;
3. establish, implement and maintain a radiation safety control and assessment program in conjunction
with the Radiation Safety Committee;
4. systematically and periodically review survey programs for radiation and contamination levels in all
areas where radioactive materials are used, stored or disposed of;
5. establish and conduct internal inspections as designated under the licence conditions and participate
in inspections requested by CNSC;
6. ensure that a personnel monitoring program is implemented including bioassays, when applicable;
7. ensure radiation safety instruments are available in sufficient number, and are calibrated and serviced
as required;
8. conduct an annual review of occupational radiation exposures and recommend ways of reducing
exposures in the interest of the ALARA principle;
9. supervise decontamination procedures as required;
10. provide waste disposal procedures in accordance with conditions of the radioisotope licence;
11. ensure necessary leak testing of sealed sources is performed;
12. control the purchasing, use and disposal of radioactive materials via enforcement of conditions of
internal permits;
13. ensure appropriate radiation safety training is provided on a regular basis as part of an ongoing
radiation protection awareness program for all users and for those who occasionally come into contact
with radioactive materials (e.g., cleaning staff, maintenance people);
14. maintain required records;
15. ensure that each internal permit is amended when necessitated by changes to facilities, equipment,
policies, isotopes, conditions of use, procedures or personnel;
16. coordinate the development of plans to be used in the case of an emergency involving radioactive
materials;
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17. investigate all overexposure, accidents and losses of radioactive materials, and report to the CNSC
when necessary; and
18. grant approval for use of radioisotopes to users only if the use will comply with all regulatory,
environmental and institutional requirements, and ultimately deny the use of radioactive materials
given sufficient cause.
1.4.2
Radiation Safety Committee Duties and Responsibilities
With respect to the Radiation Safety Committee, the RSO shall
1. function as the link between the Radiation Safety Committee and Permit Holders within the institution;
2. prepare and review in consultation with the Radiation Safety Committee a comprehensive radiation
safety manual;
3. have input in matters pertaining to
(a) facility and equipment design,
(b) work practices and procedures,
(c) waste storage and disposal management,
(d) evaluation, issuance and enforcement of internal permits,
(e) the invoking of sanctions required by non-compliance, and
(f) radiation safety training;
4. prepare in consultation with the SRSOs an annual report to the CNSC according to licence
condition; and
5. receive a report on any survey programs pertaining to contamination levels in all areas where
radioactive materials are used, stored or disposed of, as applicable.
1.5
Duties and Responsibilities of the Site Radiation Safety Officer
The SRSO is the contact for the Permit Holders and users under the SRSO's direction and coordinates all
aspects of radiation safety according to the conditions of the internal permits for sites within the building in
which they are located. If the SRSO relocates, he or she will ensure that the RSO is notified and another
SRSO will be appointed to carry out the SRSO duties.
The SRSO should be limited to a maximum of 10 room sites. If additional sites are licensed, additional
SRSOs may be appointed.
The SRSO shall
1. participate in and attend the Radiation Safety Committee meetings;
2. be available to radioisotope users effectively on a full-time basis;
3. maintain a radiation safety control and assessment program in conjunction with the Radiation Safety
Committee;
4. review with the RSO survey programs for radiation and contamination levels in all areas within their
mandate where radioactive materials are stored or disposed of;
5. participate with the RSO in internal and external inspections as per licence conditions;
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6. ensure that current users are using an appropriate monitoring program including bioassays, when
applicable;
7. review internal permits and instruct Permit Holders to register new equipment prior to ordering or
receiving of equipment; this will include monitoring of permit updates in advance;
8. monitor records to ensure that all equipment identified for disposal has been properly decommissioned
and disposed of in accordance with licence conditions; this will include providing the information to the
RSO to update permit;
9. participate in the development of an appropriate radiation protection training program and ensuring
that participation under the licence conditions are met as required; and
10. monitor each incident or accident that is reported and when necessary either investigate or contact the
RSO for additional investigation of the incident or accident; this includes any accidental exposures.
1.6
Duties and Responsibilities of Permit Holders
The internal permits will be issued to one individual, the Permit Holder, who will be responsible for the
monitoring of all functions within the designated area that fall under compliance with the licence. Permit
Holders must have experience in the handling of radiation-emitting sources and materials. They are
responsible for the location identified on the permit.
The Permit Holder shall
1. ensure that the conditions on the permit are fulfilled and ensure compliance with policies and
procedures of the Radiation Safety Committee and CNSC licence conditions;
2. be available to provide support to users within the permit designated area on a full-time basis and
ensure that safe laboratory practices are followed;
3. ensure that all users of radioactive material are listed individually on the permit; no users other than
those listed are permitted to use radioisotopes within the permit site;
4. maintain the radiation safety control and assessment program in conjunction with the SRSO;
5. ensure that all monitoring and other compliance protocols required under the consolidated licence are
conducted and records maintained;
6. ensure that current users are using an appropriate monitoring program, including bioassays, when
applicable;
7. ensure that all new equipment, open source material or sealed source material is registered on their
internal permit prior to receiving the material or equipment on site;
8. participate in an appropriate radiation protection training program and ensure that participation as per
licence conditions are met;
9. participate in surveys, and internal and external inspections as per licence conditions; and
10. report and follow up on any accident or incident with the SRSO for additional investigation of the
incident or accident; this includes all accidental exposures.
1.7
Duties and Responsibilities of Users Working with Radioisotopes
Each individual worker who uses radioactive material has a responsibility to ensure that safety practices in
the workplace are adhered to for their own safety and that of their co-workers. They must comply with the
Radiation Safety Committee policies and procedures and with those established for the Permit Holder's
internal permit. They shall accomplish this by
1. working in compliance with all policies, procedures and requirements at NRCan;
2. using any protective or monitoring equipment that is required for the safe use of radioactive materials;
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3. reporting to the Permit Holder or SRSO any defective equipment or violation that may endanger a
worker or create a potential unauthorized release of radioactive material to the environment; and
4. not creating or participating in any activity that may endanger themselves, any other worker or create
the potential for unauthorized release of radioactive material to the environment.
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INTENTIONALLY LEFT BLANK
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Chapter 2:
Licensing and Administration
2.1
Nuclear Substances and Radiation Devices Licence Issued for the Consolidated Use of
Nuclear Substances
The licence issued for the consolidated use of nuclear substances is a departmental licence that regulates
the purchasing, possession and use of open and sealed source material at all Natural Resources Canada
(NRCan) facilities. The licence is valid for five years from the date it is issued by the Canadian Nuclear
Safety Commission (CNSC). The renewal of this licence is processed at the request of NRCan through the
Radiation Safety Officer (RSO) in conjunction with the Radiation Safety Committee.
Qualified individual researchers are granted, under the authority of this Nuclear Substances and Radiation
Devices Licence, internal permits by the RSO for each room where radioactive materials are stored or
used. These internal permits are valid for a maximum period of five years, which does not exceed the
expiry date of the Nuclear Substances and Radiation Devices Licence issued by the CNSC.
2.1.1
Application for the Nuclear Substances and Radiation Devices Licence
The RSO, with the required information gathered from all Permit Holders and Site Radiation Safety
Officers (SRSOs), will complete the application and provide it to the Radiation Safety Committee for their
review. Once approved, it will be sent to the CNSC for renewal.
2.2
Internal Permit Application
Internal permits are required for the purchase, possession, use and disposal of sealed (including gauges)
and open source radioactive materials. This applies to all acquisitions of radioactive material, either
purchased or donated. Permits are issued only to staff currently employed by NRCan who possess
documented training and experience in the use of radioactive material.
Laboratory facilities for open source radioisotope work must be approved by the Radiation Safety
Committee and the RSO. See Form 8, "Design Compliance Form for Laboratories," in Chapter 6.
The internal permit is limited to the radioactive materials listed and only covers the use of these materials
within the designated areas. If the radioactive material is being transported to another site within the
facility, the new location must also have an internal permit that covers the radioactive material accordingly.
If the radioactive material is being transported to another site within the building or to another building site
within NRCan, the SRSO must be notified for approval. If the radioactive material is being transferred to
another institution (e.g., university or other government department), the RSO must be contacted for
approval or information concerning the transfer.
If the radioactive material is being transported for use at another location (sites across Canada), an
internal permit with the appropriate information will be granted to each vehicle (or pool of vehicles) used
for transporting.
To apply for an internal permit, see Form 4, "Application for Internal Permit," in Chapter 6.
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2.3
Internal Permit
Following the approval of the application, an Internal Radioisotope Permit is issued to each laboratory or
vehicle, with a designated Permit Holder for each permit. All personnel using radioactive material must be
listed on the internal permit. Three copies of each permit are produced: one for posting, one for the SRSO
and one for the RSO. All permits will have original signatures of the RSO, SRSO and Permit
Holders. A copy of the signed permit must be posted by the Permit Holder in the laboratory listed on the
permit. A permit is not valid unless the Permit Holder has signed all three copies. A permit is not valid
beyond the expiry date shown, unless a renewal application has been submitted.
The internal permit is divided into the following five parts:
•
Part 1 shows the internal permit number and the period during which the permit is valid. It lists the
Permit Holder's name and phone number, the sector, branch, division, the revision number of the
permit and the room number or vehicle number. The radioactive material must not be used or
stored in a location not listed on each permit. This section also contains the name and phone
number of the contact person in case of emergencies, and the names and phone numbers of the
SRSO and the RSO.
•
Part 2 lists all radioisotopes that may be in the possession of the Permit Holder. Devices containing
sealed source material, the isotope type of device and activity for open source material, the isotope
and the delivery rate of the material are specified. The rate of delivery must not be exceeded.
Radioisotopes not listed on the permit must not be purchased or obtained by the Permit Holder.
•
Part 3 lists users approved for work with radioisotopes. Each of the users must be properly trained
and have read this manual. Any changes to this list, including the names of students, must be
communicated to the RSO for appropriate authorization.
•
Part 4 lists the conditions specific to the individual internal permit. Permit Holders and staff should
ensure that they have read, understood and followed all of the permit conditions.
•
Part 5 contains a statement affirming that by signing, the Permit Holder agrees to the terms and
conditions under which the permit is issued.
No changes may be made to the permit without prior approval by the RSO or Radiation Safety Committee.
This includes changes to the rooms, buildings, users, isotopes ordered or the quantity permitted. To
change any part of the permit, an application for a permit amendment must be submitted (see Form 5,
"Application for Internal Permit Amendment," in Chapter 6).
2.4
Status of Permit Holder on Long-Term Leave
A permit is granted on the grounds that the Permit Holder is aware of and responsible for the activities
within the designated area. If a Permit Holder takes a long-term leave of absence or a long-term medical
leave, arrangements must be made prior to the leave, or as soon as it is established that the absence will
be extensive. The management, the SRSO and the RSO must be individually notified in writing of this
change.
Any Permit Holder acting on behalf of another Permit Holder is responsible for all activities under both
permits and will be subject to any necessary compliance enforcement.
2.5
Amendment of an Existing Permit
To amend an existing permit, an "Application for Internal Permit Amendment" (Form 5 in Chapter 6) must
be completed and forwarded to the SRSO and the RSO. The application must also include the reason for
the change, and the current internal permit number. The form must be signed by the Permit Holder.
Permit amendment requests may not be signed on behalf of the Permit Holder.
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The Permit Holder may not implement the requested changes until the permit amendment has been
approved. Following approval of the amendment, a revised permit will be issued.
Note: The five year period for the permit begins from the date the original permit was issued, not
from the date the amended permit is issued.
If the Permit Holder is unable to request a particular amendment, the manager of the Permit Holder can
request it. The request must briefly describe the reason for the change of applicant.
2.6
Renewal of an Existing Permit
Permit renewals (Form 6, "Application for Internal Permit Renewal," in Chapter 6) are initialized by the
RSO. A permit renewal form is sent to each current Permit Holder. The Permit Holder is required to
complete all requested information, sign the application and obtain the signature of the SRSO to complete
the form.
The permit renewal application will indicate the date by which the form must be returned. Failure to return
the renewal application by this date may cause disruption in the work with radioisotopes, as no purchase
or use of radioactive material is permitted without a valid permit.
If a permit renewal application request is not received by the expiry date of the current permit, it is
automatically assumed that the Permit Holder has requested that the permit be cancelled. At this
point, the RSO will contact the SRSO and the Permit Holder for decommissioning of the laboratory and
removal of any remaining radioactive material.
If a Permit Holder is not currently using or storing radioisotopes and their use is not foreseen in the
immediate future (six months), it is recommended that the permit be cancelled and the room
decommissioned. New permits can be issued upon request when a future need arises.
Following approval of the permit renewal, a new permit is issued with a term corresponding to the renewed
Nuclear Substances and Radiation Devices Licence. If the new permit has not arrived prior to expiry date
of the current permit, Permit Holders who have an approved permit renewal application on file at the time
of expiry will not be affected by any purchasing or use restrictions.
2.7
Radioisotope Laboratory Approval
All rooms intended to be used for the handling, storage or disposal of more than one scheduled quantity of
an open source radioactive material, must conform to the requirements of the CNSC Regulatory
Document R–52, Design Guide for Basic and Intermediate Level Radioisotope Laboratories, which applies
to all new or renovated facilities designed after January 1, 1986.
Any area in which radioactive material has been previously used may have an approval on file and an
inspection may not be required. Where extensive renovations or modifications have been carried out
within the area, an inspection must be completed prior to issuing of the permit.
Any area that has not been used for storage or handling of radioactive material, including new or
renovated laboratory facilities, will require an inspection by the SRSO or the RSO to ensure compliance
with the Regulatory Guide. A "Design Compliance Form for Laboratories" (Form 8 in Chapter 6) is
completed for the proposed room and approval is based on the existence of the control factors required on
the form.
If a laboratory does not meet the requirements for a basic-or intermediate-level designation (see Annex E,
"Laboratory Classification," for requirements), it may require modification prior to approval.
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2.8
Cancellation of an Internal Permit
Cancellation of a permit may be required because of a change in the activities or staffing within the area,
or because of a change in methodology. A permit may also be cancelled at the time of permit renewal. If
no current requirements for a radioisotope permit exist and the Permit Holder has no immediate plans to
resume this activity, it is recommended that the permit be cancelled until the need to resume work with
radioisotopes arises. The permit may be reactivated if the need arises in the future. Note: If radioisotopes
are being stored or instruments with radioactive sources are being retained, then a permit will have to be
maintained.
To cancel the permit, a "Decommissioning Records" form (Form 7 in Chapter 6) must be completed and
forwarded to the RSO, and copied to the SRSO requesting the permit cancellation. A complete copy of the
final contamination survey with a detailed diagram of the test sites must be attached, as outlined in the
"Decommissioning Policy" (Section 3.12).
If special disposition of any radioisotope material held under the permit is required, this must be noted in
the decommissioning records form (e.g., transfer of radioactive material to a new location, transfer of
instruments or disposal confirmation).
2.9
Purchasing and Receiving Radioactive Material
The purchasing of radioactive materials must be done with management's approval. All orders and
requisitions must be copied to the SRSO. The SRSO will then forward the records to the RSO on an
annual basis or upon request. The RSO will retain all records for six years as required by the CNSC or the
period specified, or for the period ending one year after the expiry of the licence that authorizes the activity
in respect of which the records are kept. All purchase orders must have the permit number on the
requisition. A copy of the purchase order, packing slips, Transportation of Dangerous Goods (TDG)
documents and any other documents associated with the order must be attached to the inventory sheets
(one sheet per vial; see Chapter 6 for Form 1, “Open Source Inventory Sheet,” and Form 2, “Sealed
Source Inventory Sheet”). The purchase order information may be used as a source of information for
inventories during inspections (see Section 3.8, "Receiving Radioactive Material").
2.10
Special Orders
Special orders, including standing orders, special gifts, transfer, exchanges, must be approved by the
RSO, prior to delivery of the material. This will ensure that all licence conditions are met. If any changes
are required for the permit, this will ensure that it is completed prior to the delivery of material.
2.11
Inventory Procedures
The following procedures should be followed to keep an inventory of radioactive materials:
1. All isotopes received are to be entered, one purchase per sheet, on inventory sheets (Form 1, "Open
Source Inventory Sheet," and Form 2, "Sealed Source Inventory Sheet," in Chapter 6). Subsequent
use and disposal are entered on the same sheets as soon as the isotope is used.
2. All purchase orders must be kept with the inventory sheets.
3. Each Permit Holder must maintain a complete inventory of radioactive materials in use and in storage.
4. Inventories are to be up to date and available for inspection by the RSO or the CNSC.
5. All inventory records must be kept for a minimum of six years or another specified period, or for the
period ending one year after the expiry of the licence that authorizes the activity in respect of which
the records are kept.
6. Total inventory for each isotope must not exceed permit requirements.
7. The cumulative inventory and disposal records are summarized annually.
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2.12
Compliance Inspection Policy
Compliance inspections are required to be conducted internally under the Radiation Safety Program. The
internal inspections will be conducted annually for sites using and storing open source material and every
two years for sealed source materials (as of 2004). The internal inspections may be more frequent if
necessary. The SRSOs and RSO will visit each lab to which an internal permit is issued. The visits will be
announced and at times unannounced.
The compliance inspections are generally based on the CNSC’s Risk-based Regulatory Program,
whereas legislative requirements are rated (from exceeding requirements to unacceptable) depending on
the risk associated with the requirement. The levels of risks are
1. High: immediate health, safety or security risk;
2. Medium: health, safety or security risk, but not immediate; and
3. Low: no health, safety or security risks; administrative issues only.
Annex B, a comprehensive “Internal Inspection Checklist,” will be used. In general, items of compliance
that will be reviewed during an inspection include, but are not limited to
1. administrative requirements (e.g., permit posting, training, personnel monitoring, signs and posting
of rules);
2. record keeping (e.g., monitoring, inventory, purchasing, etc.);
3. storage and handling in labs (e.g., in laboratory storage, work area safety and security);
4. protection (e.g., laboratory coat, gloves and shielding);
5. spills and contamination (e.g., procedure and cleaning);
6. waste disposal and storage sites (e.g., long-term disposal and short-term storage, other than in a
laboratory); and
7. training.
Violations will be categorized as either major, moderate or minor offences, depending on the risk
associated with the violation.
2.12.1
Major Offences
A major offence (high risk) results from violations that cause immediate risk or danger to health or safety,
that release reportable quantities of radiation to the environment, that expose staff to substantial doses or
that place the departmental licence for the consolidated use of nuclear substances in jeopardy. Examples
of a major offence include
1. contamination above licence criteria;
2. inadequate monitoring program;
3. use or storage of food or drink in the laboratory;
4. inadequate training of new staff;
5. non-participation in required bioassay programs;
6. inadequate or unsafe work and storage areas for radioisotopes; or
7. inadequate or unsafe storage areas for radiation waste.
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2.12.2
Moderate Offences
A moderate offence (medium risk) results from violations that can bring about a health, safety and security
risk, but the risk is not immediate. Examples of a moderate offence include
1. inadequate training records;
2. contamination or survey meters not calibrated; or
3. changes to the SRSO, Permit Holders or users not reported to the RSO within 15 days.
2.12.3
Minor Offences
A minor offence (low risk) is an infraction that poses no immediate risk or threat to health, safety, the
environment or the licence. Examples of a minor offence include
1. inadequate posting (e.g., internal permit, CNSC posters);
2. inadequate inventory records;
3. inappropriate use of warning labels; or
4. routine leak testing not followed.
2.13
Compliance Enforcement Policy
NRCan is issued a Nuclear Substances and Radiation Devices Licence for the consolidated use of nuclear
substances by the CNSC for the possession, use and import of radioactive prescribed substances or
devices containing radioactive prescribed substances. Since this licence is a single licence and
cancellation of the licence would result in all work involving radioactive material within NRCan being
suspended, it is essential that there be a procedure and policy in place to deal with non-compliance. Upon
issue of this licence, NRCan assumes the responsibility to ensure that any use of radioactive prescribed
substances on all NRCan sites complies with the CNSC Nuclear Safety and Control Act and its
regulations, as well as all conditions that apply to the licence.
Failure to comply with a policy or procedure established by the Radiation Safety Committee will result in
the actions described in the following subsections.
2.13.1
Major Offence Actions
Items of serious non-compliance that would place the NRCan licence in jeopardy will be dealt with
immediately. This will include any situation that is considered an immediate risk to health and safety. The
RSO and the SRSOs have the power to suspend operations or cancel the permit. The RSO will provide a
report of this action to the Radiation Safety Committee, senior representative for the Assistant Deputy
Minister (ADM), SRSO, and to the Director, Security, Safety and Emergency Management Division.
On the first offence, the Permit Holder will be notified in writing of the offence and the required action to
correct this offence. Immediate attention and correction of the violation is required.
If a second occurrence of an offence recurs within a year or the Permit Holder fails to correct the first
offence, the Permit Holder will be notified in writing that the permit will be revoked until a meeting can be
held with the Radiation Safety Committee. The Permit Holder may attend the meeting to explain why the
permit in question should be renewed.
If a third occurrence of an offence recurs within a year, the permit will be transferred to the Permit Holder’s
manager and all work will have to be conducted under the control of the Permit Holder’s manager. All
purchases of radioactive material will require the approval of the manager. The Radiation Safety
Committee will review the permit and make recommendations to the manager in writing.
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2.13.2
Moderate and Minor Offence Actions
Moderate offences must be corrected within 14 calendar days. Minor offences must be corrected within 28
calendar days.
On the first occurrence, the Permit Holder will be notified verbally by the RSO or the SRSO of the violation
observed.
If a second occurrence of an offence recurs within a year or the Permit Holder fails to correct the first
offence, the RSO will send written notification of the observed violation to the Permit Holder, with a copy to
the manager of the Permit Holder.
If a third occurrence of an offence recurs within a year, the RSO will arrange to transfer the permit to the
manager of the Permit Holder. If the manager agrees to assume the responsibility, all work will be under
his or her direct control. In this case the manager’s name and signature must appear on all purchase
requisitions. Written notification of the above action will be sent to the Radiation Safety Committee.
If a fourth occurrence of an offence takes place within a year, the Permit Holder’s manager will be required
to show cause to the Radiation Safety Committee why the permit should not be revoked. A report of this
action detailing the Radiation Safety Committee’s recommendations will be prepared and provided to the
senior representative for the ADM. If the permit is revoked, the radioactive material will be removed from
the area and disposed of or locked up for retention until the violations are rectified to the satisfaction of the
Radiation Safety Committee.
2.14
Annual Compliance Report
The NRCan Nuclear Substances and Radiation Devices Licence includes the condition that the licencee
submit an annual report. This report is intended to keep the CNSC advised of the current status of the
licence, and the circumstances, operations, performance and authorized activities that are related to the
care and control of radioactive materials and devices.
The RSO, in consultation with and with the assistance of the SRSOs, will prepare the annual report and
submit it to the CNSC by the required due date. The annual report will contain some of the following
information:
1. A summary of the major activities over the reporting year and any anticipated future change to the
radiation safety program;
2. Copies of the minutes of the Radiation Safety Committee meetings or meetings of other groups;
3. A listing of all internal permits;
4. A brief review of internal compliance activities, including the inspection schedule and results;
5. A summary of acquisitions, transfers and disposal of any radioactive materials or devices;
6. Copies of occupational radiation doses; and
7. A summary of investigation conducted, and incidents or significant occurrences, along with
descriptions of the consequences and any remedial action.
2.15
CNSC Approval for Special Projects
Authorization for projects involving unsealed nuclear substances that are in a quantity of more than
10,000 times any exemption quantity will be issued only after obtaining a written approval from the CNSC.
Contact the RSO to begin the process of obtaining approval.
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Chapter 3:
Policies and Procedures
3.1
New Policies and Procedures
The Radiation Safety Committee and the Radiation Safety Officer (RSO) may impose additional
requirements, as necessary, which will be issued in the form of new or revised policies or procedures.
These policies and procedures will not be effective until they are reviewed and approved by the Radiation
Safety Committee. After being approved and finalized, these new policies and procedures will be
distributed to all Permit Holders by e-mail and the Radiation Safety Manual will be revised. The Permit
Holders will be responsible for ensuring that the users listed on the permit are notified of new or revised
policies and procedures.
3.2
ALARA Policy
It is the policy of Natural Resources Canada (NRCan) that all activities involving ionizing radiation or
radiation-emitting devices be conducted so as to keep hazards from radiation to a minimum. Radiation
doses to all staff and the public during routine use of radioactive materials or operation of
analytical X-ray equipment, and in the case of an emergency, must remain As Low As Reasonably
Achievable (the ALARA principle).
A high standard of radiological safety will be maintained at all times in the work environment.
All activities that use radioisotopes will be appropriately licensed by the Canadian Nuclear Safety
Commission (CNSC). NRCan is committed to the achievement of compliance in accordance with the
relevant regulations and licence conditions. The holder of any such licence will ensure that all conditions of
the licence are fulfilled on behalf of the department. Persons involved in these activities are expected to
comply fully with the Nuclear Safety and Control Act and its regulations and with the Occupational Health
and Safety Act and its regulations regarding X-ray sources, lasers and sound.
3.3
Designation of Nuclear Energy Workers Policy
The General Nuclear Safety and Control Regulations and the Radiation Protection Regulations require
that nuclear energy workers (NEWs) be notified of their status as NEWs and all associated implications,
including risks related to the radiation to which NEWs may be exposed, applicable effective dose limits,
typical dose levels received and the NEWs' rights and obligations. (See Table 4.5, "CNSC Annual Limits of
Exposure for NEWs and Members of the Public," in Section 4.2.2, “External Radiation Exposure.”) If
operational requirements make it essential that a user becomes a NEW, the Site Radiation Safety Officer
(SRSO) must contact the RSO.
3.4
Food and Drinks in a Radioisotope Laboratory Policy
The storage or consumption of food and beverages in any laboratory, including radioisotope laboratories,
at NRCan, is prohibited under any circumstances. The prohibition against eating, drinking or the
application of cosmetics in a radioisotope laboratory is used to prevent the accidental ingestion of
radioactive material.
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3.5
Room Designating and Posting Policy
Radioisotopes have been classified into different levels depending on the nature and amount of
radioactive material being handled within the facility (see Annex E, "Laboratory Classification"). The
classification of a radioisotope laboratory does not involve the amount of radioactive material stored in the
laboratory but rather the amount of material handled. In all cases, once designated, the classification of
each laboratory must be posted. The classification is as follows: storage, basic level, intermediate level,
high level and containment. These posters provide a list of safety work practices to be followed when
working in these rooms:
1. Basic Level: Use of Unsealed Nuclear Substances (INFO-0728-1);
2. Intermediate Level: Use of Unsealed Nuclear Substances (INFO-0728-2); and
3. High Level: Use of Unsealed Nuclear Substances (INFO-0728-3).
It is also NRCan's policy to have durable and legible radiation warning signs posted at the boundary of,
and at every point of access to, an area, room or enclosure where there is a quantity of nuclear substance
greater than 100 times its exemption quantity, or if there is a reasonable probability that a person will be
exposed to a radiation dose rate greater than 25 :Sv/h. Permit Holders are obliged to post the name or job
title and telephone number of a person who, in case of an emergency, can initiate the appropriate
procedures referred to on a permit and who can be contacted 24 hours a day.
Internal permits are also posted at all laboratories and storage areas. A copy of the internal permit must
also be found in vehicles transporting any radioactive substances.
A radiation warning sign meeting Workplace Hazardous Material Information System guidelines is also
affixed to the entrance to rooms containing radiation-producing equipment or where radioactive materials
are used or stored.
3.6
Access, Control and Security Policy
NRCan has building security for each site consisting of Commissionaires during core hours. In order to
enter the building a government ID pass with a picture ID must be shown. If the individual does not have a
pass they must identify who they are visiting and the employee must come to the security desk and sign
them in. The visitor is issued a visitor pass and must be accompanied by an NRCan employee at all times
when in the building.
3.6.1
Basic Laboratories
The radioactive material in open source and mobile sealed source material must be secured at all times
when not in use. Storage areas, fridges, freezers, cabinets, etc. must be locked. This requires either the
room or the storage area, that has designated radioactive material within, to be locked. Small lock boxes
(metal cases, lockable diskette cases, etc.) can be purchased and secured to a bench or inside a fridge to
prevent unauthorized access to the radioactive material.
If you have any questions on securing your radioactive material, contact your SRSO or the RSO.
3.6.2
Intermediate Laboratories
The radioactive material in open source and mobile sealed source material must be secured at all times
when not in use. Storage areas, fridges, freezers, cabinets, etc. must be locked. This requires either the
room or the storage area that has designated radioactive material within be locked.
The basic premise of this policy is that the radioactive material will remain secured at all times.
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3.6.3
Control of Nuclear Substances Policy
All internal Permit Holders will maintain an inventory, and will report all activity related to their holdings,
including the results of CNSC inspections to the RSO. Special written procedures for the handling, testing,
transportation, use, and disposal of radioactive materials will be prepared as required by the Permit
Holders, and copies retained by the RSO.
3.6.4
Theft of Radioactive Material
The theft or other loss of radioactive material must be reported to the SRSO and, because this is a
serious offence, to the RSO at the Security, Safety and Emergency Management Division
immediately. This applies regardless of whether the incident was reported to the police.
After a suspected theft or other loss, it is important to know the amount of material that may be missing.
This is one reason for inventory records. All inventory records must be available for inspection by the RSO
or other regulatory authorities. Any other particulars involving the material should also be reported.
If significant quantities of materials are involved, the CNSC may have to be notified. In that event, contact
the RSO for further information.
3.7
X-ray Producing Equipment
All X-ray producing equipment must be used in accordance with the procedures described by the
manufacturer. It must also comply with the appropriate safety code.
The X-ray equipment used for experimental purposes is essentially an irradiator in which the useful beam
is confined to a specific direction, shape and size by means of slit, cone, diaphragm or other collimating
device. Where possible, the useful beam should be permanently directed into an enclosed and shielded
box into which the object to be irradiated can be inserted. The door or lid of the box should be interlocked
with the power switch of the X-ray machine. The dose rate outside the box should be such that, taking into
account the workload of the X-ray machine and the occupancy of the surrounding area, the annual dose
limits for NEWs are not exceeded. Workers who are not NEWs should be excluded from the immediate
vicinity of the X-ray machine during the whole of any period in which the machine is in use.
Notwithstanding any shielding and interlocking arrangements, users should take great care to avoid
exposing any part of their bodies to a direct X-ray beam. This is particularly important in the case of X-ray
diffraction units, where a narrow but very intense beam needs to be manipulated under manual control.
All equipment capable of producing ionizing radiation is registered with Environmental and Workplace
Health at Health Canada. A list of all registered equipment is maintained by the SRSOs, as applicable,
and the RSO. Analytical X-ray equipment is subject to testing for radiation leakage by the Environmental
and Workplace Health. The SRSOs will monitor the schedule of the testing and inspections by Health
Canada.
All such equipment must also be checked for radiation leakage upon installation and after any major repair
that could interfere with the safety interlocks. Although only open-beam X-ray equipment is capable of
exposing workers to radiation under normal operating conditions, all employees who use analytical X-ray
equipment will be monitored through dosimetry. The SRSOs will retain a copy of the thermoluminescent
dosimeter (TLD) results and will monitor the results to ensure there is no overexposure.
Any personnel suspected of overexposure or who registers above the allowable limits on their TLDs are
required to stand down from further duty with radioisotopes until an internal investigation has determined
the cause and appropriate followup has been undertaken and finalized.
3.8
Receiving Radioactive Material
At NRCan sites radioactive material is received in stores or by hand delivery through the security area at
the front entrance.
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3.8.1
Responsibilities for Receiving Material
If the material is received at stores, it will either be delivered to the laboratories or Permit Holders will be
notified to collect the material immediately. If the package is delivered to the security area, the Permit
Holder or a laboratory employee will be notified to collect and sign for the package.
3.8.2
Procedures for Receiving Packages
All packages are opened in the laboratory area by authorized personnel using the Receiving Radioactive
Packages procedures (SRSO INFO-0426), as follows:
1. Wear a lab coat and disposable gloves while handling the package.
2. Examine the package for leaks, damage and so on.
The procedures for handling damaged or leaking packages would be the same as for other packages
if an incident has occurred. In such cases, the package is always accepted from the carrier as NRCan
has the facilities and the expertise to control the incident. Spill procedures would be followed for
incidents of this type.
For damaged packages received under the Transportation of Dangerous Goods (TDG) Regulations,
both the original shipper and the carrier is contacted. If additional information concerning TDG
regulations is required, contact Transport Canada (see Annex C, "Emergency Contact Lists").
3. Open the package on a lined bench top (when opening iodine 125, open in fume hood).
4. Check for dry ice, if applicable. Return if no dry ice is present, as shipment may be spoiled.
5. Remove containers and place them behind appropriate shielding, if necessary (for phosphorus 32, use
Plexiglas, for iodine 125 use lead).
6. Open containers, remove contents and check labels against the order (quantity and contents).
7. Check vials for damage such as cracks, broken lids, seals, leakage and so on.
8. If there is damage, perform a wipe test of the lid of the vial and where the lid screws on (see
Section 3.11.2.1, “Wipe Test Procedures”). Also perform a wipe test on the outside and interior of
the box.
9. Count all wipe tests using a liquid scintillation counter. If the wipe test shows gross contamination of
the vial (more than several times above background), inform the SRSO.
10. The exterior box should be disposed of in the radioactive waste (<1 Eq) and must never be reused.
11. File a copy of all wipe tests with the purchase order.
3.9
Packaging and Transporting Radioactive Materials
All NRCan personnel who are required to transport any radioactive materials over public roadways must,
in accordance with the CNSC licensing requirements, do so in compliance with the TDG regulations and
any other related provincial regulations as required.
To meet these requirements all persons transporting radioactive material must
1. certify that they have read and understood this chapter;
2. successfully completed a competency check (transportation); and
3. possess a TDG certificate of training issued by the employer.
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Persons requiring a TDG certificate of training should contact the SRSO for further information. The holder
of the TDG certificate will be responsible for ensuring that the certificate is renewed as required. The
following procedures must be followed in the shipping of radioactive material:
1. When sending radioactive material, make proper arrangements for receipt of the package at the other
end. The new location must be licensed for the appropriate radioisotope by the CNSC.
2. When taking radioactive material to and from a field site, keep it in its shipping container and in an
unoccupied part of the vehicle, such as the trunk or back of the truck canopy.
3. Lock the vehicle or canopy when the material is in it and ensure the material is out of sight.
4. Gauges must be transported in their shipping containers to conform with federal regulations on the
transport and packaging of radioactive materials.
5. A shipping manifest must be completed each time a gauge is to be transported. This will include the
shipper's (user's) name, date and reference number. The SRSO will keep a log of all vehicles
transporting any radioactive materials.
6. The vehicle must also have a copy of the internal permit while in transit.
7. A copy of the completed shipping manifest must be faxed to the appropriate emergency contact
service company each time a gauge is to be transported. A copy of this shipping manifest must also
be retained by the SRSO while the gauge is being transported.
8. A single, Class 7 placard must be attached to the shipping manifest or documents at all times. The
shipping manifest or documents must be kept in a visible location in the cab of the vehicle at all times
when the gauge is present.
9. Whenever the gauge is removed from the vehicle for extended periods, the placard and shipping
manifest must also be removed from the vehicle.
10. When the trip is completed, the original shipping manifest indicating the return date of the gauge must
be filed appropriately.
3.10
Monitoring
Monitoring is an essential component of any radiation safety program. It involves the regular and routine
measurement or assessment, or both, of factors relevant to radiation safety.
3.10.1
Personal Dose Monitoring Policy
Dose monitoring and recording is carried out in accordance with the CNSC Regulatory Guide G–91,
Ascertaining and Recording Radiation Doses to Individuals. It is the responsibility of the Permit Holder to
ensure that new employees and those beginning work with radioisotopes are included in the TLD
radiation-monitoring service, as required.
External radiation exposures are to be measured using dosimeters provided by a licensed dosimetry
service. Dosimeters should be properly worn and stored, and examined regularly to make sure that
readings are accurate. Finger or ring dosimeters must be worn when handling more than 50 MBq of
high-energy beta-emitting nuclear substances and should be worn when working behind bench shields.
A personal dosimeter, registered with Health Canada, will be provided by the SRSO or designate, to all
employees who use radioactive materials as required or operate open-beam X-ray-generating equipment.
Results of radiation dosimetry will be retained by the SRSO and a copy of quarterly reports provided to all
dosimeter holders or upon request. Radiation-monitoring results for each individual are also recorded in
the National Dose Registry operated by Health Canada.
Personal protective equipment, including protective clothing, masks, gloves and other equipment as
required, will be provided to all staff who work with radioactive materials.
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Any personnel suspected of overexposure or who register above the allowable limits on their dosimeters,
are required to stand down from further duty with radioisotopes until an internal investigation has
determined the cause and appropriate follow-up has been undertaken and finalized.
3.10.2
Dosimetry During Pregnancy for Non-NEWs Policy
The annual dose limit for non-NEWs (1 mSv) is one half of the dose limit for female NEWs during the term
of the pregnancy (2 mSv). There is no special dosimetry required for non-NEWs during the term of
pregnancy. The female staff member who becomes pregnant must advise the Permit Holder in writing of
the pregnancy. The Permit Holder is required to notify the RSO immediately by e-mail.
The female staff member, with the Permit Holder and the SRSO, will review the radioactive material
handling and experimental procedures to ensure that all relevant precautionary measures are being
exercised. Proper use of protective clothing, handling techniques and location should be reviewed. All
aspects of the work with radioactive material should be reviewed to ensure that any radiation exposures
are kept as low as reasonably achievable. All recommendations will be submitted in writing to both the
employee and the Permit Holder.
3.10.3
Leak Testing of Sealed Sources Policy
Sealed sources are radioactive substances sealed in capsule or having a bonded cover strong enough to
prevent contact with and dispersion of the radioactive material under the conditions of use and wear for
which it was designed.
The Nuclear Substances and Radiation Devices Regulations require that sealed sources of greater activity
than 50 MBq be leak tested, as follows:
1. Self-shielding irradiators: every 12 months.
2. All other sealed sources: every 6 months.
3. All sealed sources continuously in storage: every 24 months.
4. After any incident that immediately could result in damage.
If more than 200 MBq of removable contamination is detected on the wipe, the source is assumed to be
leaking and shall be removed from service. Leak testing sampling and measuring procedures must be
performed according to the CNSC Regulatory Document R–116, Requirements for Leak Testing Selected
Sealed Radiation Sources.
Records of leak testing must be kept for at least six years and will be provided on a yearly basis to
the RSO.
3.10.4
Action Levels Policy
At NRCan, effective dose in excess of 1mSv (1000 :Sv) in one calendar year is in excess of the
acceptable limits. If there is an overexposure, the employee and the CNSC will be informed of the
exposure. No further work with radioisotopes will be undertaken by the employee until an investigation is
conducted to determine the cause of exposure.
If there are anomalous readings on the dosimetry reports or someone is approaching the 1mSv threshold,
that person will be informed to stand down until an investigative review of their procedures is undertaken
and corrective action has taken place.
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3.11
Radioactive Contamination Control Policy
A key component of NRCan's radiation protection program is to ensure that no worker is receiving
unnecessary exposures to ionizing radiation. One of the key elements to confirm this is accomplished in
the weekly monitoring, or after any procedure utilizing radioisotopes, by a monitoring device (see
Section 3.11.2.2, “Direct Measurement of Surface Contamination”) or wipe test (see Section 3.11.2.1,
“Wipe Test Procedures”), as appropriate, that is conducted by the laboratory staff when working with
radioactive material. This will confirm that no contamination within the area exists. Also, should a
contaminated site be identified, the Permit Holder and the user must ensure that prompt action is taken to
decontaminate the site and confirm this with additional monitoring. Prompt attention to this will reduce
exposure to radioactive material.
Permit Holders are responsible for all persons working with radioactive material in designated areas under
their control. Users of radioisotopes are responsible for employing good work practices which will minimize
the probability of contamination. The users are also responsible for monitoring their area for contamination
and for reporting all incidents, including all spills.
When contamination is identified, the user must proceed with the decontamination procedure and notify
the Permit Holder of the occurrence. The Permit Holder is responsible for ensuring that the
decontamination is carried out immediately. The SRSO and the RSO can be contacted for advice.
In all cases where contamination monitoring indicates activity above the limits defined by a licence, or
where any occupied area exceeds 2.5 :Sv/hour, immediate action will be taken by the Permit Holder to
remove the contamination or to reduce the ambient exposure to as low as reasonably achievable.
3.11.1
General Rules and Procedures
The following general rules and procedures should be followed:
1. Only use radioisotopes if absolutely necessary.
2. Good housekeeping is essential. Radiation work should be consolidated both in respect to the area
allotted for handling the radioactive materials and to the amount of time spent handling them. Limiting
the area expedites survey and decontamination procedures. Limiting the time spent in handling the
radioisotopes minimizes external radiation exposure and decreases opportunities for accidents.
3. Keep radioactive and non-radioactive work separate as far as possible, preferably by maintaining
rooms used solely for radioactive work.
4. Work over a spill tray lined with absorbent paper and in a fume hood or glove box when working with
dry powders or volatile substances.
5. Use the minimum quantity of radioactivity compatible with the objectives of the experiment.
6. Wear protective clothing, safety glasses and gloves when handling radioactive substances or devices.
7. Remove gloves, wash hands and monitor yourself before leaving an active area.
8. Work carefully and monitor the working area regularly to avoid problems with experiments due to
accidental contamination.
9. Label containers of radioactive material clearly, indicating radioisotope, total activity, date and the
level of radiation at the surface of the container.
10. Never eat, drink, smoke or apply cosmetics in an area where radioactivity is handled or stored.
11. Never work with unprotected cuts or breaks in the skin, particularly on the hands or forearms.
12. Never pipette any solutions by mouth.
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13. TLD badges should be worn accordingly and not left in the laboratory upon completion of the work.
Background dosimeters should not be taken into the isotope laboratory or stored near radioactive
materials.
14. To minimize the dose to the extremities, tongs or other remote handling equipment should be used
where appropriate.
15. Contamination monitoring must be done at least once per week while working with radioisotopes.
Records must be maintained and made available for inspection.
16. Inventories of all radioisotopes must be carefully maintained and available for inspection.
17. Glassware used for radioactive work must not be used for other purposes.
18. Always wash hands before leaving the laboratory.
3.11.2
Surface Contamination Measurements
Surface contamination can be measured through wipe tests and direct measurement with various types of
detectors.
3.11.2.1
Wipe Test Procedures
At least weekly or when work is completed, equipment, trays, floors and working surfaces must be
monitored (wipe test). All loose contamination should be removed. A record of wipe tests will be kept using
Form 10, "Wipe Test Results," in Chapter 6.
The basic principle of the wipe test consists of wiping the suspected contaminated surface with a piece of
filter paper moistened with solvent or water and then measuring the activity on the paper by placing it in a
scintillation counter. It is important to note that the wipe test can only measure removable (loose)
contamination. The following steps should be followed:
1. Select the surface to be smeared and identify the wipe by number.
2. Select an absorbent grade of filter paper with a diameter of about 5 cm (qualitative analytical grade is
suitable), or a cotton-tipped application swab. Always wear gloves.
3. Moisten with either water or 50% alcohol.
4. Hold the moistened filter paper on the edge with thumb and index finger or with a tweezer and rub
lightly but firmly over the surface, and by applying light pressure try to obtain the contamination on the
centre of the paper.
5. Estimate the area that you have smeared (usually 100 cm2).
6. Allow the paper to dry and measure the net count-rate above background by scintillation counting.
7. Using the following equation, calculate surface contamination in Bq/cm2.
Removable Activity = (N - NB)/(E x 60 x A x F)
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Where
N =
NB =
E =
60 =
the total count rate in counts per minute (CPM) measured from the wipe
the normal background count rate (in CPM) from the blank
the instrument efficiency factor (expressed as a decimal, i.e., for 26% efficiency, E = 0.26)
for the isotope being measured (consult the instrument manual)
sec/min
A =
area wiped (not to exceed 100 cm2)
F =
the collection efficiency of the wipe; if F is not determined experimentally, a value of
F = 0.1 (i.e., 10%) shall be used
If any count-rates are two times above background, that area must be decontaminated and then
re-measured for contamination by wipe testing. This is to be repeated until the count-rate on the wipe is
not above background.
3.11.2.2
Direct Measurement of Surface Contamination
Direct measurement of beta or gamma surface contamination can be made using various types of
Geiger-Müller detectors (GM) or scintillation detectors in conjunction with a count-rate meter. Direct
measurement, unlike a wipe test, measures both removable and fixed (or absorbed) radioactivity.
Thin-wall and end-window GMs are normally used because of high beta detection efficiencies. A survey
meter should be used to determine if a work area shows counts above background. If so, the area should
be cleaned and a wipe test performed to ensure that removable contamination has been eliminated. The
area should then be rechecked with the survey meter to determine if significant fixed contamination is still
evident. Report any fixed contamination to the SRSO. (See Table 4.6, "Permissible Limits of Surface
Contamination," in Section 4.2.3.1, “Surface Contamination.”)
If the survey meter has been calibrated, the following procedure can be used for determining surface
contamination:
1. Hold the detector close to the surface, taking care not to touch the surface, and move the detector
slowly across the surface.
2. When the meter needle shows the presence of contamination, hold the detector stationary over the
contaminated area and note the count rate.
3. Note the background count-rate while holding the detector well away from the surface being
monitored.
4. Note the counting efficiency of the meter for the contaminating isotope, which is usually indicated on
the meter.
5. Calculate surface contamination as in the following example:
Counting efficiency
5% (assume 5% if not specified on meter)
Meter window
50 cm2
Counts
75 CPM
Background counts
20 CPM
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3.11.3
Procedures for Decontamination of Areas and Equipment
Good working habits and good housekeeping will prevent most contamination incidents and circumvent
the need for decontamination. (See Table 4.6, “Permissible Limits of Surface Contamination,” in
Section 4.2.3.1, “Surface Contamination.”) When decontamination is indicated, the following general
observations apply:
1. Decontamination is carried out using chemical and physical cleaning processes.
2. Various chemicals may be used, but the initial approach should be scrubbing with hot water containing
suitable cleaning agents. Always wipe from the periphery toward the centre of the contaminated area
to prevent spreading of the radioactivity.
3. All waste chemicals, water, rags, etc created as a result of decontamination are to be treated as
"radioactive waste" if they exceed 1.0 EQ/kg or 0.01 EQ/L.
4. All spills involving more than 37 MBq (1 mCi) are to be reported to the SRSO and the RSO.
3.12
Decommissioning Policy
Before any room can be released for non-radioactive use, it will require decommissioning. To
decommission a location, all nuclear substances or prescribed equipment and related radiation warning
signs and labels are to be removed. A Permit Holder must comply with all decommissioning requirements
under the Nuclear Safety and Control Act and its Regulations by removing all nuclear substances,
ensuring that contamination levels do not exceed the limits specified on the licence, and removing all
related radiation warning signs and labels. All decommissioning records must be retained for review by the
RSO and finally by the CNSC.
Decommissioning certifies that the laboratory is free of radioactivity or radioactive surface contamination.
This is achieved when wipe test results are less than 0.5 becquerels per square centimetre (Bq/cm2) for all
radioisotopes, with the exception of alpha emitters where the value is set at less than 0.05 Bq/cm2.
When an area is identified to be decommissioned, the Permit Holder must notify the SRSO and the RSO
in writing prior to the decommissioning of the laboratory.
The Permit Holder will be responsible for all costs associated with any
•
contracted work for the removal of waste material from the laboratory;
•
outside contracted testing of the device or source that is conducted; and
•
disposal that does not meet acceptance under the current disposal of radioactive material criteria.
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The SRSO or the RSO will offer advice on decommissioning with proper written notice. They will not carry
out the actual decommissioning of the laboratory for the Permit Holder.
If a professor or researcher vacates a laboratory or work with radioactive material ceases, it is necessary
to decommission the laboratory. The CNSC requires that a record of inventory disposition be forwarded to
the RSO as well as wipe test or radiation monitoring results or both.
3.12.1
Decommissioning Procedure
When moving out of any area or room that has contained radioisotope material, closed or open source,
the following procedure must be performed:
1. Advise the RSO and SRSO of decommissioning plans.
2. Prepare for the monitoring and decontamination of areas.
3. Decontaminate, if necessary, then perform monitoring procedures.
4. Map out a plan of your laboratory area and indicate sites of swipes to be taken. These sites are
chosen to include all areas where radioactive material was or may have been used, stored, counted or
disposed, or where sample preparation occurred.
5. Perform wipe tests of the following areas (add other areas as required):
–
Fume hoods (inside, floor below, sink, if there is one);
–
Each bench site where work occurred (surface area of bench, below on floor, surface area of
cupboard doors);
–
Fridges and freezers (inside surface area where material is stored, floor area, handle of fridge,
outside surface area of door);
–
Sink in laboratory (surface area near drain, sides, taps);
–
Windows (ledges, which may require more than one swipe area if material stored there, window
handles);
–
Disposal storage site (floor, wall, if cans left against one, inside and outside of cupboards);
–
Doors (floor, door handle, area around handle);
–
Storage cabinets or drawers (bottom of shelves, sides of cabinets, door and handles of cabinet
and floor in front of cabinet); and
–
All other associated equipment (e.g., chromatograph, centrifuge, etc.).
6. If areas are contaminated, follow the decontamination procedures. (See Section 3.11.3, “Procedures
for Decontamination of Areas and Equipment.”)
There is contamination if wipe test results are above 0.5 Bq/cm2 for all radioisotopes. With used alpha
emitters, there is contamination if results are above 0.05 Bq/cm2.
7. Use Form 10, "Wipe Test Results," in Chapter 6, and include
–
full details of what room or area these results are for;
–
copy of the detailed map;
–
copy of all raw data, complete with details of what they represent;
–
convert data to Bq/cm2 (see Section 3.11.2.1, “Wipe Test Procedures,” and Section 3.11.2.2,
“Direct Measurement of Surface Contamination,” for calculations); and
–
a list of all equipment that will be left behind (i.e., centrifuge, hot water bath, etc.), only if
applicable.
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8. Remove, transfer, ship or dispose of all nuclear substances and radiation devices:
–
Remove or deface all signs, labels and nuclear substances packaging; and
–
If disposing of nuclear substances, package waste accordingly and record using Form 9, “Waste
Disposal,” in Chapter 6.
9. Dismantle, decontaminate and remove all associated equipment (e.g., chromatograph, etc.) as
required.
10. Complete the final report, which should contain the following information:
(a) A completed copy of Form 7, "Decommissioning Records," from Chapter 6, including a completed
copy of the final contamination survey with a detailed diagram of the test sites. Note any special
disposition of radioisotope material (e.g., transfer of radioactive material to a new location, transfer
of instruments, disposal confirmation, etc.);
(b) An indication of licensed activities (open source, sealed source, radiation device containing sealed
source);
(c) Historical information, such as
–
the length of time that nuclear substances and radiation devices were in use,
–
the location where they were used,
–
the specific types and quantities of nuclear substances that were used, and
–
other relevant information available from previous licences as required;
(d) A completed copy of Form 10, "Wipe Test Results," from Chapter 6;
(e) A completed copy of Form 9, "Waste Disposal," from Chapter 6;
(f) A completed copy of Form 1, “Open Source Inventory Sheet,” or Form 2, "Sealed Source
Inventory Sheet," from Chapter 6, which must include transfer information;
(g) The internal permit.
11. The RSO will conduct a final inspection of the area and provide the complete report to the CNSC.
12. The CNSC may conduct an inspection for all areas prior to approving the release of the room from
regulatory control.
3.13
Emergency Response Policy
The Departmental Health and Safety Office with the Security, Safety and Emergency Management
Division must be notified in the event of a spill involving any one or more of the following situations:
1. When a spill involves radioactive material;
2. When the radioactive material emits alpha radiation;
3. When inaccessible areas are suspected of being contaminated;
4. When reasonable efforts to decontaminate are unsuccessful in reducing the level of activity to near
background levels;
5. When there is doubt regarding the correct decontamination procedure; or
6. When significant contamination of personnel occurs.
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3.13.1
Radioactive Material Spills
There are a number of procedures that are common to all types of accidents involving hazardous
materials. These procedures should be followed in the initial stages of any incident, especially those
involving radioactive material. The following steps are based on information contained in the Handbook of
Laboratory Safety, published by CRC Press, Inc. In normal radioisotope laboratory operations, spills of
radioactive material will be the most common form of emergency situation. In the event of any spill of
radioactive material, it is important that the correct steps be taken promptly to avoid the spread of
contamination (provided that it can be accomplished without creating any additional hazard).
1. Alert everyone in the area. Ensure that everyone in the vicinity of the incident has been alerted. Be
sure to make an effective warning, especially for large laboratories or those divided into multiple
rooms.
2. Confine the problem or emergency. Restrict access to the area involved in the emergency. If the
material is a liquid, use some absorbent material to prevent its spread outside the designated area.
When controlling access, define an area large enough to accommodate the incident, such that
persons at the boundary are not affected by the emergency. For example, the restricted area around a
spill of radioactive material should accommodate the possibility of the material spreading and provide
sufficient room to accommodate cleaning procedures to minimize potential exposure to other
personnel.
3. Clear the area. Remove all persons from the immediate vicinity of the emergency. Ensure a sufficient
separation such that persons near to the incident cannot become exposed to the problem. Generally
this will involve marking an area with warning signs or tape, closing laboratory doors, etc.
4. Summon aid. In any emergency situation, it is mandatory to notify the appropriate personnel so that
the problem can be rectified as soon as possible with minimal additional hazard to all employees.
Calls to summon aid should be made from outside the emergency area. Another person, not
immediately involved in any of the above activities, should be directed to make the appropriate
notification. See Annex C, "Emergency Contact Lists."
5. Wash hands in case they were contaminated during the accident.
6. Use the appropriate detector to monitor clothing and hands to determine if any skin or clothing
contamination has occurred. If personal contamination has occurred, treat it first.
7. Ensure that a laboratory coat is used, properly buttoned up, to prevent contamination of clothing.
8. Wear two pairs of latex, chemical or combination of gloves. This will protect the hands in the
event one pair of gloves develops a defect.
9. Use a respirator if airborne material may be present to reduce the potential for accidental intake of
the radioactive material.
10. Drop dry absorbent material on wet spills. If the spilled material is dry, use water or the appropriate
organic solvent to dampen the material.
11. Mark the location and probable extent of the contamination with a wax pencil or other durable
marker. Radiation warning tape may also be used. Do not use felt tip or other permanent markers.
12. Do not track contamination away from the spill area. Do not let anyone leave the contaminated
area without being checked for contamination. Remember to check the sides of shoes for
contamination.
13. Begin decontamination procedures as soon as possible. Any experiment or procedure in progress
must be set aside until the decontamination is complete.
14. Work in from the area of lowest contamination to the area of highest contamination.
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15. Use normal cleansing agents or commercial decontamination agents. Before beginning the
decontamination procedure, ensure that sufficient materials are available to properly clean the area.
This will eliminate the need to leave the clean-up area unnecessarily.
16. Gently wash the affected area with the water and cleansing agent. The technique involves several
washings, each followed by a clean rinse. Change water and cleaning agent solution often.
Contaminated cleaning agent or water must be considered as radioactive waste.
17. Treat all cleaning materials as radioactive waste. Absorbent used for liquid material must be
returned to the plastic bottle. Absorbent paper must be put in the solid waste container.
18. Continue washing until contamination is removed or cannot be reduced any further. Monitor the
area after each wash and rinse to check progress in decontamination procedure.
19. Use a wipe test to check for the presence of any residual contamination after the procedure has
been completed. If the area is clean, record all results in the log book for the room. If contamination
remains, further cleaning is required. If cleaning is ineffective at removing the contamination, contact
the SRSO or RSO for assistance.
3.13.2
Radioactive Contamination of Skin or Clothing
If personnel are suspected of being contaminated with radioactive material:
1. Immediately assess the location and extent of the contamination.
2. Use a survey meter, if appropriate for the suspected isotope, to locate the material and provide an
assessment of the amount.
3. Remove any contaminated clothing and place clothing articles in plastic bags. List contents on a label
and attach to bag and seal the bag with tape.
4. Monitor to determine if any skin contamination has occurred, its location and extent. Treat skin
contamination as described below.
3.13.3
Treatment of Skin Contamination
When contamination of the skin is known or suspected, the steps listed below should be followed. It is very
important that skin contamination be removed immediately. Local skin contamination can provide high
radiation dose rates to the skin. Early, effective removal of the contamination can help to reduce radiation
exposure.
During skin decontamination, it is important to proceed from mild treatments to harsher ones only if
necessary. Abrasion or any other breaks of the skin must be avoided as these will allow rapid penetration
of radioactive material. Therefore, hard scrubbing is discouraged.
3.13.3.1
If the skin is intact:
1. Flush contaminated area with copious amounts of warm water.
2. Wet hands and apply mild soap or detergent. Lather well with plenty of water.
3. Wash lather into the area of contamination for two to three minutes.
4. Exercise caution so as to not spread contamination to other areas of the body.
5. Rinse thoroughly, keeping rinse water confined to contaminated area as much as possible.
6. Monitor effectiveness of removal by use of appropriate survey techniques.
7. Repeat wash and rinse procedure three times more if necessary. If further washing does not remove
the contamination, contact the SRSO or the RSO.
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3.13.3.2
In case of minor wounds not requiring hospitalization:
1. Treat immediately at or near the site of the accident.
2. Clean the affected area with swabs.
3. Wash the contaminated wound with copious amounts of warm water. Encourage minor bleeding.
4. In the case of contaminated facial wounds, ensure that contamination does not spread to mouth, ears,
eyes or nasal passages.
5. Wash wound with mild soap and water as noted above.
6. After decontamination, apply first aid dressing.
7. Notify Permit Holder, the SRSO and the RSO immediately.
3.13.3.3
In case of serious injuries:
The treatment of serious injuries takes precedence over any other consideration. Providing assistance to
seriously injured personnel should not be delayed because of concerns relating to radiation contamination.
1. Contact 911 and request emergency medical assistance. Advise about the nature of the hazard, the
amount of material, the chemical form of the material and any other pertinent information.
2. Direct someone to meet the emergency medical personnel.
3. Advise emergency medical personnel on site of the nature of the radioactive material, extent of
contamination, nature of the injuries and other relevant information. Be available for further
consultation.
4. Ensure that the victim cannot be further contaminated by radioactive material.
5. Use available materials to minimize probability of contamination of emergency medical personnel.
6. Notify Permit Holder immediately. The SRSO and the RSO will be notified by the Permit Holder.
3.13.4
Treatment of Clothing Contamination
In the event that personal clothing becomes contaminated by radioactive material, it is imperative that it be
removed quickly to reduce the exposure to radioactive material. All contaminated clothing must be sealed
in plastic bags. The bags should be labeled with the owner's name, the isotope and the suspected amount
of activity.
In most cases of very low-level contamination, ordinary laundering of the clothes will remove most of the
contamination. Contaminated clothes should be washed separately from other wash and the machine
should be well rinsed afterwards. Monitoring of the clothing should be carried out to ensure that most
contamination has been removed.
If the isotope involved has a short half-life, it may be more effective to store the clothing until the
radioactivity has decayed to low levels. Generally, a period of time equivalent to seven half-lives of the
isotope will reduce the activity to less than 1% of the original amount. Subsequent laundering will remove
the remainder of the material.
3.13.5
Internal Contamination
If internal contamination is suspected, the RSO must be notified immediately.
If the material is chemically toxic as well as radioactive, treat for chemical toxicity first. Dilution of the
contents of the stomach, followed by prompt medical attention is often the best procedure; however, refer
to the chemical first aid treatment information first.
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Personnel working with radioactive material should understand its chemical and radioactive properties
such that a prompt response to a suspected intake of material can be carried out.
3.13.6
Emergency Procedures for Portable Nuclear Gauges
Whenever an accident or fire occurs that results in severe damage to a portable gauge, the following
precautions should apply:
1. Establish a controlled zone having a least a radius of 2 m from the device. Do not enter this area
unless necessary.
2. If you must leave the area, have someone guard the area in order to discourage entry.
3. Inform the SRSO and establish a plan of action.
4. Contact the CNSC.
The law requires that the CNSC be informed of the accident within 24 hours. It is advisable, however, to
report the accident as soon as possible, because the CNSC personnel may be able to assist you. If the
inspector is unable to go to the site, he or she will nevertheless be able to advise you over the telephone
on your plan of action.
•
If the damaged unit is located in an occupied area or in the way of vehicles or pedestrians, use a
shovel, cable or long-handled tool, to move the device to a vacant area and establish a controlled
area.
•
If it is necessary to pick up any part of the damaged unit, use gloves. Place the pieces in a container,
preferably inside a plastic bag. Keep hands at least 15 cm from the sources. After handling, place the
gloves inside the bag and close it.
In order to transport a damaged gauge for disposal or repair, special precautions may be necessary.
Based upon the extent of the damage, the CNSC will be able to advise on what precautions are
necessary.
Before the controlled zone is returned to normal use, it will be necessary to ensure that all sources have
been removed by means of a radiological survey or a visual inspection if possible. You should be aware of
the location of the radioactive sources within the device. Cesium 137 sources are normally located at the
lower end of the rod, which is inserted into the ground, and americium 241/beryllium or radium
226/beryllium sources are normally located inside the case. More information is available in the equipment
manual.
As soon as possible, the source or sources must be tested for leaks (i.e., rupture of the source capsule).
Do not reuse the unit until its operation and safety have been verified.
If you have any questions, do not hesitate to contact the SRSO or the CNSC and ask for the Portable
Nuclear Gauges contact.
3.13.7
Fire or Explosion Involving Radioactive Material
In the event of a major incident involving fire or explosion where radioactive material is known or
suspected to be present, the Security, Safety and Emergency Management Division must be notified
immediately. Emergency personnel responding to the scene should be advised that radioactive materials
may be present. Any information on their location, amounts involved and special precautions should be
provided.
Personnel having specific information on radiation hazards in the area involved should be available for
consultation with the emergency personnel.
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3.14
Radioactive Waste
NRCan is committed to the proper management of the wastes arising from the use of radioactive
materials. Proper management of wastes will minimize the risk to employees and suppliers, as well as
minimizing the release of radioactive material to the environment. Form 9, "Waste Disposal," in Chapter 6
must be completed by users or Permit Holders before waste can be removed from the laboratory.
3.14.1
Classification of Radioactive Waste
Radioactive waste is any of the following:
1. Surplus radioisotope material in any form (e.g., liquid wastes, surplus material in supplied form);
2. Naturally occurring isotopes in rocks;
3. Material that has come into direct contact with radioactive material (e.g., gloves, culture dishes,
pipettes, flasks);
4. Materials used for radioactive decontamination (e.g., paper towels, sponges);
5. Material that has come into incidental contact with radioactive material (e.g., bench-top covering
material, paper towels used for wiping hands and surfaces);
6. Material for which there is a reasonable suspicion of radioactive contamination (e.g., laboratory coats,
shipping boxes);
7. Contaminated equipment used during radioisotope-handling procedures that is no longer required and
cannot be cleaned (e.g., centrifuges, gel electrophoresis equipment); and
8. All materials, including chemicals and biological materials, unless they are stored for decay periods of
7 to 10 half-lives.
If the Permit Holder is unsure as to the classification of material as radioactive waste, the SRSO or the
RSO should be contacted for any information that may be required for proper disposal of radioactive
material.
3.14.2
Responsibility for Labelling and Packaging Radioactive Waste
To ensure that radioactive waste is properly managed, it is important that the contents of the waste be
known. Radioactive materials must be properly labelled and prepared for pickup. An obvious sign must be
attached to each waste container to indicate radioactive waste and prevent accidental pickup by the
custodian service. Use the standard radiation sign or a strip of safety tape with a radioactive materials
warning label. Tags must not be left uncompleted until the time of waste collection.
Non-contaminated packaging material that once contained radioactive materials should have labels or
signs removed or marked out before the container is discarded or placed in storage. The labels are
intended as a warning. When a warning is not necessary, a false concern or a future disregard for the
proper warning may result.
Any waste that does not comply with these requirements will not be collected. The packaging and
labelling of radioactive waste is the responsibility of the Permit Holder and the radioisotope
laboratory staff. Waste will be refused if improperly packaged or labelled. These requirements are to
ensure the safety of personnel as well as to ensure that the waste can be safety processed.
Radioactive waste must not be placed in non-radioactive waste containers. It is the responsibility of each
user of radioisotopes to ensure that different types of waste are properly segregated for disposal.
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3.14.3
Location of Radioactive Waste Containers
Each radioisotope laboratory should establish one location for the consolidation of radioactive waste. More
than one location may be used if the laboratory is very large and has several widely separated designated
areas. The areas for waste must be clearly designated and the SRSO and the RSO should be made
aware of their locations.
Any form of shielding material used around a designated waste consolidation location must be designed,
constructed and used in such a way that it can be easily removed by the employees working within the
area. The design must be such that it does not create additional safety hazards in the laboratory.
Radioactive waste should not be stored beneath any working area, radioisotope or otherwise. Radioactive
waste should not be stored in the vicinity of personnel who do not work with radioactive material.
3.14.4
Waste Disposal Streams
The waste disposal streams currently used for radioactive waste at NRCan are
1. mixed radioactive material (solid) and hazardous chemicals (low level) for disposal (e.g., waste paper,
glassware, pipettes, gloves contaminated with trace chemistry and low levels of radioactivity);
2. liquid scintillation wastes (i.e., organic or aqueous scintillation liquids in plastic or glass vials,
containing low levels of hazardous chemicals);
3. liquid waste materials (i.e., glass or plastic containers of hazardous or non-hazardous liquids with low
levels of radioactivity);
4. radioactive material mixed with biological material using short half-life isotopes stored as appropriate
for the biological material for the 7 to 10 half-lives and disposed in accordance with requirements for
biological waste; and
5. radioactive sealed source material ready for disposal.
3.14.5
Specific Waste Requirements
The requirements for the disposal of specific types of radioactive waste are provided below.
3.14.5.1
Solid Waste
1. Solid waste for disposal must be placed in bags in the designated radioactive waste containers. Solid
waste that is not in a designated container with the completed forms will not be collected.
2. Radioactive waste must not be placed in regular garbage under any circumstances. The waste must
be placed in containers clearly identified as radioactive and disposed of through that stream unless
the radioactive hazard has decayed and is no longer deemed a radioactive hazard.
3. All sharps, glass pipettes or glass tubing must be placed in the white plastic containers and sealed;
they may be placed directly into a primary container, which will fit into the white plastic containers
without having to be removed or handled by the employee.
4. No flasks, bottles or tubes with any liquid are allowed in the solid waste containers. All liquid must be
separated from the solid waste. No liquid scintillation counting vials containing counting fluid are
allowed in the solid radioactive waste container.
5. Non-contaminated material, including foodstuffs or food containers, is not allowed in the solid
radioactive waste container.
6. Information on the material (date, isotope and radioactivity) disposed in the solid radioactive waste
container must be accurately recorded on the waste disposal information sheets.
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7. All containers of solid radioactive waste must be accompanied by a completed “Waste Disposal” form
(Form 9 in Chapter 6).
8. Solid waste must not contain any active or hazardous chemical agents.
3.14.5.2
Liquids Containing Radioactive Material
This section applies to all liquids containing radioactive material except those that contain a significant
amount of organic solvents or material and liquid scintillation counting fluid.
1. If the liquid is likely to dissolve the standard plastic disposal container, the Permit Holder must contact
the SRSO prior to initiation of the project or as soon as the problem is identified.
2. No liquid containing radioactive material, except water used to wash lightly contaminated glassware,
may be disposed of through the sanitary sewer system.
3. All liquids must be segregated from other radioactive waste prior to disposal of hazardous material.
No solidification is required.
4. All radioactive material must be accompanied by a completed "Waste Disposal" form or the material
will be returned to the laboratory (Form 9 in Chapter 6).
5. The waste must not contain any active biological agents.
3.14.5.3
Liquid Scintillation Counting Vials
1. Liquid scintillation counting vials must be separated from other radioactive waste.
2. Scintillation vials must be placed in a plastic bag (similar to the biomedical waste bags but not marked
as such, clear ones can be purchased), then placed in plastic containers used for radioactive waste.
3. Where possible, aqueous and organic scintillation liquid wastes should be segregated and disposed of
separately.
4. All biological material must be inactive.
5. Dry plastic vials used in gamma counters must not be mixed with liquid scintillation counting vials.
6. A completed "Waste Disposal" form must accompany the waste material (Form 9 in Chapter 6).
3.14.5.4
Radioactive Material Containing a Biological Agent
Where the liquid contains radioactive material and biohazardous agents, the latter must be inactivated
prior to the release of the material for disposal preparation. Contact the SRSO if you require additional
information to prepare protocols.
3.14.5.5
Liquid Scintillation Counters
Liquid scintillation counters may have a small radioactive source incorporated into the unit. If a liquid
scintillation counter is to be sent for disposal, the SRSO and the RSO must be notified in writing prior to
the removal of the equipment.
The Permit Holder is responsible to ensure that the equipment is decommissioned as per procedures prior
to removal from the laboratory. If the instrument is to be relocated it must be transferred to a new permit.
If it is to be transferred to a new institution, contact the RSO prior to any transfer agreement being
initiated.
The RSO will issue an amended permit after the removal of the equipment is completed. It is the
responsibility of the Permit Holder to ensure that the unit is free from any surface contamination prior to
removal of the unit for disposal.
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3.14.5.6
Gas Chromatography Units
Gas chromatography units may also contain small open or sealed sources of radioactive material. The
requirement for liquid scintillation counters applies.
3.14.5.7
Miscellaneous Sealed Sources
The Permit Holder must notify the SRSO and the RSO in writing of the intention to dispose of the
unwanted sealed source. The RSO will send back confirmation that the notice is received and retained
on file.
The Permit Holder will provide the RSO with the completed "Waste Disposal" form (Form 9 in Chapter 6).
The form will be retained on file and the new permit will be prepared. The RSO will issue an amended
permit when the disposal of the standard sealed source is confirmed in writing.
The sealed source may have to be transferred back to the manufacturer. Please contact the RSO for more
information.
3.14.5.8
Refrigerators, Freezers and Other Equipment
All refrigerators, freezers and other equipment that have contained radioactive material or were used in
radioactive research and are no longer required must be thoroughly decontaminated. The Permit Holder
is responsible for ensuring that all radioactive material is removed and the unit is free of any surface
contamination. In addition, the Permit Holder must ensure that all radioactive warning labels are removed
or defaced so as to eliminate any reference to radioactive material.
Following decontamination, the SRSO and the RSO are provided with copies of the results for the testing.
The RSO will issue an amended permit.
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Chapter 4:
Radioactivity
4.1
Radiation Physics
4.1.1
Fundamental Particles
In order to appreciate the origins, characteristics and relative hazards associated with nuclear radiation, a
few introductory remarks must be stated about the nature of matter.
The fundamental particles from which all atoms are constructed are called protons, neutrons and
electrons. Their basic properties are summarized in Table 4.1. Protons and neutrons are found in the
nucleus of the atom whereas electrons are usually found free or in orbitals around the nucleus.
Table 4.1 Properties of Fundamental Particles
Particle
Mass
Relative Mass
Electric Charge
Electron
0.911 x 10-30 kg
1/1836
-
Proton
1.673 x 10-27 kg
1
+
Neutron
1.675 x 10-27 kg
1
Zero
4.1.2
The Atom
Atoms consist of an extremely dense nucleus of protons and neutrons, surrounded by a "cloud" of
electrons. The nucleus constitutes approximately 99.9% of the mass of the atom. An atom normally has
the same number of electrons as protons so that the net electric charge carried is zero.
Although the atom is surrounded by a dense cloud of orbital electrons, the majority of the volume occupied
by an atom is empty space. As an illustration of the amount of empty space in the atom, if all such space
were removed from all atoms in the Earth, the Earth would be reduced to the size of a beach ball.
The number of protons in the nucleus is called the atomic number (Z). The atomic number identifies an
element and determines its chemical properties. The mass number (A) of an atom is defined as
A = Z + N, where N represents the number of neutrons in the nucleus. An atom of an element can be
identified in general by AZXN, where X represents the chemical symbol for the element; for simplicity, this
form is usually shortened to AX.
Example: 126C6 or 12C represent an atom of carbon.
4.1.3
Isotopes
Atoms of an element can be found that have different mass numbers (A). These different forms are called
isotopes of the element, and differ from one another only in the number of neutrons (N) in the nucleus.
Example: 12C and 13C are isotopes of carbon.
Elements often occur naturally as a mixture of stable isotopes. The isotopes of an element are chemically
identical since the chemical properties of an atom are determined by the atomic number (Z).
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4.1.4
Radioisotopes
Not all isotopes of an element are stable. An unstable nucleus, or radioisotope, will undergo a
spontaneous transformation into a more stable decay product. The transformation process is known as
radioactive decay, and is accomplished by the emission of nuclear radiation. Radioactivity is a
phenomenon which is independent of the chemical and physical states of the radioisotope. Different
radioisotopes have unique radioactive properties.
Example: 11C and 14C are radioisotopes of carbon, whereas 12C and 13C are stable isotopes of carbon.
The number of radioisotopes known today exceeds 1250. The majority of radioisotopes are produced by
neutron activation of stable isotopes in a reactor. Only a small number of radioisotopes occur naturally.
Naturally occurring radioisotopes contribute to the background radiation in which we live. Some are
created by the interaction of cosmic rays with atoms in the upper atmosphere (cosmogenic). Examples of
cosmogenic radioisotopes are 3H, 7Be, 14C. Their rate of production is very small but they do contribute to
the total radiation dose received due to natural background radiation.
Other naturally occurring radioisotopes have been present on the Earth since it was formed. In this regard,
the most important radioisotopes are members of the uranium and thorium radioactive series, and an
isotope of potassium with a mass number of 40 (40K). Radon gas is a member of the Uranium 238 decay
chain.
4.1.5
Radiation Energy
The electron volt is a unit of energy useful in atomic physics and is the expression of the energy
associated with nuclear radiation. The energy of nuclear radiation is generally expressed in units of million
(mega) electron volts (MeV). One million electron volts is equivalent to the energy gained by an electron
accelerated through an electrical potential difference of one million volts. The kiloelectron volt (keV) is also
used, particularly with respect to X-ray energies. The energies of most nuclear radiation range from
several keV to four or five MeV or more.
4.1.6
Nuclear Radiation
Alpha particle emission, beta particle emission, and gamma radiation are the most important phenomena
of radioactive decay for radioisotopes used in biomedical research. Sources of energetic neutrons are also
used in research. As these nuclear radiation penetrate matter, they dissipate their energy through
"collisions" (with atomic electrons) and other interactions in the absorbing medium. The results of these
interactions are the excitation and ionization of absorber atoms, and the disruption of molecular bonds.
Radiation capable of creating ions is called "ionizing radiation." Disruption of the molecular bonds may be
detrimental to biological systems.
Alpha and beta radiation are considered particulate radiation since there is a nuclear particle involved in
the radiation. Gamma radiation is electromagnetic radiation as it consists only of energy and has no rest
mass. Neutrons are also considered as particulate radiation and have a mass but no associated electrical
charge.
4.1.6.1
Alpha Particle Emission
An alpha particle (") is a positively charged assembly of two neutrons and two protons (helium nucleus,
He) which is discharged from a heavy nuclei during radioactive decay. An example of the decay of an
alpha-emitting radioisotope is shown below.
4
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Alpha decay involves a decrease in the atomic weight by 4 and a decrease in the atomic number by 2.
Alpha particles are the least penetrating of nuclear radiation. The range in air of the most energetic alpha
particle is only a few centimetres. Their range in tissue is insufficient to penetrate the 0.07 mm of the dead
outer layer of skin (epidermis). Alpha radiation from radioactive substances outside the body is thus
harmless. However, internally deposited alpha-emitting radioisotopes are toxic because all the energy of
the radiation is deposited in living tissue.
4.1.6.2
Negative Beta Particle Emission
A beta particle ($–) is a negative electron that is ejected from the nucleus upon the spontaneous
transformation of a neutron into a proton. An example of a beta decay equation is given below. A negative
beta decay involves no change in atomic weight but an increase of 1 in the atomic number. This is due to
the additional proton created. Beta particles exhibit a continuous energy distribution ranging from zero to a
maximum energy characteristic of the particular beta emitter.
Beta emission is accompanied by the emission of an antineutrino (v–e). The difference between the energy
partitioned to the beta particle and the maximum energy of the emission is given to the antineutrino. The
antineutrino is a small essentially massless particle which does not interact with matter. The average
energy of beta particles is approximately a of the maximum energy. The interaction of beta particles with
matter results in electronic excitation, ionization, and the production of X-rays (bremsstrahlung). Beta
particles will penetrate matter to varying depths depending upon their energy and on the density of the
absorber. They have a range in air of approximately 3.5 metres per MeV and in tissue, a few centimetres.
The hazards of beta radiation depend on the energy of the beta particles and the nature of any shielding.
For most beta emitters, the container of the isotope is sufficient to reduce the beta radiation levels to near
zero. The radiation from external sources emitting weak beta particles, such as tritium (3H) and carbon
(14C), is nameless. However, the radiation from strong beta emitters, such as 32P, may pose a serious
hazard to skin. In addition, any internally deposited beta-emitting radioisotope is potentially harmful.
Beta radiation is effectively shielded by low atomic weight material such as Plexiglas or Lucite. Lead may
be used to reduce the small amount of bremsstrahlung radiation produced from larger sources. However,
the low atomic weight material must always be positioned closest to the source. The radiation should
interact with the low atomic weight material before reaching the lead.
4.1.6.3
Positive Beta Particle Emission
A positive beta particle or positron ($+) is an electron with a positive electric charge rather than the
negative charge normally associated with the electron. Positron emission occurs from the nucleus and
generally occurs when there is an excess in the number of protons in the nucleus. In this reaction, a
proton is changed into a neutron with the emission of a positron and a neutrino (<e). This reaction,
illustrated below, shows the positron emission following the decay of 13N to 13C. The positron, after
emission from the nucleus, will generally be slowed down and combined with an orbital electron. The
result is the annihilation of the two particles and the production of two gamma rays, each of 0.511 MeV..
Therefore, positron emission is always accompanied by some gamma radiation. As with negative beta
particle emission, the positron is emitted within a spectrum of energies associated with the decay of
the atom.
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4.1.6.4
Gamma Ray Emission
Both alpha and beta decay processes frequently leave a daughter nucleus in an "excited" or metastable
(m) state. A gamma ray (() is a photon (packet) of electromagnetic radiation produced by the
spontaneous de-excitation of an excited nuclear state to a lower excited state or to the ground state. An
example of a gamma ray emission is given below.
Gamma rays are the most penetrating type of nuclear radiation. Protection against gamma radiation
involves the reduction of intensity to acceptable levels by suitable thicknesses of appropriate absorbers.
The absorptive properties of matter are functions of the atomic number (Z) of the absorber and the energy
of the gamma radiation. Materials of high atomic number such as lead (Z = 82) are preferred absorbers of
gamma radiation. Gamma emitters always present a potential external radiation hazard because of the
penetrating nature of their radiation. Protective measures are essential for the safe handling of gamma
sources.
4.1.6.5
Electron Capture (EC)
The process of electron capture is similar to the emission of a positron in that it reduces the number of
protons in the nucleus. In the process of electron capture, one of the inner orbital electrons interacts with
the nucleus and combines with a nuclear proton to form a neutron and a neutrino. The neutrino is the only
particle emitted from the nucleus and is not readily detected since it does not normally interact with any
type of absorber material. Due to the vacancy in the inner orbital electron shell, the other electrons will be
rearranged with electrons moving down from outer to inner shells. In the process, X-rays are created
representing the difference in the energy between the energy levels of the outer shell and the inner shell.
An example of the process of electron capture is shown below.
4.1.6.6
Internal Conversions (IC)
Internal conversion is a process that may occur when the nucleus normally emits gamma radiation. The
gamma radiation interacts with an inner orbital electron resulting in the transfer of the energy of the
gamma ray to the orbital electron. The electron is then ejected from the atom. The emitted electron is
known as a conversion electron and is monoenergetic, as opposed to the spectrum of energies that is
associated with electrons emitted during negative and positive beta decay. No gamma ray is emitted
during the process of internal conversion but it is possible for X-rays to be emitted following the
rearrangement of the orbital electrons.
4.1.6.7
Neutron Emissions
Neutron sources are more commonly used in engineering and geology applications. Neutrons can be used
to activate stable isotopes and create artificial radioactivity. Neutrons can be found in a nuclear reactor but
can also be created from sealed sources. Generally, the emission of neutrons is accomplished by
bombarding the target material with either alpha particles or high-energy gamma rays. The neutrons are
literally knocked out of the target atom nucleus. Examples of neutron sources are
1. plutonium 239/beryllium: alpha, neutron source;
2. americium 241/beryllium: alpha, neutron source;
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3. sodium 24/beryllium: gamma, neutron source; and
4. sodium 24/deuterium oxide (D2O): gamma, neutron source.
In all of these examples, the radioisotope provides either the alpha particle or gamma ray to cause
ejection of a neutron from the second material (beryllium or deuterium oxide) which is the target.
Californium 252 is also a source of neutrons that are provided as a result of the spontaneous fission of the
Californium 252 atom.
Neutron sources require special handling and dosimeters as the neutrons are not detected by the usual
thermoluminescent dosimeter (TLD) in use. Neutrons emitted from most sources have relatively high
energies. Once they lose this energy (become thermalized), they may be absorbed by the nucleus of an
atom. Neutrons have no electrical charge and therefore must lose energy by collisions with the nuclei of
atoms in moderator material. These materials can also be used for shielding since they will also absorb
the thermalized neutrons. The most effective transfer of energy occurs when the atom of the absorber is
close in weight to that of the neutron. Therefore, moderator or shielding material containing a large amount
of hydrogen is the preferred shielding material. Examples of effective neutron moderators or shields are
water, wax and concrete. However, absorption of the neutron is usually accompanied by the emission of a
gamma ray. For absorption by a hydrogen atom, the associated gamma ray is emitted with an energy of
2.2 MeV. It should be noted that lead cannot be used as shielding for neutrons. Contact the Site Radiation
Safety Officer (SRSO) or the Radiation Safety Officer (RSO) for information when handling of neutron
sources is required.
4.1.6.8
X-rays
X-rays are similar to gamma rays in that they are packets of energy or photons. However, gamma rays
originate from within the nucleus, while X-rays originate outside of the nucleus.
X-rays are created when electrons undergo a change in the amount of energy that they possess. For
example, X-rays are created during the process of electron capture when a vacancy is created in the inner
orbital shell of an atom. Electrons from higher energy outer orbitals will "drop down" to fill the inner
vacancy and will lose energy. This energy is lost in the form of X-rays. Another difference between X-rays
and gamma rays is that while the latter are emitted with discrete energies, the nature of the production of
X-rays results in a spectrum of energies being created. Therefore, shielding for X-rays is slightly different
than shielding for gamma rays although both are effectively shielded by lead and concrete.
X-rays may also be created when accelerated electrons are slowed in the presence of the nucleus of an
atom. This is the principle behind the operation of X-ray machines. Electrons are accelerated in an
electrical field and then directed to impinge on a target material constructed of metal, usually tungsten.
The nuclei of the target atoms slow the electrons down and in this process the electrons give up their
energy in the form of X-rays. This radiation is also known as bremsstrahlung from the German for
"braking radiation." Bremsstrahlung can also be created from the negative beta emission from certain
isotopes such as phosphorus 32 since the conditions are similar. Use of light materials for shielding will
reduce the probability of creating bremsstrahlung and is the reason for the use of plastics such as
Plexiglas for shielding of beta sources.
4.1.7
Activity
The activity (A) of a radioactive material refers to the rate of disintegration of the unstable nuclei. One unit
of activity is called the curie (Ci). The Standard International Unit (SI) of activity is called the becquerel
(Bq), where 1 becquerel (Bq) = 1 disintegration/sec. The relationship between these units is shown in
Table 4.2. The activity of a radioisotope will decrease over time due to decay of the isotope and is related
to the half-life of the material through the equation shown below.
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The activity at any time (A) is related to the original activity (Ao) by the decay constant (8) and the time (t)
since the activity was originally measured. Note that the units of time for the decay constant and the
elapsed time must be the same as the exponential portion of the equation is dimensionless. The decay
constant is related to the half-life of the isotope as shown above.
One curie (Ci)
= 3.7 x 1010 disintegrations/sec (dps)
= 3.7 x 1010Bq
= 2.22 x 1012 disintegrations/min (dpm)
The specific radioactivity of a radioisotope refers to the amount of radioactivity per unit of mass or other
measure. Due to the dilution that may occur in the course of a radioisotope experiment, consideration
should be given to using a specific radioactivity that is high enough to ensure adequate labelling of the end
product. This will avoid unnecessary repeats of the experiment.
Table 4.2 Submultiples of the Curie (Ci)
Units
Ci
Bq
dpm
millicurie (mCi)
10-3
3.7 x 107
2.22 x 109
microcurie (uCi)
10-6
3.7 x 104
2.22 x 106
nanocurie (nCi)
10-9
3.7 x 101
2.22 x 103
picocurie (pCi)
10-12
3.7 x 10-2
2.22 x 100
4.1.8
Half-life
The half-life (T½) of a radioisotope is the time required for one half of the unstable nuclei to decay. If the
activity of the sample is Ao at time t = 0, then the activity remaining after one half-life is ½ Ao. Figure 4.1
illustrates the decrease of activity with time.
Although the half-lives of radioisotopes differ, they all decay in this predictable fashion. 131I (T½ = 8 days)
will lose 87% of its radioactivity in 24 days (three half-lives). 14C will lose only half of its activity after 5730
years (one half-life).
Note that after two half-lives, one quarter of the nuclei are left, after three half-lives, only one eighth are
left, and so on. The half-lives of different radioisotopes range from about 10-8 seconds to 1010 years.
Table 4.3 indicates the radioactive properties of certain radioisotopes.
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Figure 4.1: Exponential Decay of Radioisotopes
Table 4.3 Radioactive Properties of Selected Radioisotopes
Radioisotope
3
H
14
C
Half-life
Decay Mode
Energy (MeV)
12.26y
Beta
0.018 (max)
5730y
Beta
0.156 (max)
32
P
14.28d
Beta
1.71 (max)
35
S
87.9d
Beta
0.167 (max)
Ca
165d
Beta
0.252 (max)
Cr
27.8d
Electron Capture, X-rays
0.320 (9%)
Fe
45.6d
Beta, Gamma
0.475 (max)
45
51
59
1.095 (56%); 1.292 (44%)
60
Co
5.26y
Beta, Gamma
0.314 (max)
1.173 (100%); 1.332 (100%)
65
Zn
245d
Electron Capture, X-rays
1.115 (59%); 0.511 (3.4%)
125
I
60.2d
Electron Capture, X-rays
0.035 (7%)
131
I
8.05d
Beta, Gamma
0.606 (max); 0.364 (82%)
Cs
30.3y
Beta, Gamma
0.514 (max); 0.662 (85%)
137
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Radioisotope
Decay Mode
Energy (MeV)
203
Hg
46.9d
Beta, Gamma
0.213 (100%); 0.279 (77%)
226
Ra
1620y
Alpha, Numerous Beta and Gamma
Radiation from Progeny
4.78 (95%); 4.60 (5%)
Am
458y
Alpha, Numerous Gamma
Radiation
5.49 (85%); 5.44 (13%)
241
4.2
Half-life
Radiation Measurement
For effective radiation protection, it is necessary for personnel to know the dose of radiation they have
received due to their handling or other work with radioactive material. Normally, this is expressed in terms
of radiation exposure or absorbed dose.
4.2.1
Measurement of Radiation Exposure
Nuclear radiation cannot be measured directly by humans in the same way as light or heat radiation.
Instead, it is necessary to monitor the effect of radiation on something to determine the amount of
radiation that is present. Radiation causes its effects through ionization of atoms in a material, and
measurement of the amount of ionization is the manner in which radiation is monitored.
There are many different units used to express the amount of radiation that is present. As noted earlier, Bq
or Ci are units of activity and are not used to measure radiation dose. This section will generally be
concerned with the measurement of external radiation and the resulting dose.
4.2.1.1
Radiation Exposure Dose
Usually it is more useful to know how much radiation is absorbed by the biological system of interest but
sometimes it is only possible to measure the amount of radiation to which a person is being exposed. This
is the radiation exposure dose and, for x- and gamma radiation, it is expressed in terms of röntgen (or
rœntgen), after W.C. Röntgen, who discovered X-rays in 1895. The röntgen (R) is a measurement of the
ionization of air and is equivalent to the production of 2.08 x 109 ion pairs per cubic centimetre of dry air at
standard temperature and pressure (STP). One röntgen is also equivalent to 2.58 x 10-4 coulombs per
kilogram of air, which is the SI unit of radiation exposure. Exposure in röntgens is usually expressed in
smaller units called the milliröntgen, abbreviated as mR.
Radiation exposure is not an effective measurement for radiation protection because it does not describe
the amount of radiation actually being absorbed by the biological system. Only radiation that is absorbed
can have any effect on a living system. Any radiation that is not absorbed is harmless. For example,
during negative beta decay, an antineutrino particle is emitted. This is a chargeless, essentially massless
particle that does not interact with matter. Therefore, the antineutrino will pass through the body without
causing any harm. In addition, the röntgen cannot be used to measure particulate radiation such as alpha
and beta particles and is only valid for X- and gamma radiation with an energy less than 3 MeV. Therefore,
in order to determine the amount of radiation that is biologically significant, it is necessary to measure the
amount of radiation that is absorbed.
4.2.1.2
Radiation Absorbed Dose (rad)
Measurement of the energy deposited in matter by nuclear radiation is fundamental in health physics.
Absorbed dose refers to the energy deposited per unit mass at the point of interest in any medium by all
types of ionizing radiation. The commonly used unit of radiation absorbed dose is the rad (R); the SI is the
gray (Gy).
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1 rad = 0.01 joules/kilogram = 0.01 gray
For X and gamma radiation, exposure of air to 1 R of radiation will result in an absorbed dose to the air of
0.869 rads. However, for body tissues and other material, the absorbed fraction differs depending on the
material (bone, water or muscle) and the energy of the radiation.
The main advantage of the rad over the röntgen is that it may be used with any radiation and any
absorbing medium. The rad is also a measurement of the biologically significant radiation. In measuring
the rad for human exposure, the absorbing medium must have radiation absorptive properties similar to
those of human tissue. Therefore, materials that have densities close to tissue and a similar mean atomic
number are used. An advantage of the lithium fluoride chips in TLDs is that they absorb radiation in a
manner similar to that of tissue.
Unless otherwise noted, wherever the term dose is used, it is implied to mean the absorbed dose rather
than a measure of exposure.
4.2.1.3
Relative Biological Effectiveness (RBE)
Different types of radiation vary in their ability to cause damage in biological systems. Some types of
radiation will cause damage at lower doses than will others. Generally, these effects are measured relative
to another type of radiation that is used as a standard. Typically, the standard radiation chosen is the
gamma radiation from Cobalt 60. The dose of a test radiation required to produce a specific biological end
point is measured against the dose of the standard radiation required to achieve the same result. This
results in a ratio comparing the two types of radiation and is known as the relative biological
effectiveness of the test radiation or its RBE. The RBE can be used to convert the dose in rads from
different types of radiation to allow comparison of exposures. Without the RBE, it would be impossible to
set standards of exposure since they would have to accommodate the different types of radiation and their
effectiveness.
Multiplying the rad times the RBE provides a measure of the dose equivalence. The RBE for X and
gamma radiation is 1. For neutrons and alpha particles, the RBE can vary up to a factor of 20, meaning
that these types of radiation can produce a biological effect at a radiation dose level 20 times less than the
gamma dose level that will produce the same effect.
A disadvantage of the RBE is that it is very closely tied to the biological end point under examination. For
instance, the RBE of alpha particles may differ when the end point is lens opacity versus a test system
involving chromosomal aberrations. In addition, RBEs cannot be measured in humans. Therefore, the
RBE is primarily used in radiation research.
4.2.1.4
Radiation Weighting Factor
Due to the inherent problem of using the RBE in radiation protection, the term radiation weighting
factor (RWF) is used in International Commission on Radiological Protection (ICRP) Publication 60. The
RWF is not dependent on the biological end point being examined but is related to the linear transfer of
energy by the radiation to the surrounding tissue. The RWF is widely used in radiation protection to
compensate for the different biological effectiveness of different types of radiation, much like the use of
the RBE.
The RWF is established by the ICRP. As with the RBE, the RWF is dimensionless. RWFs for various
types of radiation are given in Table 4.4.
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Table 4.4 Radiation Weighting Factors for Various Types of Radiation (ICRP 60, 1990)
Type of Radiation
Radiation Weighting Factor
200-250 kVp X-rays
1
Gamma Rays
1
Electrons and Muons, all Energies
1
Neutrons, Energy > 0keV
5
Neutrons, Energy 10 keV to 100 keV
10
Neutrons, Energy 100 keV to 2 MeV
20
Neutrons, Energy 2 MeV to 20 MeV
10
Neutrons, Energy > MeV
5
Protons, Energy > 2MeV
5
Alpha Particles, Fission Fragments, Heavy
Nuclei
20
4.2.1.5
Equivalent Dose
The unit of dose equivalent was developed as a measure of the rad times the RWF of the radiation. The
conventional units for dose equivalent is the rem, which is an acronym for röntgen equivalent man. The
SI unit for dose equivalents is the sievert (Sv) with 1 Sv = 100 rem. The term dose equivalent is being
replaced by the term equivalent dose in ICRP Publication 60.
The unit of dose equivalent is used to allow comparison of the radiation dose received from types of
radiation having different RWF.
4.2.2
External Radiation Exposure
Radiation protection guidelines have been established for two fundamental groups in society, nuclear
energy workers (NEWs) and members of the public. Both groups may receive a radiation exposure
from the occupational use of radioactive material but the dose limitations are different for each group. A
person does not need to be designated as a NEW to work with radioactive material.
The ICRP has recommended values for maximum permissible annual doses to NEWs and to members
of the public from the occupational use of radioactive materials. These guidelines exclude doses incurred
in medical applications of radiation or from natural background radiation. These values have been adopted
for use in Canada by the Canadian Nuclear Safety Commission (CNSC). The maximum permissible doses
for both categories are shown in Table 4.5, "CNSC Annual Limits of Exposure for NEWs and Members of
the Public," provides the annual limits for NEWs and members of the public.
The maximum permissible doses represent the sum of all radiation does due to occupational exposure.
The values are based on the ICRP Publication 60 that was published in 1990 and has set extremely
conservative limits. Nevertheless, every precaution should be taken to avoid all unnecessary exposures. It
should also be noted that with these maximum values, the expected normal value will be much lower. To
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put these values in perspective, it is interesting to note that the average whole body dose rate from the
natural environment is approximately 300 mrem (3.0 mSv) per year. A passenger taking a return flight
from Toronto to Vancouver would receive a whole body dose of about 5 millirem (50 uSv) from the
increased cosmic radiation at high altitudes.
Table 4.5 CNSC Annual Limits of Exposure for NEWs and Members of the Public
Whole Body
Skin
Hands and Feet
Lens of Eye
Nuclear Energy Workers
20 mSV (2 rem)
500 mSV (50 rem)
500 mSV (50 rem)
150 mSV (15 rem)
General Public
1 mSV (100 mrem)
50 mSV (5 rem)
none specified
15 mSV (1.5 rem)
4.2.2.1
The ALARA Principle
The concept of the maximum permissible dose is misleading in that it implies a safe level of exposure. In
reality, it is a sliding scale of increasing risk associated with each increase in radiation exposure. An
analogy may be made to the highway speed limit where traveling 100 km/hr in an area posted as
100 km/hr does not imply danger. However, as speed is increased, the risk of injury due to accident also
increases. Management of radiation doses is similar except that there is emphasis placed on keeping the
radiation exposure as low as reasonably achievable. Where it may be permissible to travel at the posted
speed limit on a highway, in radiation protection the limit is the upper bound and all doses must be kept as
far below this value as practicable. This is the ALARA principle.
As Low As Reasonably Achievable (ALARA)
The concept of ALARA is to keep all exposures as low as reasonably achievable, social and economic
factors taken into consideration. Although the federal agencies may prescribe a certain radiation limit, it
is incumbent on persons working with radioactive materials and their employer to ensure that all
radiation doses are in accordance with the ALARA principle. Social and economic factors will dictate
the practical lower limits of this policy. Such factors are not meant as "escape clauses" but must be
viewed in the practical sense.
4.2.2.2
Nuclear Energy Workers
Any person who works with radioactive materials and has a reasonable probability of exceeding the dose
limits for a member of the general public must be designated as a NEW. Dose limits for a NEW are higher
than for members of the general public but there is provision for additional information and medical
surveillance. It should be noted that having a TLD badge does not constitute identification as a NEW.
Conditions for being designated as a NEW include
1. working in the vicinity of a nuclear reactor;
2. working with unsealed alpha emitters;
3. working with neutron sources having a source strength greater than 104 neutrons per second; or
4. participating in special exercises.
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4.2.2.3
Members of the General Public
The CNSC establishes radiation dose limits for members of the general public that are based on
international standards and ensure that the collective dose equivalent received by a population will not
result in significant risk of detrimental effects caused by exposure to the radiation. Generally, the dose
limits are set conservatively to a value of 1/10 of the NEW's limit. The exception to this is the whole body
dose equivalent limit which is 1/20 of the NEW's limit. The 1/10 rule is designed to compensate for the
variations in health among members of the general public. While NEWs are generally considered to be in
good overall health, the same may not be true for all members of the general public.
All persons who have not been classified as a NEW are considered to be members of the general public
for dosimetry purposes.
4.2.3
Internal Radiation Exposure
Exposure to surface contamination may result in external radiation exposure as well as the possible
uptake of radioactive material into the body. Radioactive material in the body will continue to contribute to
the radiation dose received by an individual while the material is in the body. Generally, it is possible to
calculate the amount of intake that has occurred through the use of a proper bioassay technique. The
amount of intake is then used to calculate the committed dose equivalent (also known as the
committed equivalent dose in ICRP Publication 60). The committed dose equivalent is a measurement
of the radiation dose equivalent that will be received by the person while the radioactive material is in the
body over a specific time period, conservatively taken to be 50 years. Radioactive material may be
removed by natural excretion and turnover of body constituents. Medical procedures may also be used to
affect the retention time of the radioactive material in the body.
In addition to the internal contamination that may result from accidents involving radioactive material, there
are other pathways whereby radioactive material may contribute to an internal radiation dose.
4.2.3.1
Surface Contamination
One method whereby radioactive material could be accidentally ingested is through the uptake of surface
contamination that results from the handling of radioisotopes. To minimize the possibility of internal
radiation exposure from this source, the CNSC sets surface contamination standards for working in a
radioisotope facility. These values, found in Table 4.6, "Permissible Limits of Surface Contamination," are
established as a condition of the licence and may be averaged over an area not exceeding 100 cm2.
Weekly monitoring is required by CNSC to reduce the potential for accidental uptakes due to surface
contamination. Contamination that is detected must be immediately cleaned up to prevent accidental
intakes of radioactive material.
Note: Remedial action is required whenever the level of surface contamination exceeds 0.5 Bq/cm2,
averaged over an area not exceeding 100 cm2, regardless of the type of surface.
Table 4.6 Permissible Limits of Surface Contamination
Activity
Working Surfaces
All Other Areas
Alpha
0.5 Bq/cm2
0.05 Bq/cm2
Beta-Gamma
5.0 Bq/cm2
0.5 Bq/cm2
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4.2.3.2
Ingestion or Inhalation of Radioisotopes
Another method whereby radioactive material could become an internal radiation source is through the
ingestion or inhalation of radioactive material through routine handling. Small intakes of the material, of
which the user is unaware, are possible. In particular, inhalation or ingestion of tritium or radioiodine is
possible and bioassay requirements have been established for those who routinely handle these
radioisotopes. Permits that allow the handling of this material may list, as a condition, the requirement for
the appropriate bioassay to be carried out.
It is the responsibility of the Permit Holder to ensure that bioassays for tritium and radioiodine
work (125I,131I) are performed as required by Health Canada, Radiation Protection Bureau.
Personnel handling these isotopes should take proper precautions to minimize the intake of radioactive
materials during the course of routine handling. Most of the protective clothing, equipment and procedures
are designed to minimize this possibility. Adherence to proper handling techniques is the best defence
against such intakes.
4.2.3.3
Intakes Occurring from an Accident
In any accident involving radioisotopes, there is the possibility of an intake of the radioactive material. If
any situation occurs that may have resulted in the accidental ingestion or inhalation of radioactive material,
the SRSO and the RSO must be notified immediately. Specific procedures can be employed to help
reduce the radiation dose due to internally deposited material. Such methods are most effective when
used before or shortly after an intake has occurred.
4.3
Principles of Radiation Protection
Shortly after the discovery of radiation in the late 1890s, it became apparent that exposure to ionizing
radiation could have unexpected harmful effects. This was first recognized among early radiology
technicians who held the X-ray film under the patient during the X-ray exposure. The hands of the
technicians were severely affected by the radiation that they received. Other early experience with
radiation demonstrated that it posed a risk to workers unless they were suitably protected.
In 1928, an international committee was formed to recommend radiation protection measures and to
propose limits on radiation exposure. Originally known as the International X-ray and Radium Protection
Committee, it was reorganized in 1950 and renamed the ICRP. The ICRP is an international group
composed of persons with expertise in radiation protection and related fields.
In Canada, the CNSC is the federal agency that sets radiation standards. The CNSC bases its regulations
on accepted international practices and the recommendations of the ICRP.
Radiation comes from many sources, both natural and artificial. Figure 4.2 shows the sources of radiation
and their relative contribution to the radiation dose received by the average person each year.
Miscellaneous sources of radiation include fallout from nuclear weapons, occupational doses, sources of
radiation associated with nuclear power and other sources.
The largest contribution to the average annual exposure is the radiation in the natural environment. The
amount of radiation from this source will vary as a function of the altitude and the geology of the area of
residence. Some areas will also differ in the amount of radon exposure, primarily due to the geology of
the area.
Radiation, whether from natural or artificial sources, is an integral part of life on the planet. The primary
goal of radiation protection is to protect workers, members of the public and the environment from the
detrimental effects of radiation from the occupational uses of radioactive material, while still allowing its
use for beneficial purposes.
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Figure 4.2: Sources of Radiation
4.3.1
Objective of Radiation Protection
The main objective of a radiation protection program is to prevent detrimental non-stochastic effects and to
limit the probability of stochastic effects to acceptable levels. Stochastic effects are those for which an
increase in radiation exposures causes an increase in the probability that the effect will occur
(e.g., cancer) but not the severity of the effect. Non-stochastic effects are only observed above a threshold
radiation dose, the effect will always occur when the radiation dose is above the threshold and the severity
of the effect is dependent on the total dose (e.g., opacity of the lens of the eye).
The ICRP recommends a system of dose limitation that has the following main features (from ICRP 26):
•
No practice shall be adopted unless its introduction produces a positive net benefit.
•
All exposures shall be kept as low as reasonably achievable, economic and social factors being taken
into account.
•
The equivalent dose to individuals shall not exceed the limits recommended for the appropriate
circumstances by the ICRP.
Although the specific dose limits proposed by the ICRP may change over time, these principles have
remained as the basis for all radiation protection programs.
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4.3.2
"Rules of Thumb" for Radioactive Material
4.3.2.1
Alpha
It requires an alpha particle of at least 7.5 MeV to penetrate the protective layer of the skin, which is
normally 0.07 mm thick.
4.3.2.2
Beta
It requires a beta particle of at least 70 keV to penetrate the protective layer of the skin.
The average energy of beta rays with a normal spectrum of energies is approximately one-third the
maximum energy of the beta ray. The range in air equals 12 ft (3.66 m) per MeV. The dose rate to skin
(in rads/hr) at one centimetre from an unshielded point source (neglecting self and air absorption) equals
300 rad/hr per millicurie. The dose rate to skin at 1 cm from a point beta ray source varies only slightly with
beta energy.
For beta particle energies above 0.6 MeV, the dose rate through the nominal protective skin layer is
9 rads/hr (90 mGy per hour) from a uniformly thin deposit of 1 :Ci/cm2 (37 kBq/cm2) of a beta-emitting
radionuclide.
4.3.2.3
Gamma
The equation describing the dose rate for X-ray and gamma radiation point sources is given below where
C is the source strength in millicuries, (EEAn) is the sum of the energy (E) of the gamma radiation in MeV
multiplied by the probability of emission (n) for each gamma ray emitted and r is the distance in metres
from the source. This equation is only valid for X-ray and gamma radiation in the energy range of 0.07 to
2 MeV. Table 4.7 gives the dose rate for 1 mCi sources of commonly used gamma emitters at a distance
of 1 metre.
Table 4.7 Dose Rate of Some Commonly Used Gamma Emitters
mrem/hr per mCi at 1 metre
:Sv/hr per Mbq at 1 metre
1.34
0.36
Cr
0.02
0.01
Fe
0.66
0.18
60
Co
1.37
0.37
64
Cu
0.13
0.04
0.33
0.09
I
0.28
0.08
Cs
0.38
0.10
Hg
0.25
0.08
Radioisotope
22
Na
51
59
65
Zn
131
137
203
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4.3.2.4
Neutrons
The dose equivalent rate in rem/hr from a point source of neutrons, effective energy of about 2 MeV, is
given below where Q is the number of neutrons emitted per second from the source and r is the distance
in centimetres.
The thickness of paraffin required to reduce the intensity of neutrons by one half (the half-value layer) for
1 MeV neutrons is 1.26 inches (3.2 cm). For 5 MeV neutrons, the half-value layer is 2.72 inches (6.93 cm)
of paraffin.
4.3.2.5
Radioactive Decay
After 7 half-lives, the activity of any radionuclide will be reduced to less than 1% of the original amount.
For radionuclides with a half-life greater than six days, the change in activity over 24 hours will be less
than 10%.
Radioactive decay follows the equations given below. Either can be used, depending on the units of
measurement available. N is the number of nuclei after time t, No is the original number of nuclei, A is the
activity after some time t and Ao is the original activity. The value 8 is known as the decay constant and is
specific to the radioisotope. The value shown by -8At can also be represented by -(0.693t/T½) where
8 = 0.693/T½. The value shown by -(0.693t/T½) is a representation of the number of half-lives derived from
the half-life of the material (T½) and the amount of time that has passed (t).
For example, 32P has a half-life of 14.7 days. To find out how much is left from a 1 mCi source after seven
days, the following information is used:
8 = 0.693/14.7 = 0.0471
A = (1 mCi)(e-(0.0471)(7)) = (1 mCi)(0.72) = 0.72 mCi
The physical half-life (T½p) of a radioisotope is the time required for the amount of activity to decrease by
one half due to radioactive decay. It is specific to the radioisotope.
The biological half-life (T½b) of a radioisotope is the time required for the amount of a radioisotope in a
biological system to be reduced to one half of the original amount and is due to removal by biological
processes. It is specific to the chemical form of the radioisotope and varies from individual to individual.
The effective half-life (T½e) is a measure of the elimination of a radioisotope from a biological system
though both radioactive decay and the removal by biological processes. It is a combination of the physical
and biological half-lives.
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4.3.3
External Radiation Protection
There are a few general methods that may be employed for protection from external sources of radiation.
Generally, it is a good practice to utilize all of these practices wherever feasible to reduce exposures
consistent with the ALARA principle.
4.3.3.1
Time
Radiation is emitted from a source at a constant rate. Therefore the radiation dose will be dependent on
the amount of time spent in proximity to the source of radiation. A radiation dose is controlled most easily
by limiting the time spent in a radiation field.
Example: Radioiron is used in ferrokinetic studies of blood plasma. An injection of ferric chloride
containing 500 cCi Iron 59 is to be administered to a calf. The dose rate at the surface of the syringe is
40 mrem/minute. The syringe is handled for 1.5 minutes; estimate the dose to the fingers.
Dose = 40 mrem/minute x 1.5 minutes = 60 mrem
If the procedure can be performed in one half the time noted above, then the radiation dose received can
be reduced as follows:
Dose = 40 mrem/minute x 0.75 minutes = 30 mrem
However, while it is advisable to reduce the time in proximity to radioactive material, it is not
recommended that a procedure be unnecessarily rushed in order to accomplish this reduction. Rushing a
procedure may introduce errors with higher consequent risk of an accident.
4.3.3.2
Distance
The radiation field at any point is inversely proportional to the square of the distance from the source
(assuming negligible distance between the source and the point of interest).
Maintaining as great a distance as possible from small gamma sources is an effective method of
protection. A good practice is to work with radioisotopes at arm's length to minimize the radiation field to
the trunk of the body. It should be remembered though, that local dose rates to the hands and fingers may
be quite substantial with some isotopes. This is also due to the phenomenon described by the inverse
square law where halving the distance between the source and receptor will quadruple the radiation
intensity. The use of long-handled tools when working with unshielded radioactive sources will reduce
exposure to the hands and fingers.
Since alpha and beta particles have limited ranges in air, distance affords an effective method for
protection against them. However, maintaining sufficient distance from radiation sources is not always
practical for sources of beta and gamma radiation and shielding of the sources becomes necessary.
4.3.3.3
Shielding
Shielding is the most reliable method for protection against radiation and is installed to reduce the
radiation field from a source. Shielding can be used very effectively for beta and gamma sources. Alpha
sources, due to the limited range of the particle, do not normally require shielding unless beta or gamma
radiation emissions are associated with the decay of the radioisotope. Beta radiation can be shielded
using low atomic number material such as plastics (e.g., Plexiglas). Shields for gamma radiation are
usually constructed of steel, concrete, lead, or other high atomic number (Z) materials.
It should be noted that the effectiveness of a given thickness of lead shielding will be dependent on the
energy of the radiation being absorbed. Therefore, lead aprons, while particularly effective for the low
energy radiation emitted from 125I, will not be as effective when shielding against the higher energy
radiation from 131I. Lead aprons should be used carefully as they may introduce a false sense of security to
the wearer when handling radioactive material. Contact the SRSO or RSO for information.
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4.3.4
Internal Radiation Protection
Alpha and beta particles and gamma rays are the principal forms of radiation encountered during
radioisotope work in biomedical research. Due to their limited range in air and tissue, alpha particles do
not present a radiation hazard when outside the body as they are unable to reach living tissues. Beta
particles, while their range is much greater, generally pose a radiation hazard only to the skin. Gamma
rays tend to pose the greatest concern for exposures from external sources due to their long range and
penetrating power through tissue.
In terms of concern from radiation sources internal to the body, the situation is effectively reversed. Alpha
particles pose a greater hazard when taken internally due to their ability to cause intense local damage.
Beta particles and gamma rays are less hazardous but this is dependent on the effective half-life and
energy of the radiation associated with the decay of the radioisotope. Some radioisotopes are distributed
throughout the body (e.g., tritium) while others are concentrated in specific organs or tissues (e.g.,
radioiodine in the thyroid, radium in the bone). Internal exposure will continue until the radioisotope
decays, or until it is eliminated biologically. Protective efforts are therefore mandatory. Procedures for
internal radiation protection include methods to control contamination, and basic hygienic practices. The
former would include all efforts to keep the material contained, the use of a fume hood, or glove box, and
trays with absorbent paper; the latter would include wearing of gloves and protective clothing and washing
after handling radioactive sources.
Radioisotopes can enter the body through inhalation, ingestion, skin absorption or entry through a wound.
Elimination of the radioisotopes can take place through the respired air, urine, feces or sweat. The uptake
and subsequent elimination of radioisotopes will depend on the chemical nature of the material and its
ability to be transferred between the environment and various body systems. The ICRP has prepared a
comprehensive list of radioisotopes and the amount allowed to be taken internally by different exposure
pathways. The amount of a particular radioisotope, called the Annual Limit on Intake (ALI), represents
the intake of a radionuclide that will result in a annual whole body dose of 20 mSv (from ICRP
Publication 61). Consult Annex I, “Regulatory Quantities for Typical Radionuclides,” for the ALI of
frequently used radioisotopes.
The ALI is the upper limit and must not be exceeded. To exercise the ALARA concept for internal
exposures, radiation doses from radionuclide uptakes must be kept as far below this level as reasonably
possible, social and economic factors taken into consideration. To achieve ALARA, bioassay programs
are used to monitor for any uptake of the radioisotope under consideration.
Radiotoxicity of an isotope refers to its potential capacity to cause damage to living tissue as the result of
being deposited inside the body by either ingestion, inhalation or absorption. This potential for damage is
governed by the mode and energy of the radioactive disintegration, the physical half-life, the rate at which
the body excretes the material, and the radio-sensitivity of the critical organ. Together with activity,
chemical and physical form, the radiotoxicity is taken into account when determining the type of handling
precautions necessary for the radioisotope in question. Table 4.8 provides levels of radiotoxicity.
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Table 4.8 Radiotoxicity
Radiotoxicity of the Individual Radionuclides
Permissible Level of Activity (for Normal
Chemical Operations)
Very High
5 MBq (135 uCi)
High
500 MBq (13.5 mCi)
Moderate
5 GBq (135 mCi)*
Slight
50 GBq (1.35 Ci)
*Except for Mo99m TC generators and 99mTC eluate, for which the permissible activity is 100 GBq (3 Ci).
Some radioisotopes are also hazardous because of their chemical toxicity. This may be due to toxic or
carcinogenic effects of the chemical. The fact that the material is radioactive does not increase or
decrease this chemical toxicity. For example, natural uranium is an example of a chemically toxic
radioactive material where the primary concern is the chemical toxicity of uranium to the kidney. Control of
this hazard will also result in the proper control of the hazardous radiological characteristics of this
material.
4.3.4.1
Bioassay
Bioassay techniques are the method of determining the amount of a particular radioisotope in the body.
Two methods can be used for carrying out a bioassay technique; in vitro and in vivo.
In vitro techniques are used when a small sample of a body fluid or tissue is sampled and analyzed in a
detector. This is the technique used when urine is monitored for assessing tritium uptake.
In vivo techniques involve measuring the amount of radioactive material by placing detectors close to the
surface of the body. This technique is used for assessing the uptake of radioiodine in the thyroid or
uranium in the lungs.
It is the responsibility of the Permit Holder to ensure that bioassay monitoring is carried out when
required by Health Canada.
Bioassay and other medical examinations are carried out at the discretion of the SRSO, RSO or the
Radiation Safety Committee and the CNSC. Results of such examinations will be available to both the
person examined and the appropriate regulatory authorities. Bioassays are typically required following the
handling of certain radioisotopes, notably the radioiodines and tritium (the latter only after the handling of
large quantities). Where necessary, the permit will stipulate the conditions under which a bioassay is
required. The frequency of the bioassay monitoring is dictated by the radioisotope and its chemical and
radiological behaviour in the body. Bioassay techniques must be sensitive enough to ensure that any
significant amount of radioactive material will be detected.
4.3.4.2
Bioassay Requirements - Radioiodine
Bioassays for radioiodine are mandated by the CNSC and are carried out in accordance with Regulatory
Document R–58, Bioassay Requirements for 125I and 131I in Medical, Teaching and Research Institutions.
Participation in the bioassay program is required when the amount of open source quantities of radioiodine
handled exceeds 1.35 mCi (50 MBq) during a three-month period. This refers to the total amount of
radioiodine used over the period. Persons who work with radioiodine, or those who are sufficiently close to
the process that significant intake is possible, must participate in the bioassay program.
Contact the RSO to enrol in the thyroid bioassay program or to arrange for a bioassay measurement.
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The required frequency for bioassay monitoring depends on the status of the individual. According to
R–58, there are three levels: baseline, routine and maintenance. The frequency for each status level is
provided below:
Bioassay Frequency for 125I
Bioassays for radioiodine must be performed after six hours but within seven days following work with
radioiodine.
•
Baseline:
An individual shall undergo a bioassay prior to beginning work with radioiodine.
•
Routine Status:
An individual is in routine status and shall undergo bioassay after each use of radioiodine or
monthly (whichever is less frequent):
•
–
For the first three months that he or she is in the bioassay program;
–
Following any significant change in the radioiodine handling procedures;
–
Following a significant increase in the amount of radioiodine used; or
–
Following an observed thyroid burden in excess of the appropriate investigation level (1 kBq).
Maintenance Status:
Bioassay for 125I shall be performed at quarterly intervals if each observed thyroid burden for that
individual during the previous quarter was less than the investigation level of 1 kBq.
When the bioassay is performed each quarter, any result above the investigation level of 1 kBq will
result in the individual returning to routine status.
Bioassay Requirements for Infrequent Use of Radioiodine
A person may be considered to be an infrequent user of radioiodine where the frequency of use is more
than twice the maintenance status interval for the radioisotope (e.g., for 125I, an infrequent user would be
one who will not use it for more than six months).
An infrequent user of radioiodine may apply to leave the bioassay program provided the following two
conditions have been met:
•
The person is in the maintenance status for the radioiodine; and
•
The last two bioassay measurements have been less than the investigation level of 1 kBq.
The Permit Holder must apply to the RSO to have the radioiodine purchase level reduced to less than
1 mCi (37 MBq) per three months. The infrequent user must rejoin the bioassay program before
increasing this level and resuming work with radioiodine. The user will enter the program at the routine
status level, following a baseline measurement.
Bioassay Requirements - Tritium
Tritium bioassays may be required following the handling of significant quantities of tritium. The amount of
tritium that may be handled before a bioassay is required is dictated by the chemical form of the material.
When a Permit Holder is permitted to purchase quantities of tritium that may require a bioassay, the permit
will contain a condition to that effect.
Due to the specific nature of tritium handling and the quantities involved, the bioassay requirements for
tritium are dependent on the nature of the handling. See your permit for conditions or contact the RSO.
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4.3.5
Radiation Dose Monitoring
4.3.5.1
Survey Monitors for External Radiation Exposure
The most common radiation detection and monitoring instruments are the Geiger-Müller (GM) survey
meter and the ion chamber survey meter.
The scale on a GM survey meter usually indicates counts/minutes (or counts per second) and mR/hr.
However, voltage pulses produced by the GM detectors are independent of the amount of energy
deposited in the sensitive volume. Consequently, the readings in counts/minutes are, in general, more
accurate than the readings in mR/hr. Detectors calibrated for a particular gamma ray energy can be used
to accurately measure dose rates associated with those rays. GM survey meters are most useful for
gamma and for high-energy beta detection.
The voltage pulses produced in ion chamber-type instruments are dependent on the amount of energy
deposited in the sensitive volume of the detector. These instruments are therefore calibrated to read dose
rate (mR/hr) directly. Ion chamber survey meters are used for monitoring the radiation fields from beta,
gamma, and X-ray sources.
4.3.5.2
Personal Dosimeters
The primary objective of personnel monitoring is to prevent overexposure by monitoring a radiation
exposure history. Personnel monitoring devices are worn to record the cumulative whole body dose (mrem
or mSv) received from occupational exposures to external radiation. Information obtained when the
dosimeters are read is useful for evaluating the effectiveness of protective measures and the necessity of
appropriate actions.
All persons who work with radioactive material at NRCan must wear the appropriate personal monitoring
device. This does not apply to those persons who work in areas where only 3H, 14C, or 35S are used. In
addition, monitoring for the radiation dose to the extremities may be required. Consult the Internal Permit
for details and contact the SRSO or the RSO for additional information.
The personal monitoring device most commonly employed is the TLD. TLDs for personnel monitoring
contain two lithium fluoride (LiF) crystal chips situated under aluminum filters. When exposed to ionizing
radiation, temporary defects are created in the thermoluminescent crystal. These defects are stable until
the LiF chip is heated and the TLD releases the excitation energy in the form of light. The intensity of the
emitted light is proportional to the absorbed dose. One of the LiF chips, under the thick aluminum disk, is
used to record the whole body dose while the other chip, under the thin aluminum film, is used to record
the skin dose. To record whole body exposure, dosimeters are normally worn at the chest or waist levels.
TLDs have certain limitations that must be recognized. Most apparent is that these devices must be
"processed" before an indication of exposure can be obtained. The use of direct reading dosimeters may
be warranted if immediate indication of accumulated exposure is desired. The LiF chips are sensitive to
ultraviolet light and may produce false results if exposed. Ultraviolet light is emitted from normal
fluorescent lights and the badges must be protected from exposure to them. TLD badges are also
insensitive to the weak beta radiation from ³H, 14C and 35S during normal handling. However,
contamination of the badge with beta emitters may result in non-relevant exposures being recorded. Care
should be taken that the dose recorded by the TLD badge is representative of the true dose to the
individual to whom it is assigned. The badge must not be left in an area where it could receive a radiation
exposure when not worn by the individual (e.g., on a lab coat and left near a radiation source overnight).
4.3.6
Requirements During Pregnancy
It is known that the fetus is more sensitive to the effects of radiation than the adult human. Therefore,
special precautions must be taken to provide the proper degree of protection to the fetus during the term
of the pregnancy.
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It is not possible to accurately measure the radiation dose to the fetus and so it must be inferred from the
exposure to the mother. Radiation protection principles limit the radiation exposure to the mother and
therefore achieve a minimum risk to the fetus.
4.3.7
Surface Contamination Monitors
The most effective means of monitoring for surface contamination is through the use of the wipe test
technique and liquid scintillation counting of the wipe. This test will detect all beta-emitting radionuclides
and some gamma emitters as well.
Specialized instruments are also available that are capable of detecting a wide range of radioisotopes in
the form of surface contamination. Generally, these instruments operate on the basis of gas ionization and
proportional counting where the size of the pulse created is related to the energy of the radiation.
Correction factors are applied to convert the pulses to a reading, typically in the form of Bq/cm². These
monitors have larger detection surfaces and thin Mylar film windows on the detector. They are fragile but
very effective as portable instrumentation. While some monitors may incorporate correction factors for
specific radionuclides, the monitor may not be used to determine the type of radionuclide. Specific
correction factors may only be used when the identity of the radioisotope is known.
Some GM survey monitors have windows that are sufficiently thin to permit the monitoring of some
beta-emitting radionuclides. The efficiency of the detection will depend on the energy of the radiation with
low-energy beta emitters (e.g., ³H, 14C and 35S) having a very low efficiency. High-energy beta emitters
such as 32P are easily detected by such monitors. Gamma-emitting radionuclides will also be detected with
these monitors.
When using portable instrumentation for surface contamination monitoring, care should be exercised to
ensure that the indicated reading is representative of the factual situation. The reading from surface
contamination monitors can be influenced by sources of radiation in the vicinity of the surface being
monitored. If possible, remove all radiation sources from the area to be monitored by the survey
instrument. All survey meters should be checked on a periodic basis to ensure that they are operating
properly and are capable of detecting the type and energy of radiation of interest. A monitor that is not
functioning properly may not detect areas of surface contamination that require remedial action.
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Chapter 5:
Training
5.1
Worker Training and Authorization Policy
It is the policy of Natural Resources Canada (NRCan) to authorize staff members (Permit Holders and
users) to work with nuclear substances only after they have successfully completed appropriate training.
The training will include information on the safe use, storage and disposal of radioactive material. All
employees and students will have the risks associated with ionizing exposures explained to them prior to
working with radioactive material, except when on-the-job training is carried out under the direct
supervision of a person with a level of training and expertise that is acceptable to the Canadian Nuclear
Safety Commission (CNSC).
A record is maintained of the training received by each worker. Retraining is given following any significant
change in work. Training will be site-specific, task-specific and tailored to the educational background and
the practical needs of each trainee.
To promote a good safety culture, the basic radiation safety training will be extended to auxiliary
personnel: clerical, janitorial, maintenance, nursing and security.
Possession, use, storage and transfer of nuclear substances is strictly limited to the licence holder and
designated and trained employees.
The requirement that all new staff or students asked to work with radioisotopes first be provided with basic
radiation safety training will be waived if proof of equivalent training at another recognized institution is
provided. The Radiation Safety Officer (RSO) with the Radiation Safety Committee will assess the level of
knowledge of the individual, and if the evaluation proves to be unsatisfactory, then training will be required.
Non-compliance will be considered as a major offence on the part of the Permit Holder.
5.2
Short-Term Employees, Including Students and Volunteers
The Permit Holder is responsible for ensuring that no student or volunteer under the age of 18 years is
working with radioactive material unless both the Site Radiation Safety Officer (SRSO) and the RSO have
given prior written approval.
The Permit Holder is also responsible for ensuring that short-term employees (including students and
volunteers) have read the NRCan Radiation Safety Manual and the training manual. They must be fully
informed of all laboratory procedures that they may be required to perform in the course of their work or in
the event of an emergency. Once all the required training has been done, the “Short-Term Employee
Radiation Safety Training Record” (Form 11 in Chapter 6) must be completed and signed by the user,
Permit Holder, SRSO and RSO, and must be attached to the permit. The validation period on this record
indicates the date that the user will no longer be required to work with radioactive material (date of
departure). When the employee leaves, the record must be removed from the form and filed.
Students and volunteers who are in the process of completing their education or who have no laboratory
experience must be supervised when they are working with radioisotopes under NRCan's internal permits.
The Permit Holder will be responsible for ensuring that personal dosimeters are provided as required prior
to any work being conducted by the student, volunteer or other short-term employee using radioactive
material.
Questions regarding students or volunteers working with radioactive material should be addressed to the
SRSO or RSO.
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5.3
Site Radiation Safety Officers
For SRSOs and their alternates to effectively execute their duties and responsibilities, they are required to
take the following training:
1. Radiation Safety Officer Training (e.g., Radiation Safety Institute);
2. Transportation of Dangerous Goods (TDG), Class 7; and
3. Working Safely with X-rays, if applicable.
5.4
Other Personnel
The NRCan training modules can be customized or adapted to assist SRSOs or Permit Holders in
providing training and awareness to support and administrative staff, such as security personnel, safety
officers, administrators, shipping/receiving personnel, housekeeping employees and others. See
Section 5.11 for NRCan’s training matrix.
5.5
NRCan's Radiation Safety Course
All radioisotope licences issued by the CNSC include a condition requiring licensees to ensure that only
persons properly trained and informed of the hazards are allowed to handle radioactive materials.
Therefore, the Permit Holders and users must attend the NRCan Radiation Safety Training course.
The NRCan Radiation Safety Training course has been developed in collaboration with all NRCan science
sectors. Some training modules have also been obtained from the Radiation Safety Institute. The
substance of the training course simulates the format of subject matter suggested in the CNCS Regulatory
Guide C–200, Radiation Safety Training for Radioisotope, Medical Accelerator and Transportation
Workers.
The NRCan Radiation Safety Training modules have been developed to
1. instruct workers in the procedures submitted by the licensee and accepted by the CNSC to ensure
regulatory compliance;
2. inform workers of their responsibility to report promptly to the licensee any condition that might violate
the CNSC regulations or licence conditions;
3. educate trainees about the radiation characteristics, radiation risks and hazard levels of the materials
with which they will be working; and
4. describe the regulatory process and the measures taken by the licensee to protect workers.
The Radiation Safety Training course is divided into two sessions. Permit Holders and users working with
open source radioactive material will attend the one-day training session for open source material. Permit
Holders and users only working with sealed source radioactive material will attend the half-day training
session for sealed source material. The sessions will follow the NRCan Radiation Safety Training matrix
provided in Section 5.11.
5.6
Training Scheduling
In the National Capital Region, a Radiation Safety Training course will be provided one to three times a
year or as required. This will be dependent on the requirements of the laboratories. Arrangements will be
made to ensure that regional staff also receive the course as required.
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5.6.1
Retraining
The CNSC recommends retraining programs both to enhance and to maintain employee competency.
Periodic refresher training will be available. Workers should be retrained after receiving new assignments
or when procedures change. The retraining will reflect the new working conditions and environment to
which the worker will be exposed. In addition, radiation safety topics should be discussed at informal
safety meetings held for workers at least once a month. Users should also participate in a retraining
session every three years.
5.7
Administering the Training Program
5.7.1
Training Records
The Permit Holder is responsible for ensuring that a complete record is maintained of the qualifications of
and training received by every worker. These records, using Form 3, “User Radiation Safety-Related
Training Record,” in Chapter 6, should indicate if and when previous experience and training have been
taken into consideration. Copies of these records will also be available through the SRSO and the RSO.
5.7.2
Written Exam
A written exam will be administered at the end of the Radiation Safety Training course. A passing mark of
70% on the exam is required for certification.
5.7.3
Certification
The licensee will provide every worker who has obtained the passing mark with a certificate indicating that
the worker has successfully completed the Radiation Safety Training course. The certificate will reference
the CNSC requirement for certification, and will include the trainee's name, title of the course, modules
completed, date of issue, the name of the person responsible for issuing the certificate.
5.8
Radiation Safety Training Modules
The Radiation Safety Training course has ten modules. The topics in the modules reflect the required
curriculum. The instructor will vary the length and content of each module depending on the
understanding, qualifications and experience of the participants. The content will also be based on the
type of work involving nuclear substances (open or sealed sources).
Module 1: Radiation Safety Orientation
Objective:
1. To provide a brief introduction to the departmental radiation safety training program and radiation
safety practices.
Content:
A. Introduction
B. NRCan Radiation Safety Program Framework
C. Licensing and administration
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5–3
Module 2: Regulatory Requirements
Objectives:
1. To inform trainees of the regulatory requirements, including the responsibilities of licensees to provide
the training prescribed in standard licence conditions.
2. To inform trainees of worker responsibilities under the regulations.
Content:
A. Highlights of the Nuclear Safety and Control Act and Regulations.
Module 3: Radiation and Radioactivity
Objectives:
1. To acquaint the trainee with the basic concepts on the structure of matter.
2. To acquaint the trainee with the basic concepts of radiation.
3. To provide information about the types of radioactive decay.
4. To introduce the mechanism of radioactive decay.
5. To provide information about the hazards of various types of radiation.
Content:
A. Structure of matter
B. Atom (protons, neutrons, electrons)
C. Atomic number and weight
D. Isotopes
E. Radiation
F. Ionizing (alpha, beta, gamma, X-rays (type, hazard and shielding)) and non-ionizing radiation
G. Radioactive decay
H. Activity and half-life
Module 4: Radiation Quantities and Units
Objectives:
1. To acquaint the trainee with the units used to measure radiation.
2. To provide information concerning the correct usage of the units as they apply to different types of
radiation.
3. To provide information concerning the conversion of the old units to the new units (Standard
International Units (SI)).
Content:
A. Energy
B. Absorbed dose
C. Unit of dose equivalent
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5–4
D. Radiation weighting factors
E. Effective dose
F. Tissue weighting factors
G. Exposure dose
H. Conversion from customary units to SI units
Module 5: Radiation Detection and Measurement
Objectives:
1. To develop a basic understanding of radiation detection and measurement.
2. To learn the basic concepts of radiation measuring instruments.
3. To acquaint trainees with the more commonly used radiation measuring instruments required for the
operation and environment in which they will be employed.
Content:
A. Radiation detection
B. Survey instruments: Geiger-Müller (GM) counters; liquide scintillation detectors
C. Resolving time
D. Dosimeters:
1. Personal dosimeters: typical examples of commercially available dosimeters; specifications of
radiation protection importance; procedures use, wearing and storing personal dosimeters;
advantages and disadvantages
Module 6: Biological and Health Effects of Exposure to Radiation
Objectives:
1. To inform trainees of the relative sensitivity of various cells of the body to radiation.
2. To develop an understanding of the types of biological effects of radiation on the various organs and
tissues of the body.
3. To acquaint the trainee with the stochastic and deterministic effects of radiation on living matter.
4. To acquaint trainees with the genetic effects of radiation.
Content:
A. Concept of radiation dose: absorbed, equivalent and effective dose
B. Effects of radiation on people:
1. Hereditary effects
2. Somatic effects: long-term and short-term somatic effects
C. Stochastic and non-stochastic
D. Deterministic effect
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Module 7: Effects of Radiation on the Fetus
Objectives:
1. To provide workers with knowledge of radiation effects on an unborn child.
2. To enable workers to make better judgements regarding radiation risks while pregnant.
3. To explain the declaration of pregnancy procedure.
Content:
A. Effects of radiation on fetus
B. Exposure during pregnancy
C. Risk to the fetus of prenatal radiation exposure
D. Hereditary effects of radiation
E. Declaration of pregnancy
Module 8: Controlling Radiation Exposure
Objectives:
1. To relate time, distance and shielding as methods of reducing radiation exposure.
2. To impress on the trainees the importance of the ALARA principle "keeping exposures as low as
reasonably achievable," taking into account economic and social factors.
3. To develop an understanding of the hazard from contamination when handling loose radioactive
material, and contamination control practices.
Content:
A. ALARA Principal
B. Radiation exposure
C. Control of external radiation exposure: use of time, distance and shielding in actual radioisotope work
D. External radiation exposure
E. Internal radiation exposure: modes of entry into body: inhalation, ingestion, absorption through skin
Module 9: Operating and Emergency Procedures
Objectives:
1. To provide information about the department's operating and emergency procedures.
Content:
A. NRCan policies and procedures
1. ALARA
2. Designation of NEW policy
3. Food and drinks
4. Room designation and posting policy
5. Access, control and security policy
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5–6
6. Control of nuclear substances policy
7. Purchasing and receiving
8. Packaging and transporting
9. Personal Dose Monitoring Policy
10. Dosimetry during pregnancy for non-NEW
11. Leak testing
12. Surface contamination measurements
13. Radioactive contamination control policy
14. Decontamination procedures
15. Decommissioning policy and procedures
16. Emergency response policy
17. Radioactive material spills
18. Radioactive contamination of skin or clothing
19. Treatment of clothing contamination
20. Treatment of skin contamination
21. Internal contamination
22. Emergency procedures for portable nuclear gauge
23. Fire or explosion
24. Radioactive waste management
Module 10: Transportation Requirements
Objectives:
1. To acquaint the trainee with the basic requirements of regulations governing the transport of
radioactive material.
2. To provide information necessary to properly label transportation containers.
3. To provide information necessary to properly describe radioactive material on shipping documents.
Content:
A. Act and regulations
B. Training requirements
C. Certificates
D. Receiving radioactive material
E. Shipping radioactive material
F. Transporting radioactive material
G. Placarding of transport vehicle
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5.9
Other Training
As regulations and new requirements are introduced, it may become necessary to conduct specialized
training. Information regarding these training courses will be provided to all Permit Holders as required.
These training sessions will become an intricate part of the licence conditions for training, and therefore
will require mandatory attendance as per permit conditions.
Other types of training that may be required by users of radioactive material include Transportation of
Dangerous Goods (TDG), Workplace Hazardous Materials Information System (WHMIS) and X-ray safety.
5.10
Workplace Hazardous Materials Information System
WHMIS is a nationwide communication system that provides information to workers and employers on
hazardous materials used in the workplace. WHMIS applies to all Canadian workplaces. It requires that all
workers who work with or near a hazardous substance, as defined in the Controlled Products Regulations,
are informed about potential hazards and recommended safe work practices.
Under the Nuclear Safety and Control Act a “nuclear substance" does not include the substances being
used that carry radionuclides. This means that the non-radioactive carrier material, if a controlled
substance within the meaning of the Hazardous Products Act, will be subject to the rules of WHMIS and
will, therefore, require WHMIS labelling. There will be quantity exemptions for the non-radioactive
component of mixtures based on a combination of volume or weight, and hazard.
WHMIS requires that information be provided in three ways:
1. All controlled products used in the workplace must have a WHMIS label on the container.
2. Material Safety Data Sheets (MSDS) and hazard information must be readily available in the
workplace. An MSDS summarizes the health and safety information about the product.
3. Workers must receive training to be able to recognize and work safely with the controlled products.
Trainees should be informed that the HAZARD SYMBOL is an important part of the WHMIS label.
5.11
NRCan Radiation Safety Training Matrix
Module 1: Radiation Safety Orientation
Module 2:
Regulatory Requirements
Module 3: Radiation and Radioactivity
Module 4:
Radiation Quantities and Units
Module 5: Radiation Detection and Measurement
Module 6:
Biological and Health Effects
Module 7: Effects of Radiation on the Fetus
Module 8:
Controlling Radiation Exposure
Module 9: Operating and Emergency Procedures
Module 10: Transportation Requirements
D:
detailed course
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Chapter 5 – March 2006
I:
5–8
introductory course
Table 5–1: NRCan Radiation Safety Training Matrix
Job Task/Use Description
NRCan Training Modules
1
2
3
4
5
6
7
8
9
10
Users of Sealed Sources
D
I
I
I
I
I
I
I
I
D
Users of Unsealed Sources
D
D
D
D
D
D
D
D
D
D
SRSOs
D
D
D
D
D
D
D
D
D
D
Security Personnel
I
I
I
I
D
D
Housekeeping and Janitorial
I
I
I
D
Shipping, Receiving and Distributing
I
Waste Disposal
I
Service and Maintenance
I
I
Administrators
I
I
Reception Staff
I
Safety Officer
D
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Chapter 5 – March 2006
5–9
I
I
I
I
I
D
D
D
D
I
D
D
D
D
I
D
I
I
I
I
I
I
I
D
D
I
I
INTENTIONALLY LEFT BLANK
NRCan Radiation Safety Manual
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5–10
Chapter 6:
Forms
Form 1
Open Source Inventory Sheet
Form 2
Sealed Source Inventory Sheet
Form 3
User Radiation Safety-Related Training Record
Form 4
Application for Internal Permit
Form 5
Application for Internal Permit Amendment
Form 6
Application for Internal Permit Renewal
Form 7
Decommissioning Records
Form 8
Design Compliance Form for Laboratories
Form 9
Waste Disposal
Form 10
Wipe Test Results
Form 11
Short-Term Employee Radiation Safety Training Record
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6–1
OPEN SOURCE INVENTORY SHEET
Form 1
Use one sheet per vial for each open source.
Permit Number
Location
Received
Checked by
P.O./Supplier
Nuclear Substance
Product
Quantity
Volume
Vial ID
Date
User(init)
Procedure
Material
Used
Material in
Stock
Waste Form
L
O
S
A
= Aqueous Liquid
= Organic Solvent
= Solid
= Absorbent Material
NRCan Radiation Safety Manual
Chapter 6 – March 2006
Waste Form
Disposal
Method
Amount in
Waste (%)
Disposal Method
1
2
3
4
5
6
7
6–2
= Municipal Garbage
= Municipal Sewer
= Incinerator
= Return to Supplier
= Transfer to Another Licensee or Supplier
= Transfer to Storage
= Other
SEALED SOURCE INVENTORY SHEET
Form 2
Use one sheet for each sealed source.
Permit Number
Location
Date of Receipt
Checked by
Manufacturer
Model Name and Number
Radionuclide
Source Size
Serial Number
Transfer to
Transfer Date
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USER RADIATION SAFETY-RELATED TRAINING RECORD
Form 3
Employee Name:
Position:
Division/Branch/Sector:
Education and Qualifications:
Training
Type*
Date
Provided
Provided
by
Employee’s
Signature
Permit Holder’s
Initials
Module 1: Radiation Safety
Orientation
Module 2: Regulatory
Requirements
Module 3: Radiation and
Radioactivity
Module 4: Radiation Quantity
and Units
Module 5: Radiation Detection
and Measurement
Module 6: Biological and
Health Effects of Exposure to
Radiation
Module 7: Effects of Radiation
on the Fetus
Module 8: Controlling
Radiation Exposure
Module 9: Operating and
Emergency Procedures
Module 10: Transportation
Requirements
In-house (on-the-job) Training
WHMIS
TDG
X-ray Safety
Other:
*Type:
D - detailed course
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I - introductory course
6–4
P - professional qualification
APPLICATION FOR INTERNAL PERMIT
Form 4
Individual internal permits are required for each room or vehicle1 where sealed and open source
radioactive materials will be stored, used or transported. These permits are also necessary for all
acquisitions of radioactive material, either purchased or donated.
The internal permit is limited to the radioactive materials listed and only covers the use of these materials
within the designated areas. If you transport the radioactive material to another site within your facility, the
new location must also have an internal permit that covers the radioactive material you wish to work with
in the new location.
If you transport the radioactive material to another site within the building or to an external building site
within Natural Resources Canada, you must notify the Site Radiation Safety Officer (SRSO) for approval.
If you are transferring the radioactive material to another institution (e.g., a university or another
government department), contact the Radiation Safety Officer (RSO) for approval or information
concerning this.
Following the approval, an internal permit is issued to a designated Permit Holder2 for each room
(laboratory or storage room) and vehicle. All personnel using radioisotope permits must be listed on the
licence. Three copies of each permit will be produced: one for posting, one for the SRSO and one for the
RSO. All will have original signatures of the Permit Holder. A copy of the signed permit must be
posted by the Permit Holder in the laboratory listed on the permit.
Any changes to the permit require the permission of the RSO.
NO permit is transferable to another holder or room location.
1
Where many vehicles are used, one permit will be issued. A list containing all possible vehicles will be attached.
2
Permits will be issued to one individual (Permit Holder) who will be responsible for the monitoring of all functions within
the designated area (location identified on the permit) that fall under compliance with the licence. The Permit Holder will
be a person with managerial responsibilities in the designated area and who has knowledge and experience in radiation
safety.
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APPLICATION PROCEDURE
The following application form must be completed for each room and vehicle where nuclear substances
are being used, stored or transported.
Part 1. General Current Licence Information
Provide all current licence information as required.
Part 2. Nuclear Substances and Radiation Devices
General Information Required for New Permit
Provide the room number (or vehicle, indicating type and licence plate number), laboratory level,
designated Permit Holder (researcher or applicable person), position of the Permit Holder, his or her
phone number, and complete address (including the section, division, branch and sector as well as the
building). Radioactive material must not be used or stored in a location not listed at the top of each
permit.
Also indicate the name of the SRSO and the purpose of the licence.
Radionuclide Information to Be Included on Internal Permit
List all radioisotopes in your possession. Specify the activity for open source material, devices containing
sealed source material, the isotope type of device and the isotope and the delivery rate of the material.
(The rate of delivery must not be exceeded). Radioisotopes other than those listed on the permit must not
be purchased or obtained by the Permit Holder before obtaining the approval of the RSO.
Persons (Users) Approved for Work with Nuclear Substances
List all users that will be working with the nuclear substances. All users must be properly trained. Any
changes to this list must be approved by the RSO. For students or short term employees, Form 11 will be
completed and attached to the permit during the validation period.
Part 3. Instruments Used for Radiation Detection and Monitoring
Provide a list of radiation detection and monitoring devices, including the name of the instrument, the
manufacturer and number as well as the model and serial number.
Part 4. Details of Experiment/Work Involving the Nuclear Substances Listed in Part 2
Provide details of the work involving radioisotopes.
Part 5. Instruments Labelled for Radioisotope Usage
Provide a list of all instruments, such as centrifuges, refrigerators, fume hoods, etc., where radioactive
materials will be used.
Part 6. Design Compliance Form for Laboratories
All rooms intended to be used for the handling, storage or disposal of more than one scheduled quantity of
a radioactive material, must conform to the requirements of the Atomic Energy Control Board Regulatory
Guide R–52, Design Guide for Basic and Intermediate Level Radioisotope Laboratories. This Regulatory
Guide applies to all new or renovated facilities designed after January 1, 1986.
Any area in that radioactive material has been previously used may have an approval on file, and an
inspection may not be required. Where extensive renovations or modifications have been carried out
within the area, an inspection must be completed prior to issuing of the permit.
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–6
For any area that has not been used for storage or handling of radioactive (open source) material,
including new laboratory facilities or those renovated, a completed “Design Compliance Form for
Laboratories” is required for the proposed room. Approval is based on the existence of the control required
on the form. An inspection by the RSO will also be required to ensure compliance with the Regulatory
Guide. Contact the RSO for a copy of the “Design Compliance Form for Laboratories” (Form 8 in this
section) if you are applying for a room that has not been previously approved for radioisotope use.
Part 7. Understanding
The Permit Holder must sign the application. By doing this, the Permit Holder is agreeing to the terms and
conditions under which the permit will be issued.
Send the completed and signed form to
Radiation Safety Officer
Security, Safety and Emergency Management Division
Human Resources and Security Management Branch
Natural Resources Canada
580 Booth Street, 11–A2–4
Ottawa, Ontario K1A 0E4
Tel.: (613) 995-5344
Fax: (613) 943-0336
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Chapter 6 – March 2006
6–7
APPLICATION FOR INTERNAL PERMIT FORM
Part 1. General Current Licence Information
Licence Number
Expiry Date of Current Licence
Room Number(s)
Licence Holder or Primary Licence Contact
Position of Licence Holder
Telephone Numbers
Complete Address
(include Section, Division, Branch and Sector,
Building, Street, City, Province and Postal Code)
Licensed Use Types and Activities
Part 2. Nuclear Substances and Radiation Devices
(a)
General Information Required for New Permit
Room or Vehicle Number
Laboratory Level
Permit Holder
Position of Permit Holder
Telephone Numbers
Complete Address
Site Radiation Safety Officer
Licenced Activities / Purpose of Licence
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–8
(b)
Radionuclide Information to Be Included on Internal Permit
G
Unsealed Nuclear Substances
Radionuclide
G
Maximum Activity
Contained in any
Single Source
Use
Location
Storage
Locations
Estimated Number
of Sealed Sources
>50 Mbq
Use
Locations
Storage
Locations
Serial
Number
Radiation Devices Containing Sealed Nuclear Substances
Device Manufacturer
(c)
Total Quantity to Be
Acquired per Year
Sealed Nuclear Substances
Radionuclide
G
Maximum Quantity in
Possession
Model and Serial Number
Radionuclide
Activity
Persons (Users) Approved for Work with Nuclear Substances
Name
NRCan Radiation Safety Manual
Chapter 6 – March 2006
Position
Telephone Number
6–9
Dosimetry
Part 3. Instruments Used for Radiation Detection and Monitoring
Instrument
Manufacturer / Number
Model and Serial Number
Part 4. Details of Experiment / Work Involving the Nuclear Substances Listed in Part 2
Part 5. List Other Instruments Labelled for Radionuclide Usage (Centrifuges, Refrigerators, Fume
Hoods, etc.) and Their Location (Room Number)
Part 6. Design Compliance Form for Laboratories
Please complete Form 8, "Design Compliance Form for Laboratories," if you are applying for a room that
has not been previously approved for radioisotope use.
Part 7. Understanding
I accept the designation of Permit Holder and certify that all information submitted is true and correct to the
best of my knowledge.
Signature of Permit Holder
Date of Signature
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–10
APPLICATION FOR INTERNAL PERMIT AMENDMENT
Form 5
Name of Permit Holder
Current Permit Number
Name of Site Radiation Safety Officer
Room Number of Permit
Address of Permit Holder
Phone Number of Permit Holder
AMENDMENT DETAILS
Radioisotope
Use Limit
Open Source
Sealed Source
Activity
Type of Device
COMMITTEE APPROVALS
Approved by
Print Name
NRCan Radiation Safety Manual
Chapter 6 – March 2006
Signature
Date
6–11
COMMITTEE COMMENTS
FOR OFFICE USE ONLY
Revision Number of Permit
Revision Approved
YES
NO
Reason for Not Granting Approval:
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–12
APPLICATION FOR INTERNAL PERMIT RENEWAL
Form 6
Name of Permit Holder
Current Permit Number
Name of Site Radiation Safety Officer
Room Number of Permit
Address of Permit Holder
Phone Number of Permit Holder
Return renewal application to the Radiation Safety Officer within 20 working days prior to the expiry date
on your permit. Failure to submit a renewal application will result in the automatic cancellation of the
permit. All radioactive material will be collected for disposal.
Return Renewal Application by
Confirmation of Current Permit Information:
Indicate no changes if none are required.
If changes are required, make appropriate
amendments.
G
Sealed Nuclear Substances
Radionuclide
G
Activity Requested for New Permit
Radiation Devices Containing Sealed Nuclear Substances
Device Manufacturer
G
Activity on Current Permit
Model and Serial Number
Radionuclide
Activity
Persons (Users) Approved for Work with Nuclear Substances
Name
NRCan Radiation Safety Manual
Chapter 6 – March 2006
Position
Telephone Number
6–13
Dosimetry
G
Instruments Used for Radiation Detection and Monitoring
Instrument
Manufacturer / Number
Model and Serial Number
Permit Holder Signature
Date
Site Radiation Safety Officer Signature
Date
Permit Approval Date
E-mail Confirmation Date
Permit Sent
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–14
DECOMMISSIONING RECORDS
Form 7
ADMINISTRATION
Name of Permit Holder
Current Permit Number
Room Designation
Name of Site Radiation Safety Officer
Room Number of Permit
Address of Permit Holder
Phone Number of Permit Holder
DECOMMISSIONING CHECKLIST
Yes
Radioactive materials have been transferred to a new location
Permit number to which materials have been transferred
New permit has been amended
Radioactive materials have been disposed
Disposal document is attached
Wipe test conducted
Wipe test conducted by
Date
Type of Monitor
Calibration Date
Make, Model and Serial Number
Results Meet CNSC Licence Criteria
(Non-fixed contamination does not exceed 0.5 Bq/cm2 averaged over an area
not exceeding 100 sq/cm2)
Original wipe testing data print-out is attached
Wipe test result in becquerels are attached
Map of areas wiped is attached
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–15
No
N/A
Yes
Instruments have been decommissioned
List of instruments is attached
Wipe test results on instruments is attached
Instruments have been moved to a new location
Permit number to which instruments have been transferred
Instruments will be used for other radioactive work
New permit has been amended to include transferred
instruments
All radioactive warning labels have been removed
The original permit is attached
The manual has been returned to the Radiation Safety Officer
FINAL INSPECTION OF LABORATORY
Date of Inspection
Participants in Inspection
Comments on Inspection
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–16
No
N/A
DECOMMISSIONING SIGN-OFF
The Permit Holder, Site Radiation Safety Officer and Radiation Safety Officer must sign this document
once the laboratory has been declared free of radioactive material. Their signatures confirm the area is
decommissioned.
All documents must be available at the time of the final sign-off for the Site Radiation Safety Officer and
the Radiation Safety Officer.
Permit Holder
Print:
Signature:
Date:
Signature:
Date:
Signature:
Date:
Site Radiation Safety Officer
Print:
Radiation Safety Officer
Print:
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–17
DESIGN COMPLIANCE FORM FOR LABORATORIES
Form 8
A separate form must be completed for each laboratory for which approval is being sought. In the case of
identically constructed laboratories, only one form need be submitted.
This form must be approved by the Radiation Safety Officer (individual authorized to act for the
organization that holds or will hold a licence to use radioactive material in the facility described herein)
after consultation with members of the Radiation Safety Committee. Any changes to the project that will
alter the information supplied on this form must be reported to the CNSC before radioactive material is
used in the laboratory.
Identification of Laboratory / Rm Number
Floor on Which Laboratory Is Located
Description of Building
Complete Address
(Building, City, Province and Postal Code)
Organization (Sector, Branch and
Division)
Description of Work to Be Carried Out in
the Laboratory
Project Name and Description
Estimated Date of Completion
Number of Exemption Quantities to Be
Used
On Open Bench
In Containment
Classification of Lab
Basic Lab
Intermediate Lab
Contact Person
Name
Signature
Name
Signature
Name
Signature
Title
Telephone Number
Site Radiation Safety Officer
Telephone Number
Radiation Safety Officer
Telephone Number
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–18
FOR OFFICE USE ONLY
CNSC File Number
Project Name
Date of First Review
Reviewing Officer
Name
Signature
With Fume Hood
Without Fume Hood
Action / Further Information
Obtained
Approved as
Basic Laboratory
Intermediate Laboratory
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Chapter 6 – March 2006
6–19
1
(a)
Ventilation
Yes
No
Yes
No
Radioactive aerosols or gases are likely to be produced in the laboratory.
(If NO, and if there is no intention to install a fume hood, or glove box, the rest of
section 1 need not be answered.)
(b)
Laboratory will be at negative pressure with respect to surrounding areas.
(c)
A glove box will be installed.
(If YES, please submit details.)
(d)
A fume hood will be installed.
(If NO, subsection 1.1 need not be answered.)
1.1
Fume Hood
(a)
All air from the laboratory will be vented through the fume hood.
(b)
Air vented through the fume hood will be vented without re-circulation.
(c)
The fume hood will be constructed of smooth, impervious, washable and
chemically resistant material.
(d)
Consideration has been given to the weight of shielding that must be supported
by the working surface of the fume hood.
(e)
The working surface of the fume hood will have slightly raised edges.
(f)
The linear face velocity of the fume hood will be between 0.5 and 1.0 metre /
second.
(g)
Before radioactive material is used in the fume hood, the fume will be tested to
verify the flow rate and the absence of counter currents.
(h)
The fume hood will be located near an entrance to the laboratory.
(i)
A readily visible flow-measuring device will be included on the face of the fume
hood.
(j)
There will be an automatic after-hours shutdown system.
(If YES, indicate if there is to be an override provision.)
(k)
The fume hood exhaust will be filtered.
(If YES, please submit details of filtration.)
(l)
Fume hood filters will be monitored for radioactive contamination before
disposal.
(m)
The fume hood exhaust duct will be constructed of corrosion-resistant material.
(n)
All joints in the exhaust duct will be smoothly finished and sealed.
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–20
1.1
(o)
Fume Hood
Yes
No
Yes
No
The fume hood exhaust duct will connect with other exhaust systems.
(If YES, please submit details.)
(p)
The fume hood exhaust duct will have horizontal sections.
(If YES, please submit details.)
(q)
The fume hood exhaust fan will be placed close to the discharge point.
(r)
The fume hood fan motor will be mounted outside the exhaust duct.
(s)
Exhaust stack height will ensure acceptable dilution, dispersion, and elimination
of unacceptable re-entry through building openings.
(t)
Exhaust ducts from fume hoods in radioisotope laboratories will be identified on
plans supplied to maintenance personnel.
(u)
The fume hood exhaust duct will be marked at 3-metre intervals with radiation
warning symbols.
2
Finishing and Fixtures
(a)
Flooring will have an impervious surface with a strippable coating.
(b)
All joints in the flooring material will be sealed.
(c)
Walls and ceilings will have smooth, impervious and washable finishes.
(d)
Counter surfaces will have a smooth, impervious, washable and chemicalresistant finish.
(e)
All joints on counters will be sealed.
(f)
Cupboards and shelving will have smooth, impervious, chemical-resistant and
washable finishes.
(g)
Light fixtures will be easy to clean.
(h)
Light fixtures will be enclosed.
(i)
Sinks will be made of material that is readily decontaminated.
(j)
Sinks will have overflow outlets.
(k)
Taps will be operable by means not requiring direct hand contact.
(l)
An emergency eye-wash station will be installed.
(m)
An emergency shower will be provided.
(n)
Patient washrooms will be finished in materials that are easily decontaminated.
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–21
3
Plumbing
(a)
Faucets with vacuum or cooling line attachments will have back-flow protection
devices.
(b)
The drain from the laboratory will go directly to the main building sewer.
(c)
The drain will connect with drains other than the main building sewer.
Yes
No
Yes
No
Yes
No
Yes
No
(If YES, please submit details.)
(d)
The drain line will be marked at 3-metre intervals with radiation warning
symbols.
(e)
Sink drain traps will be accessible for monitoring.
(f)
Chemical resistance of the drains has been considered.
(g)
Drains from radioisotope laboratories will be identified on plans supplied to
maintenance personnel.
4
Storage
(a)
Waste will be stored in the laboratory.
(b)
An area to store waste outside the laboratory will be provided.
(c)
Materials that may give rise to radioactive aerosols or gases will be stored in an
appropriately vented area.
(d)
Appropriate shielding will be provided for storage locations.
5
Security
(a)
The laboratory will be provided with a lockable storage area or lockable doors.
(b)
The intermediate laboratory will be provided with a good lock on each door.
(c)
A lockable storage area will be provided in the intermediate laboratory.
(d)
The laboratory windows on the ground floor will prevent access.
6
Miscellaneous
(a)
Provision will be made for hanging up potentially contaminated laboratory
clothing within the laboratory.
(b)
Provision will be made for an appropriate radiation-monitoring device to be
installed in the laboratory.
(c)
Food or beverage preparation facilities will be excluded from the laboratory.
(d)
Desks or study facilities will be located in the laboratory.
(e)
Provisions will be made for emergency lighting in the laboratory.
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–22
WASTE DISPOSAL
Form 9
WASTE GENERATOR INFORMATION
Permit Number
Name of Permit Holder
Name of Site Radiation Safety Officer
Room Number of Permit
Address of Permit Holder
Phone Number of Permit Holder
Creation Date (date the container leaves the laboratory for disposal)
Contact (name of person responsible for the radioactive material if
different from Permit Holder)
Signature (contact person)
CONTAINER INFORMATION
Radiation, Surface (total radiation at the surface of the container)
Radiation, 1m (total radiation measured at 1 metre for the
container)
Container Type (physical description of the container)
Inner Packaging (physical description of the container)
RADIOACTIVE CONTENT
Radiochemical (proper chemical name used for all material being
disposed)
Radionuclide (list of isotopes being disposed)
Physical State (physical state of the material)
Quantity (how much of the material is being disposed of in millilitres
or grams)
Package (description of the packaging of the material, for example,
glass, plastic)
Radioactivity (activity level of the isotope being disposed)
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–23
OTHER CONTENTS
Material Description (description of material that is in the container for
disposal, for example, lab coats, gloves, plastics, glass pippets)
Physical State (physical state of the material: solid, liquid, gaseous)
Quantity (how much is in the package in grams)
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–24
WIPE TEST RESULTS
Form 10
Permit Number
Name of Permit Holder
Name of Site Radiation Safety Officer
Room Number of Permit
Date
Checked by
AREA MAP
Wipe
Number
Site
Initial Count
1
2
3
4
5
6
7
8
9
NRCan Radiation Safety Manual
Chapter 6 – March 2006
6–25
Recount after
Decontamination
Notes
SHORT-TERM EMPLOYEE RADIATION SAFETY TRAINING RECORD
Form 11
Employee Name:
Position:
Division/Branch/Sector:
Education or Qualifications:
Description of Training
Date Received
Employee’s Signature
Review of Radiation Safety Manual
Review of Radiation Safety Training
Manual
In-house (on-the-job) Training
Other
Validation Period:
Verified and Approved by:
Signature of Permit Holder
Date:
Signature of Site Radiation Safety Officer
Date:
Signature of Radiation Safety Officer
Date:
Once all training has been completed, this signed form must be attached to the permit. A copy must also
be given to the Site Radiation Safety Officer and the Radiation Safety Officer.
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Chapter 6 – March 2006
6–26
Chapter 7:
Glossary of Terms
Absorbed Dose
The amount of energy absorbed in the body, or in an organ or tissue of the body, due to exposure to
ionizing radiation, divided by the respective mass of the body, organ or tissue. The original unit of
absorbed dose was the rad while the SI unit of absorbed dose is one joule per kilogram and is named
the Gray (Gy); 1 Gy = 1 joule/kg. It is not necessarily equivalent to the dose to which the system is
exposed.
Absorption
The process by which radiation transfers some or all of its energy to the medium through which it is
passing.
Absorption Coefficient, Linear (:)
The fractional decrease in the intensity of a beam of gamma or X-radiation as it passes through an
absorbing medium. It is expressed per unit thickness of medium (usually cm-1). The value of the linear
absorption coefficient is unique for the absorbing material and dependent on the density of the
absorbing medium. The value of : is used in the equation I = IoAe-:x, where I is the intensity and x is the
thickness of the absorber in the same base units as :.
Absorption Coefficient, Mass (:m)
The linear absorption coefficient of a material divided by the density of the absorbing material. It is
expressed in units of cm2/g. The mass absorption coefficient is independent of the density or nature of
the medium. For example, the mass absorption coefficient of water for 1.0 MeV gamma rays is
0.0707 cm2/g. The linear absorption coefficient of water as liquid (20°C) is (0.0707 x 0.998234) =
0.0706 cm-1; and for water as ice (-20°C), it is (0.0707 x 0.99349) = 0.0702 cm-1.
Activation
The process of making a material radioactive, generally by the absorption of neutrons (must be of
more than 10 MeV energy). Activation is used in the SLOWPOKE Reactor to allow analysis of very
small amounts of materials by the subsequent radiation that is given off during decay of the activated
material.
Activity
The rate of nuclear transformations or transitions occurring in a radioactive source. The SI unit of
activity is the becquerel (Bq), one disintegration per second. Often used loosely to mean radioactivity.
Alpha Particle (")
A small charged particle consisting of two neutrons and two protons. It is sometimes emitted from the
nucleus of the higher atomic number elements during radioactive decay. The alpha particle is the
nucleus of a helium 4 atom; it is not very penetrating. Due to the +2 charge, it is very effective at
causing ionizations along its limited path length. An alpha particle will not travel very far in air and is
effectively stopped by a sheet of paper or the dead cell layer of the skin.
Annihilation Radiation
The radiation emitted as a result of the interaction of a positron (positively charged beta particle) and
an electron or negatron (negatively charged beta particle). The annihilation of these particles results in
the disappearance of the two particles and the formation of two gamma rays, each of 0.511 MeV,
which are oppositely directed.
NRCan Radiation Safety Manual
Chapter 7 – March 2006
7–1
Annual Limit on Intake (ALI)
An ALI is the limit of a radioisotope, measured in becquerels, that is allowed for ingestion or inhalation
while working with radioisotopes. An intake of 1 ALI is assumed to provide a whole body radiation
dose equivalent to the maximum annual allowable exposure. The actual amount of a radioisotope that
constitutes an ALI depends on the current maximum permissible exposure level.
Artificial Radioactivity
Man-made radioactivity produced by particle bombardment or electromagnetic radiation (cesium 137).
As Low As Reasonably Achievable (ALARA)
A level of individual or collective dose or intake, or effluent release, or of any other parameter related
to radiation dose, such that the cost of reduction to a lower level would, under the given
circumstances, exceed the resulting health benefit; the health benefit being the reduction in
"detriment" resulting from the reduction in dose.
Atomic Number (Z)
The number of protons in the nucleus of an atom. The atomic number determines the chemical
properties of the element. Atoms with the same atomic number but differing in the number of neutrons
are called isotopes.
Atomic Mass (A)
The total number of neutrons and protons in an atom.
Attenuation
The reduction in intensity of radiation as a result of being absorbed in a medium as it passes through
the medium.
Autoradiograph
A record of the radiation emitted from a sample on photographic film. It is made by placing the sample
containing the radioactive material in close proximity to the photographic film.
Background Radiation
Radiation arising from natural sources in the environment. There are four principal sources of ionizing
radiation in the environment: cosmic radiation; external radiation from rocks and soil; internal radiation
from radioactive materials in the body; and internal radiation from radon gas in the air. The annual
dose equivalent from background radiation sources in Toronto, Ontario is approximately 300 mrem
(3.0 mSv).
Becquerel
The SI unit of radioactivity; it is equivalent to 1 disintegration per second. (See curie.)
Beta Particle ($)
A small, electrically charged particle ejected by the nucleus during radioactive decay. A beta particle
usually has a negative electric charge and may be known as a negatron ($-). Beta particles may also
have a positive charge, and these are known as positrons ($+). Although the range in air can be
several metres, negative beta particles are effectively stopped by low atomic number materials such
as Plexiglas.
NRCan Radiation Safety Manual
Chapter 7 – March 2006
7–2
Bioassay
The assessment of the uptake of radioactive materials into the body. Two methods are available, in
vitro and in vivo. The former involves taking a specimen, usually a fluid such as urine, and measuring
the radioactivity in it by use of a suitable counter. The material is assessed external to the body. In
vivo techniques involve placing a radiation monitor near the body and measuring the radioactivity
being emitted from radioactive material within the body. An example of this is the use of a detector
placed near the thyroid to measure uptake of 125I by counting the gamma radiation emanating directly
from the gland.
Bremsstrahlung
A phrase derived from the German language, it literally means "braking radiation." Electrons that
approach the nucleus of a high atomic number element will be slowed down. The change in energy is
emitted as X-radiation and is known as bremsstrahlung radiation. This is the primary means by which
X-rays are generated in X-ray machines. Accelerated electrons are slowed by the tungsten atom
nucleus in the target material and bremsstrahlung is emitted. Bremsstrahlung can also be emitted by
electrons emitted during negative beta decay which interact with the walls of the container in which the
radioactive material is located.
Calibration
The process of determining the accuracy of equipment used for radiation monitoring. Generally, the
response of a radiation monitor is compared to the amount of radiation from a known source. By
convention, most instruments for gamma radiation monitoring are calibrated against the 0.662 MeV
gamma rays emitted from 137Cs.
CNSC
CNSC is the acronym for the Canadian Nuclear Safety Commission, the federal regulatory agency
responsible for the possession and use of radioactive materials in Canada. On May 31, 2000 the
CNSC replaced the Atomic Energy Control Board (AECB).
Cancer, Solid
A form of cancer involving a tumour mass. It may be in one or more locations within the body. The
other general form of cancer is leukemia, which is a cancer of the blood and blood-forming tissues. No
specific tumour mass is involved in leukemia.
Carcinogenic
The ability of a material to cause cancer, whether it is chemical, biological or physical in nature.
$-naphthylamine is an example of a carcinogenic chemical and ionizing radiation is an example of a
carcinogenic physical agent.
Carrier
A non-radioactive or non-labelled material of the same chemical composition as the corresponding
radioactive or labelled counterpart.
Carrier-Free
A solution or material lacking a carrier. Essentially, the pure radionuclide.
Collective Dose Equivalent
The sum of the individual radiation doses received by a group of persons, expressed in
Person-Sieverts.
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Chapter 7 – March 2006
7–3
Committed Dose Equivalent (or Committed Equivalent Dose)
The total radiation dose received from a radioactive substance in the body during the 50 years
following the intake of that substance.
Contamination (Radioactive)
Radioactive material deposited on a surface or in a medium where it is not wanted. Surface
contamination is generally monitored through the use of the wipe test.
Counter, Scintillation
An instrument designed to measure very small amounts of radioactivity, generally from negative beta
decay. It involves placing the radioactive material in a vial containing an organic aromatic solvent and
fluor molecules. As the radiation is given off, the beta particles interact with the organic aromatic
solvent and cause excitation of the molecules. The other organic compounds in the mixture convert
the excitation energy to fluorescence. The light emitted during the fluorescence is detected by very
sensitive photomultiplier tubes positioned outside of the vial. The signal from the photomultiplier tubes
is processed and then converted into counts per minute. Due to the fact that the radioactive material is
intimately mixed with the primary detector, detection efficiency is much higher than with other means
of detection.
Critical Organ
The body organ receiving a radionuclide or radiation dose that results in the greatest overall damage
to the body. Generally, the critical organ depends on the isotope. For example, for 125I and 131I, the
critical organ is the thyroid due to the preferential uptake of iodine by that gland and its susceptibility to
radiation damage. Other organs and tissues of the body will be irradiated following the uptake of
radioiodine but the thyroid will exhibit damage first.
Curie (Ci)
The former unit for expressing radioactivity. The curie was originally based on the decay of 1 gram of
radium and is equivalent to 37 billion disintegrations per second. More common units are the millicurie
(mCi) and the microcurie (:Ci). This unit is being replaced by the SI unit known as the becquerel (Bq).
One :Ci is equivalent to 37 kBq.
Decay Constant
The fraction, lambda (8), of the number of atoms of a radioisotope that decay in a unit time. It is
expressed as the reciprocal of time (e.g., seconds-1) and is related to the half-life by the following
equation: 8 = 0.693/T½.
Decay, Radioactive
The spontaneous transformation of radioactive material into a different nuclide. The transformation
usually involves the emission of some form of energetic particle or photon.
Decommissioning
Actions taken in the interest of health, safety, security and protection of the environment to retire a
nuclear facility permanently from service. Decommissioning is also used to refer to the cleaning of a
radioisotope laboratory so that it can be removed from an internal permit.
Delay and Decay
The storage of radioactive waste containing radionuclides with short half-lives for a sufficient time to
enable their unrestricted discharge to the environment when their final activity level is below regulatory
limits.
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Chapter 7 – March 2006
7–4
Deterministic Effects (See Non-stochastic Effects)
Disintegration
The process by which a radionuclide undergoes radioactive decay. Another means of expressing
radioactive decay although there is no actual disintegration of material involved.
Disposal, Waste
The permanent and secure containment of radioactive wastes, with no intention to retrieve them.
Dose, Radiation
A general term denoting the quantity of radiation or the radiation energy absorbed by a medium.
Dose Equivalent (or Equivalent Dose)
The product of absorbed dose and Radiation Weighting Factor and all other modifying factors
necessary to obtain an evaluation of the effects of irradiation received by exposed persons, so that the
different characteristics of the exposure are taken into account. The unit for dose equivalent is the rem
while the SI unit of dose equivalent is the sievert (Sv).
Dose Rate
Radiation dose emitted per unit of time.
Dosimeter
A device used to measure and record the dose of radiation to which a person has been exposed.
Some dosimeters are able to report in units of absorbed dose.
Dosimetry
The measurement of radiation dose. Carried out by either practical measurements or theoretical
evaluation.
DPM
Acronym for disintegrations per minute.
Efficiency (Counter)
The ability of a radiation monitoring instrument to detect radiation. It is a function of the geometry and
design of the detector as well as the internal electronics. It may also be dependent on the type of
radiation being monitored.
Electromagnetic Radiation
The propagation of varying electric and magnetic fields through space at the speed of light, exhibiting
the characteristics of wave motion.
Electron
A nuclear particle with a negative electric charge equal numerically to the charge of the proton and a
mass of 1.8040e-3 atomic mass units.
Electron Volt (eV)
A measure of energy. It is commonly used for expressing the energy associated with radioactive
decay. It is the amount of energy gained by an electron travelling through a potential difference of one
volt. Common multiples include the kiloelectron volt (keV) and the megaelectron volt (MeV).
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Erythema
Reddening of the skin caused by exposure to radiation. The skin erythema dose (SED) was a unit of
radiation exposure in the early part of the 1900s. It is due to the dilation of the capillaries in the skin
and occurs with exposure to ionizing radiation doses of about 1000 rem (10 Sv).
Exemption Quantity (EQ)
EQ, previously referred to as scheduled quantity (SQ), is a regulated amount of radioactivity of an
isotope that is specific for each licence and radioisotope. The Canadian Nuclear Safety and Control
Act regulates and determines the EQ, based on the radioactive properties and the relative risk
associated with that isotope during shipping and disposal. These values are set by the Canadian
Nuclear Safety Commission (CNSC) using standards developed by the International Commission of
Radiological Protection (ICRP). The EQ is an amount that would not be expected to cause serious
health effects if ingested or inhaled. The EQ is dependent on the radiotoxicity and chemical toxicity of
the radionuclide and is used to determine the status of a laboratory, where 1 EQ is the maximum
amount that may be handled in an ordinary laboratory with no special precautions. Up to 1000 EQ
may be handled in a basic-level radioisotope laboratory while larger amounts must be handled in an
intermediate-level radioisotope laboratory.
Exposure Dose
The measure of ionization produced in air by gamma or X-radiation. Originally measured in
röntgens (R), the current SI equivalent is coulombs per kilogram of air.
Exposure, Acute
Typically, exposure to a hazardous agent for a period of less than 24 hours.
Exposure, Chronic
Typically, exposure to a hazardous agent for more than 24 hours.
Film Badge
An old reference to the personal dosimeter worn for monitoring exposure to radiation. Originally, the
small badges contained pieces of photographic film that were developed following the wearing period.
The amount of radiation to which the person was exposed could be assessed from the density of the
clouding of the film. The photographic film in the badges has since been replaced by small
thermoluminescent crystals.
Gamma Photon
Electromagnetic radiation emitted by the nuclei of radioactive substances during radioactive decay,
similar in nature to X-rays.
Gamma Ray (()
An energetic photon emitted from the nucleus during radioactive decay. It is a very penetrating form of
ionizing radiation requiring lead or concrete for effective shielding. Usually emitted from radioisotopes
in very discrete energies.
Geiger-Müller Tube (GM tube)
The main component of most commonly available radiation detection instruments. It consists of a
hollow tube filled with a gas and contains a central electrode running parallel to the length of the tube.
The shell of the tube forms the other electrode. The tube is held at a high potential voltage,
approximately 1200–1800 volts, and radiation passing through the gas will cause it to become ionized.
The ionization is amplified and detected by the supporting circuitry. The GM Tube may also have a
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small amount of material wrapped around it to improve its response over a wide range of radiation
energies and is known as an energy-compensated detector. If the end of the tube is made of a thin
material such as Mylar, it is called a thin-end window detector and the GM tube can be sensitive to
some alpha and beta radiations. Generally, the efficiency of a GM tube is approximately 1%.
Genetic Damage
Damage caused to genes in cells that are part of the reproductive organs. Genetic damage does not
affect the current generation but may be passed on to future generations.
Gray (Gy)
The SI unit of absorbed dose, it is equivalent to one joule per kilogram.
Half-life, Physical
The characteristic time taken for the activity of a particular radioactive substance to decay to half of its
original value; that is, for half the atoms present to disintegrate.
Half-life, Biological
The characteristic time required for the amount of a substance to be reduced to one half its initial
value due to elimination by biological processes alone. The biological half-life is not dependent on the
radioisotope but does depend on the organ or body system in which the material is deposited and the
chemical properties of the material.
Half-life, Effective
The characteristic time required for a radioactive material to be eliminated from a biological system
through a combination of the physical and biological removal processes. The effective half-life is a
mathematical combination of the physical and biological half-lives of the particular radioisotope.
Half-Value Layer
The thickness of shielding material required to reduce the intensity of a given type of radiation to
one half of the original amount. Related to the tenth-value layer.
Hazardous Lifetime, Radiologically
The length of time a material poses a potential radiological hazard if it is not contained and isolated
from the public and the environment.
Health Physics
The branch of science dealing with radiation protection. It arose as a result of the development of the
atomic bomb in the Manhattan Project. There is some suggestion that the phrase arose as a result of
the need for the secrecy surrounding the development of the bomb. Supposedly, words associated
with radiation could not be used and so it was decided to call the field health physics. Persons working
in the field of radiation protection may also be referred to as health physicists.
IAEA
Acronym for the International Atomic Energy Agency. It is an international body within the United
Nations that provides advice and assistance to member nations on the use of nuclear power.
ICRP
Acronym for the International Commission on Radiological Protection. Originally known as the
International X-ray and Radium Protection Committee, it was reorganized in 1950 to become the
ICRP. The ICRP publishes recommendations on radiation protection that are usually the basis of
legislation for radiation protection. This is the situation in Canada where the CNSC adopts the
recommendations of the ICRP.
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Inverse Square Law
The relationship between distance and intensity for radiation. The intensity of radiation from a point
source is inversely proportional to the square of the distance from the source. This relationship has
application in radiation protection, especially in the use of tongs or other handling devices to reduce
radiation doses to the fingers and hands.
Ion
An atomic particle, atom or chemical radical that carries a net electrical charge, either positive or
negative.
Ionization
The process by which electrons are removed or added to atoms to create ions. Radiation that
possesses enough energy to remove orbital electrons is called ionizing radiation.
Ionization Chamber
A small chamber used for the measurement of radiation exposure. Similar to a Geiger-Müller tube, it is
operated at much lower electrical potentials. The fundamental principle of gas ionization by radiation
still applies but since the potential voltage is not as great, the amount of amplification in the tube is
small. Generally used for personal dosimeters and standardization instruments.
Ionization Radiation
Radiation that removes orbital electrons from atoms, thus creating ion pairs. Alpha and beta particles
are more densely ionizing than gamma rays or X-rays of equivalent energy. Neutrons do not cause
ionization directly but by collision losses during scattering.
Irradiation
The process of exposing some material to radiation.
Isotopes
Atoms with the same atomic number (number of protons in the nucleus) but having different atomic
mass numbers because of different numbers of neutrons in the nucleus. Isotopes of a given element
all behave the same chemically although some may be radioactive.
Labelled Compound, Radioactive
A molecule that has had one of its atoms replaced by a radioactive element of the same kind. The
path of the molecule through a biological system can be traced when it has been labelled.
Latent Period
The period of time between the exposure to radiation and the expression of radiation injury. Generally
applied to cancer induction from chronic radiation exposure, the latent period can be anywhere from
5–10 years for leukemia to 20–30 years for solid cancers.
Linear Energy Transfer (LET)
A measure of the rate at which an energetic particle transfers energy to the surrounding medium.
Alpha particles have a high LET while beta particles have a lower LET. The electrons set in motion as
a result of gamma ray absorption have the lowest LET by comparison. Generally expressed in units of
keV per micrometre of path length.
Maximum Permissible Concentration
The concentration of a radioisotope that, if inhaled or ingested, would provide a whole body dose
equivalent that is equal to the maximum annual radiation exposure limit.
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Natural Radioactivity
The property of radioactivity exhibited by naturally occurring radionuclides (uranium 238, thorium 137).
Negatron ($-)
A negatively charged electron. Most commonly referred to as an electron although not strictly correct.
(See also Beta Particle.)
Neutron
A nuclear particle having a mass similar to a proton but having no electrical charge. During negative
beta decay ($-), a neutron disintegrates into a proton and a negatron, with the negatron being ejected
from the nucleus. Neutrons can exist outside of the nucleus and have a high potential for radiation
damage since they must lose energy by scattering. Shielding for neutron sources involves using
materials containing large amounts of hydrogen as well as boron.
Non-ionizing Radiation
Electromagnetic radiation that is not capable of disrupting the chemical bonds of molecules but is
capable of creating photochemical, heating and other effects.
Non-stochastic Effects (Deterministic Effects)
Health effects caused by radiation that occur only above a given dose threshold and the severity of the
effect depends on the absorbed dose. An example of a non-stochastic effect is cataract formation in
the lens of the eye.
Nuclide
A general term referring to all isotopes of an element.
Nuclear Energy Worker (NEW)
A person who is required, in the course of the person's business or occupation in connection with a
nuclear substance or nuclear facility, to perform duties in circumstances where there is a reasonable
probability that the person may receive a greater dose of radiation than the prescribed limit for the
general public.
Nucleus
That part of the atom in which the total positive charge and most of the mass is concentrated.
Photon
A quantum of energy emitted in the form of electromagnetic energy. Gamma photons originate in the
nucleus.
Point Source
A source of radiation, the physical size of which does not influence the intensity of radiation being
monitored at any given location. It can be considered to arise from a single point.
Positron ($+)
A positively charged electron emitted from the nucleus during some forms of radioactive decay. A
positron will combine with an electron or negatron ($-) and result in the production of annihilation
radiation. (See also Beta Particle.)
Proton
Elementary nuclear particle with a positive electric charge equal to the charge of the electron and a
mass of 1.007277 atomic mass units.
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Radiation
The emission and propagation of energy through a medium without requiring the medium for
propagation. Generally used to refer to ionizing radiation.
Radiation, External
Radiation received by the body from a radioactive source external to the body.
Radiation, Internal
Radiation received by the body from radioactive materials inside the body.
Radiation Weighting Factor
A modifying factor used in the derivation of dose equivalent. It is used in comparisons of different
types of radiation. Previously known as the quality factor.
Radioactive
Exhibiting radioactivity.
Radioactivity
The property of a certain nuclide to spontaneously emit particles or gamma radiation or to emit
X-radiation following orbital electron capture or to undergo spontaneous fission.
Radioisotope (Radionuclide)
A radioactive isotope.
Radiolysis
Chemical decomposition by the action of ionizing radiation.
Radioresistant
Resistant to the effects of irradiation, principally applied to biological systems. Cells of the body that
are not easily damaged by exposure to ionizing radiation are termed radioresistant.
Radiosensitive
Sensitive to the effects of irradiation, principally applied to biological systems. Cells of the body that
are easily damaged by exposure to ionizing radiation are termed radiosensitive.
Radiotoxicity
The term referring to the potential of a radioisotope to cause damage to living tissue by the absorption
of energy from the disintegration of the radioactive material that is within the body.
Reference Man
A standard model of a human being, developed by the International Commission on Radiological
Protection (ICRP) and detailed in ICRP Report 23. The characteristics of standard man are used when
specific body information is not available for dosimetry purposes.
Regulatory Dose Limit
A legal limit on radiation dose specified in the General Nuclear Safety and Control Regulations.
Relative Biological Effect (RBE)
For any given living organism, the ratio of the absorbed dose of a reference radiation that produces a
specific biological effect to the absorbed dose of the radiation of interest that produces the same
biological effect.
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Röntgen Equivalent Mammal (rem)
The older term used to describe equivalent dose. The rem is a product of the absorbed dose in rads,
the Radiation Weighting Factor and any other modifying factors. The SI unit is the sievert (Sv):
1 Sv = 100 rem.
Röntgen; also spelled Rœntgen or Roentgen (R)
Named after Wilhelm Röntgen, it is a unit of radiation exposure. Useful submultiples include the
milliröntgen (mR) and the microröntgen (:R). This is gradually being replaced by the SI equivalent,
which is coulombs per kilogram of air.
Sealed Source
A radioactive material in a capsule that is sealed or in a cover to which the radioactive material is
bonded, where the capsule or cover is strong enough to prevent contact with and dispersion of the
radioactive material under the conditions of use for which the capsule or cover is designed.
Shielding
The use of absorbing material between a source of radiation and the detector or recipient. Shielding
absorbs radiation and reduces the intensity of the incident radiation. It does not change the energy of
the incident radiation. Shielding is chosen on the basis of its effectiveness for a given type of radiation,
its cost and other physical attributes.
SI
Acronym for Système International, it is an international system of units of measurement.
Sievert (Sv)
The SI unit for equivalent dose. It is gradually replacing the rem; 1 rem = 0.01 Sv.
Somatic Injury
Injury to tissues of the body other than the reproductive organs. Somatic injury affects the current
generation but is not passed on to future generations.
Source, Radioactive (or Radiation)
Any quantity of radioactive material intended for use as a source of radiation.
Specific Activity (Specific Radioactivity)
The activity of a radionuclide divided by the mass of the element whose radionuclide is considered.
The activity of a material divided by its mass or volume.
Stochastic Effects
Health effects caused by the absorption of radiation. Stochastic effects occur randomly without
evidence for a threshold value. While the severity of the effect does not depend on the dose, the
probability of the production of stochastic effects is thought to be linearly related to radiation dose.
Survey Meter
An instrument used to measure radiation, typically radiation exposure dose. The instrument usually
consists of an energy compensated Geiger-Müller (GM) tube and associated circuitry that causes a
meter deflection or other readout in the presence of ionizing radiation.
Tenth-Value Layer
This is the amount of shielding required to reduce the intensity of gamma or X-radiation to one tenth of
its initial value. The tenth-value layer is generally applied in X-ray work since the initial shielding may
change the quality of the X-ray beam.
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Thermoluminescent Dosimeter (TLD)
A personal dosimeter that uses solid crystals to monitor radiation absorbed dose. Typically, these
crystals are composed of lithium fluoride (LiF) and exhibit radiation absorption characteristics similar
to that of human tissue. The ionizing radiation produces small local crystal defects that are stable until
the crystal is heated. When the crystal is heated to temperatures of approximately 200°C, the defects
are removed and the associated energy is released in the form of light. The amount of light produced
is proportional to the number of crystal defects induced which in turn is related to the amount of
radiation absorbed.
Waste, Radioactive
Any material containing or contaminated with radionuclides in concentrations greater than would be
considered acceptable for uncontrolled use or release, and for which there is no foreseen purpose.
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Chapter 8:
Special Procedures
The special procedures listed below are not included in the manual. They are available upon request.
•
Radiography Survey Meter – Technical Manual
•
Working with Nuclear Gauges
•
Gamma Rays Systems, Series 900
•
Alpha Scintillation Probes
•
Portable Radiation Monitor
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Chapter 9:
CNSC Legislative Documents
The Radiation Safety Manual is based on the following Canadian Nuclear Safety Commission (CNSC)
legislative documents. They are not included in the manual, but links are provided below to versions of
them on Government of Canada websites.
•
Nuclear Safety and Control Act
<http://law s.justice .gc .ca/en /N-28.3 /ind ex.htm l>
•
General Nuclear Safety and Control Regulations
<http://law s.justice .gc .ca/en /n-28.3/s or-2000-202/1 53798.h tm l>
•
Radiation Protection Regulations
<http://law s.justice .gc .ca/en /n-28.3/s or-2000-203/1 54458.h tm l>
•
Nuclear Substances and Radiation Devices Regulations
<http://law s.justice .gc .ca/en /n-28.3/s or-2000-207/1 54139.h tm l>
•
Packaging and Transport of Nuclear Substances Regulations
<http://law s.justice .gc .ca/en /n-28.3/s or-2000-208/1 54290.h tm l>
•
Nuclear Security Regulations
<http://law s.justice .gc .ca/en /n-28.3/s or-2000-209/1 53978.h tm l>
•
Re gulatory Guide G– 121 , Radiation Safety in Educational, Medical and Research Institutions
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G121 _EE.pdf>
•
Re gulatory Guide G– 219 , Decomm issioning Planning for Licensed Activities
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G219 _e.pdf>
•
Re gulatory Guide G– 129 , Ke eping Ra diation Ex posures “As Low As Re asonably Achievable
(ALAR A)”
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G129 rev1_e.pdf>
•
Re gulatory Guide R–117 , Requirements for Gamm a Radiation Survey Meter Calibration
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /R-117E .pdf>
•
Re gulatory Guide R–116 , Requirements for Leak Testing Selected Sealed Radiation Sources
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /R-116E .pdf>
•
Re gulatory Policy P–290, Manag ing R adioactive W aste
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /P290_e.pd f>
•
Re gulatory Policy P–211, Compliance
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /P211_e.pd f>
•
Dra ft Re gulatory Guide G– –31 3, Radiation Safe ty T raining Program s for W orkers Inv olved in
Licensed Activities with Nuclear Substances and Radiation Devices, and with Class II Nuclear
Facilities and Prescribed Equipment
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G-313P ublicConsultationMay05_e .pdf>
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•
Dra ft Re gulatory Guide G– 302 –3.1 , CNSC Type I Inspection of Activities and Devices for Nuclear
Substances and Radiation Device Licensees - Group 3.1 Licensees
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G302 -3.1_e.pdf>
•
Dra ft Re gulatory Guide–30 3–3 .1, CNSC Type II Inspection of Activities and Devices for Nuclear
Substances and Radiation Device Licensees - Group 3.1 Licensees
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /G303 -3.1_e.pdf>
•
Dra ft Re gulatory Guide G– 300 –3.1 (Us e T ypes: 815, 841, 847, 849, 851, 857, 863), Annual
Compliance Reporting – Group 3.1 Licences
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /group3.1.pdf>
•
Propos ed R egu latory G uide, C–200 , Radiation Safety Training for Radioisotope, Medical Accelerator
and Tran sportation W orkers
<http://www.cn sc.gc.ca/pubs _catalogue/uploads /c200_e.pdf>
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Annex A
Radiation Safety Committee Terms of Reference
1.
Context
Research work using radioactive material is carried out and devices capable of producing ionizing
radiation are used at Natural Resources Canada (NRCan) facilities. All work with ionizing radiation,
regardless of how small a radiation dose is received, is regarded as a potential risk to health. The rules
and regulations established are designed to minimize exposure to ionizing radiation, ensure safe working
conditions and provide for the protection of the environment. The NRCan Radiation Safety Committee
(RSC) is committed to the concept of ALARA where all radiation exposures are kept As Low As
Reasonably Achievable.
Regulations require that each licence have an RSC with sufficient authority to implement and enforce the
radiation safety program encompassing the department's ordering, usage, handling, monitoring, storage
and disposal of radioactive materials.
In Canada, the possession and the use of radioactive materials are governed by the Canadian Nuclear
Safety and Control Act administered by the Canadian Nuclear Safety Commission (CNSC). The Assistant
Deputy Minister, Corporate Management Sector, authorizes the RSC for NRCan to administer this licence
and to be responsible to the Assistant Deputy Minister (ADM) for all aspects of radiation safety at NRCan.
Ensuring compliance with the terms of federal regulations for the procurement and management of
radioactive materials within NRCan is therefore the responsibility of the NRCan RSC.
2.
Roles and Responsibilities
See Chapter 1 of RSM for a detailed list of key duties and responsibilities.
(a) Departmental Radiation Safety Committee (RSC)
The responsibilities of the NRCan RSC includes all sources of ionizing radiation (both materials and
devices), for whatever use, on all properties occupied by NRCan employees. To this end, the committee
also has the authority to recommend the suspension, when necessary, of the use of any radioisotope or
radiation-producing devices regardless of the source of authorization.
The RSC considers and advises on the establishment of radiation emergency measures within NRCan
facilities and co-operation and integration with other programs. The Committee also conducts educational
programs as required with respect to radiation hazards.
The RSC has the authority to consult with appropriate persons or institutions to revise administrative
procedures for the use of radioactive materials as circumstances warrant.
(b) Radiation Safety Officer (RSO)
The departmental Radiation Safety Officer (RSO) shall administer the Nuclear Substances and Radiation
Devices Licence issued for the consolidated use of nuclear substances issued to NRCan by the CNSC by
overseeing and coordinating all aspects of radiation safety within the institution. The RSO will also act as
the liaison for NRCan with other organizations, as well as the RSC and users.
(c) Site Radiation Safety Officer (SRSO)
The Site Radiation Officer (SRSO) will participate in and attend the RSC meetings. The SRSO will also
maintain a radiation safety control and assessment program in conjunction with the RSC within their
own site.
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3.
Committee Structure
(a) Membership
The committee meetings are co-chaired by the RSO and a sector senior management appointee.
The sector senior management appointed by the sector ADM shall be at a Director level, or higher. The
appointment period is from January 1 to December 31 of a given year.
The senior management appointee is responsible to ensure problems and requests that require ADM's
attention or approval are raised at the appropriate level or before the Executive Committee, as required.
All four sectors will appoint, in turn, a co-chairperson for the one year their sector is responsible for the
chairperson. The order of appointment starting January 2004 will be as follows:
1. Canadian Forest Service
2. Earth Sciences Sector
3. Minerals and Metals Sector
4. Energy Technology and Programs Sector
The committee will also be comprised of SRSOs from each site and from all four science sectors. The site,
size and use of radioactivity will determine the number of individuals for each site.
In addition, special advisors will sit on the committee to provide technical advice as necessary.
Ex officio members and observers will participate without any voting authority. However, under certain
circumstances ex officio members may participate in the voting process (see Section c below).
All voting members (SRSOs and their alternates) should have professional experience and expertise in
the use of radioactive materials.
(b) Method of Appointment
The representatives will be appointed by their respective senior management and report either directly or
functionally to senior management within their sector.
(c) Alternates
Every SRSO shall designate an alternate who should have the same or equivalent professional
experience, expertise and authority as the SRSO. The alternates will attend the meetings in the absence
of the SRSOs. An ex officio member may be appointed by the SRSO as the alternate and will have voting
privileges in the absence of the SRSO.
(d) Tenure of Membership
The term of appointment for members will be for an undefined period. Members shall notify the
Chairperson of the committee in writing of their departure. Upon departure, senior management will
appoint a replacement to fill the vacancy.
(e) Secretary
Secretariat support shall be provided by the RSO.
(f) Guests
Other special advisors or technical experts and guests may be invited to attend meetings as required.
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4.
Meetings
(a) General Meetings
Meetings shall take place in the National Capital Region in a conference room provided by the RSO.
Arrangements for teleconferences will be made by the RSO.
When English- and French- speaking representatives participate in meetings, both oral and written
communications should reflect equality of status of the two official languages. This committee will ensure
that there is full comprehension by all members.
All meetings will be held in the afternoon between 1:30 p.m. and 3:30 p.m. (Ottawa time) to ensure that all
regions are able to attend.
(b) Regular Meetings
The committee shall meet three times during the licensing reporting period (from December 1 to
November 30) for regular meetings (spring, fall and winter).
(c) Additional or Special Meetings
Special meetings will be held as required to address specific issues at the call of the co-chairpersons or
other members.
(d) Quorum
A quorum shall consist of representation from a minimum of six sites for regular meetings. Note: Each
SRSO or his or her alternate is required to attend two out of three regular meetings per reporting
period.
Note that there may be a requirement for all SRSOs to participate if a special meeting is called.
5.
Record Keeping
(a) Agenda
The secretary shall prepare the agenda and send it to all committee members to solicit any additional
agenda items or revisions prior to the meeting date. The revised agenda will be available at the meeting,
and by electronic mail.
(b) Minutes
The secretary shall prepare the draft minutes as soon as possible following the meeting and forward to
members for comments. The final draft minutes will subsequently be distributed to all members for
approval during the next meeting.
6.
Documentation
All relevant radiation safety documentation received or prepared by the RSO will be forwarded to the
committee members as required.
7.
Amendments
These terms of reference may be amended by a majority of committee members on an "as required"
basis. Generally, the terms of reference will be reviewed and amended (if required) on a yearly basis.
Last approval date:
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Below requirements
not checked
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Notification of corrective actions for items of non-compliance must be returned to RSO by:
Items of non-compliance:
Activities/Comments:
Inspector name:
High
C=
N/C=
Inspection Date:
H=
Meets requirements
not applicable
Persons seen:
Medium
B=
N/A=
Permit Numbers and Permit Holders:
Location:
M=
Low
Risk
L=
Exceeds requirements
Unacceptable
Rating: A=
E=
Annex B
Internal Inspection Checklist
D=
Significantly below requirements
Area Classification
Description
LC VI) 6.
Requirements
Rating
Comments
Area Posting
RP 21 (1) (all)
Radiation warning signs
RP22
Frivolous Posting of Signs
RP 23
Internal authorization
LC VI) 1
Internal Permit posted
LC VI) 1
List of users
NSRD 36 (1) (b)
Appointed SRSO
Inventory
NSRD 36 (1) (a)
Emergency contact information
No eating, no drinking
NRCan Radiation Safety Manual
Annex B – March 2006
Verify that a no eating, drinking... is posted.
M
Verify that the name and 24 hour number of the emergency contact is posted.
H
B–2
Verify that an inventory is maintained and that it includes details of name, quantity, and location; for sealed source(s) the model and serial number of the source; for radiation device(s), the model
and serial number of the device; for unsealed sources the quantity used and the manner in which it was used. (on internal permit)
M
Verify that a Site Radiation Safety Officer has been appointed.
M
Verify that a list of persons authorized to handle nuclear substances and/or radiation devices is maintained and accurate on the internal permit.
M
Verify that the internal permits are posted at all locations of licensed activity including field operations.
L
Verify that the current user being inspected has obtained, from the licensee, and internal authorization (permit) and that the instructions on this licence are compiled with by the lab users.
H
Verify that no signs are used where there is no permanent presence of radiation or nuclear substances. Licensee is not expected to remove or cover RWS posted on permanent storage location
when the nuclear substances or radiation devices are temporarily removed.
M
Verify that radiation warning symbols (RWS) are in accordance with the regulation.
L
Verify that prominent radiation warning symbols/signs and appropriate wording are posted at each entrance to an area, room, or enclosure where there is > 100EQ of a nuclear substance or the
dose rate > 25uSv/hr
M
Verify that all use areas were classified in accordance with the licence condition. Verify that the classification is posted with the appropriate classification signage.
H
Posting/Signs
Risk
Personal dosimeters
Description
Requirements
Rating
Dosimetry records
Ascertaining of dose directly
RP 05 2(a)
Dose limits/Body
RP 13 (1)
Dose limits/Organs
RP 14
Extremity dosimetry
LC 2578
Licensed dosimetry
RP 08
Contamination precaution - Protective clothing
LC 2925
Comments
Use of equipment & procedures
GN 12 (1) (e)
Thyroid monitoring/screening/bioassay
LC2046
Room design approval
LC 2922
NRCan Radiation Safety Manual
Annex B – March 2006
B–3
Verify that all rooms in which > 5 ALI of unsealed nuclear substances are used have been approved by the CNSC.
H
Facility
Verify that thyroid screening and monitoring is performed as per permit conditions.
H
Verify that workers are using the safety equipment, devices, and facilities provided to them in a reasonable and responsible manner. Verify by observation that workers comply with the established
procedures.
H
Verify that workers are wearing gloves and protective clothing when handling unsealed nuclear substances in a basic lab and at all times in an intermediate or high level lab.
H
Where dosimetry is required (determined at licence application) verify that service is provided by a licensed dosimetry service.
M
Verify that when handling > 50 MBq of P32, Y90, Sr89, Rh186 or Sm153, workers wearing dosimeters supplied by licenced dosimetry service.
H
Verify that the equivalent dose limits have not been exceeded including non-NEWs as prescribed in the “Table of equivalent dose limits”.
H
Verify that the effective dose limits have not been exceeded for NEWs, non-NEWs (< 1mSv/y), pregnant NEWs (<4 mSv/balance of pregnancy).
H
Verify that the licensee is determining their worker radiation dose through direct monitoring. If applicable (use of dosimeters and/or bioassays).
H
Verify that dosimetry results are kept on file and results communicated to worker.
H
Verify that approved personal dosimeters are worn by workers when applicable. Verify location of storage of TLDs.
H
Personnel
Risk
Cleanliness of room
Description
Fume Hoods
Dose control
Container/device labelled
RP 20 (a)
Rating
Container/device source details
RP 20 (1) (b)
Field Devices I.D.
NSRD 22
Comments
Leak Test/Routine
NSRD 18 (1) (a) (b) (d)
Failed Leak Test
NSRD 18 (3)
Contamination Criteria
LC 2642
Contamination Monitoring
LC 2924
Contamination/survey meter available
LC 2572
NRCan Radiation Safety Manual
Annex B – March 2006
Verify that a portable contamination meter is available, that it functions correctly.
M
B–4
Verify that all classified rooms are checked for removable contamination following work with nuclear substances, or at least weekly. Verify that workers monitor themselves after working with
unsealed nuclear substances, or at least daily. Verify that equipment is monitored before being released for unrestricted use.
H
Verify that wipe test sampling & counting methods can measure the specified activity. Verify through survey that there is no loose contamination in handling and storage areas.
H
Verify leak test measurement results, if there were any leak test results > 200 Bq and if so that they were reported to the CNSC and the device was removed from use.
M
Verify that leak test were performed at the appropriate frequency and in accordance with the submitted procedure.
L
Verify that each device used in the field has securely attached, a durable and legible label indicating the name or job title and the 24-hr telephone number of an emergency contact person.
M
Verify that containers and devices with > 1EQ are labelled with the radionuclide name, quantity and date of source measurement.
H
Verify that all containers and devices with > 1EQ are labelled with a radiation warning symbol (RWS) and appropriate wording.
H
Requirements
LC 2575 (b)
Verify that the dose rates are <2.5uSv/h(± 20%) at all normally occupied areas.
M
Verify that the fume hoods are operable and uncluttered.
H
Verify that the room is clean and uncluttered.
M
Risk
Description
Meter calibrated
NSRD 20
Requirements
Rating
Comments
Change Notified
GN 15 (c)
Location Notification
LC 2300
Contact Details Posted (Storage)
NSRD 23
Control Releases
GN 12 (10) (f)
Disposal (Consolidated)
LC 2160
Decommissioning
LC 2571
Package integrity
PTNS 16 (1)/SS 209, 524540
NRCan Radiation Safety Manual
Annex B – March 2006
B–5
Verify that dangerous goods are transported in the appropriate type of package. Check package for damage or degradation that may compromise the design integrity of the package.
H
Packaging, Shipping and Transportation
Verify by examination of decommissioning records and by the appropriate sampling/monitoring that use locations have been satisfactorily decommissioned.
H
Verify that the approved methods/equipment are being used for disposal. A survey of the regular garbage can be performed to check for nuclear substances inappropriately disposed of.
H
Indicate Waste contractor used for the disposal of radioactive
Verify that stored waste is properly segregated and decayed to an acceptable level prior to release.
H
Verify that the name or job title and 24-hr telephone number of the emergency contact person is posted at or near the storage location.
M
Storage/Waste/Disposal
Verify that any location that will be used for > 90 days or whose use has been discontinued is reported to the RSO within 7 days (must be reported to CNSC).
M
Verify that changes in SRSO, permit holders and users manager have been reported to the RSO within 15 days. (must be reported to CNSC)
M
Is the calibrating agency approved by the CNSC
Name of calibrating agency
Date of last calibration
If a survey meter is required by a licence condition or a regulation, verify that, on the day of use, the survey meter being used had been calibrated within the 12 month period preceding its use by: a)
verifying the calibration certificate or; b) verifying the calibration sticker on the survey.
M
Type of radiation detector being used
Risk
Dose rates on package
Description
Marking on Pkg
PTNS 16 (4)/ SS 437
Rating
Comments
Shipping names and UN number on small
means of containment
TDG 4.11/TDG 4.12
Activity and T.I.
TDG 4.14
Pkg check or damages
PTNS 21 (3)
Shipping document
TDG 3.5, 3.6/ PTNS 15
(2),17 SS 448-459
Shipping doc location
TDG 3.7
Vehicle Placarded
TDG 4.15
Pkg Secured on vehicle
TDG 5.4/ PTNS 15 (5)/SS
462
Shipping document kept 2 years
TDG 3.11
NRCan Radiation Safety Manual
Annex B – March 2006
B–6
Verify that the shipping documents were kept for two years after transport (electronic or paper). ELS shipping documents must be kept for two years after they cease to be used. For exemptions
see 3.11 (4)
L
Verify that the dangerous goods are properly secured in the means of containment (package). Then, verify that the means of containment are properly secured in the vehicle. Category Y II and Y III
shall not be carried in the passenger compartment.
H
Verify that the placard is posted on the large mean of containment (e.g: container, trailer, vehicle, etc.). Required only for YIII packages.
H
Verify that the shipping document is in a pocket mounted on the vehicle door or the document is within reach of driver.
H
Verify that the shipping document contains the following information: consignor’s name and business address, date of preparation, shipping name, class, UN number, quantity (activity) of
dangerous goods in SI units, number of packages for each shipping name, 24 hour phone number, the name and symbol of each radionuclide, form, category (WI, YII, YIII), Transport index for (YII
and YIII), the package design approval certificate number(s) (if applicable) and the special form certificate number(s) (if applicable), special instructions, consignor’s declaration and, if applicable,
the words “Exclusive Use Shipment”. Shipping name, Class and UN number must be noted together, in that order.
H
Check that persons receiving or opening packages have verified if they were damaged, tampered with or the content escaped from them.
H
Verify that the radionuclide name or symbol, activity and transport index (where applicable) are correctly displayed on the primary class labels.
H
Verify that the shipping name and UN number are displayed next to the primary class labels on two opposing sides of a small means of containment (<500 L).
H
Verify that the package is marked appropriately according to regulations including the transport index. Verify that safety marks includes labels, UN numbers and shipping name. Verify that all safety
marks are legible, durable and weather resistant, of proper color, orientation and size (can not be reduced in size). Their location must be on opposite sides (not on top or bottom).
H
Requirements
PTNS 16 (4)/ SS 416
Verify that the external surface dose rate is in compliance with regulations
H
Risk
TDG Training Certificate
Description
TDG 6.1, 6.3, 6.5
Requirements
Rating
Comments
Licence Available
Radiation safety manual
GN 14 (2)
TDG Training Certificate on file
TDG 6.6, 6.7
Act/Regs Available
GN 12 (1) (k)
Transfer Records
NSRD 36 (1) (c)
Training Records
Record Retained
GN 28
NSRD 36 (1) (d)
List of NEWs
RP 24
NEWs informed
RP07
Inspection/Decom/Test Records
NSRD 36 (1) (e)
NRCan Radiation Safety Manual
Annex B – March 2006
B–7
Verify results kept on file for at least 3 years (NSRD 36 (3)). Verify accuracy by sampling of records.
M
If workers have been declared NEW (Nuclear Energy Worker), check for record of signed acknowledgement by each NEW.
M
Verify a list of NEWs is up to date that includes names and job categories.
L
Verify that no prescribed records have been disposed of without proper CNSC notification.
L
Verify that records of training are maintained for all workers.
M
Verify transfer records are maintained since the last inspection and that they include the date of transfer, recipient licence #, name/address of recipient, make/model, serial #, NS (nuclear
substances) and quantity.
H
Verify that all workers have access to a paper or electronic copy of the Act and applicable regulations.
L
Verify that the employer has kept records of training and copies of all issued TDG training certificates.
H
Verify that a copy of the NRCan Radiation Safety Manual containing work policies and procedures is available in every room having a permit.
M
Verify that a copy of the license is available at the location.
L
Records/Documents
Verify that the employer has provided all TDG trained workers with a TDG certificate of training that includes: the name and business address of the employer, the employee’s name, the expiry date
of the certificate (road-36 months; air-24 months), aspects of handling, offering for transport and transporting. Certificate must be signed by the employee and the employer.
H
Risk
Description
Reportable Incidences
GN 29 (all)
Requirements
Rating
Comments
Device Incidences
NSRD 21
Emergency Contact
LC 2559
Radiation Safety
NSRD 17
Leak test/event
NSRD 18 (1) (C)
Mandatory Training
GN 12 (1) (b)
Access Control - storage
LC 2575 (a)
Sources - Devices
GN 12 (1) (g)
Sabotage
GN 12 (1) (h)
NRCan Radiation Safety Manual
Annex B – March 2006
B–8
Windows should be secured with bars, metal grill, expanded metal mesh and/or retrofitted with a security type glazing.
Windows
Verify that the licensee has measures in place to provide warning of any sabotage that may have taken place.
H
Verify that unless in use or under surveillance by an authorized user, nuclear substances and radiation devices are under locked storage restricting access to authorized users. Any compromise of
physical security must be detectable.
H
Verify that when in storage access to nuclear substances or radiation devices is restricted to persons authorized by the licensee. Verify that there is no possible access to that area when it is
unattended.
H
Security
Check that the number of qualified workers match the number submitted in the application.
H
Training and Qualification
Verify that leak tests were performed immediately after any event that might have damaged the source, in accordance with the submitted procedure.
L
Verify that the workers have a copy of the emergency procedures at the work site.
M
Verify that a durable and legible sign indicating the name or job title of a 24-hour emergency contact is posted at/near each radiation device.
M
If a device is involved in an incident, verify that a proper function test or inspection was performed before the device was returned to use.
H
Question staff about unusual or unplanned events that could involve situations listed in GN 29. Were these events immediately reported to the CNSC and a written report sent in 21 days?
H
Emergencies and Unplanned Events
Risk
Doors
Description
Requirements
Rating
Comments
NRCan Radiation Safety Manual
Annex B – March 2006
B–9
If substances and devices are transported to another location, security measures should be in place to ensure the shipment is not susceptible to compromise or theft. Must not be left unattended
for extended periods of time and vehicles must be locked.
Transportation
If the premises uses security guards, it is recommended that the room be checked on a regular basis during guard patrols. The guard should have a list of authorized personnel.
Security Guards
If the premises utilizes card access, installing a card reader for access control to secure storage areas should be considered.
Card access control
If keypad lock is used, combination should be changed whenever an authorized person no longer required access to the area, the combination has been or is suspected of being compromised or at
least once every six months.
Keypad
Door keys must be under strict control with a limited number of keys issued to authorized persons only. A record should be maintained of all keys that are issued, date of issue and to whom.
Keys
Doors should be secured whenever the area is left unattended. They should be either solid core wood or metal clad installed in a robust frame. Doors should be equipped with a deadbolt lock
(security approved hardware) with a restricted keyway
Risk
NRCan Radiation Safety Manual
Annex B – March 2006
B–10
INTENTIONALLY LEFT BLANK
Annex C
Emergency Contact List
Use the Ra diation Safety Em erge ncy C onta ct List tem plate (Appendix 1 in Microsoft W ord format) for
recording and amending site emergency contact information.
Ap pendix
1 - Radiation Safety Em erge ncy C onta ct List tem plate
Ap pendix
2 - Bells Corners Complex
Ap pendix
3 - 601 Booth, Ottawa
Ap pendix
4 - 5 55 Booth , Ottaw a O nta rio
Ap pendix
5 - Fredericton, New Brunswick
Ap pendix
6 - D artm outh, N ova Scotia
Ap pendix
7 - S ault Ste. M arie, O nta rio
Ap pendix
8 - Ste-Foy, Québec
Ap pendix
9 - S udbury, O nta rio
Ap pendix
10 - Victo ria, British Co lum bia
Ap pendix
11 - E dm onto n, Alberta
Ap pendix
12 - D evon, Alberta
NRCan Radiation Safety Manual
Annex C – March 2006
C–1
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NRCan Radiation Safety Manual
Annex C – March 2006
C–2
Annex D
Measurement Units Conversion Table
RAD (rad)
GRAY (Gy)
1 kilorad (krad)
10 gray (Gy)
1 rad (rad)
10 milligray (mGy)
1 millirad (mrad)
10 microgray (:Gy)
1 microrad (:rad)
10 nanogray (nGy)
GRAY (Gy)
RAD (rad)
1 gray (Gy)
100 rad (rad)
1 milligray (mGy)
100 millirad (mrad)
1 microgray (:Gy)
100 microrad (:rad)
1 nanogray (nGy)
100 nanorad (nrad)
REM (rem)
SIEVERT (Sv)
1 kilorem (krem)
10 sievert (Sv)
1 rem (rem)
10 millisievert (mSv)
1 millirem (mrem)
10 microsievert (:Sv)
1 microrem (:rem)
10 nanosievert (nSv)
SIEVERT (Sv)
REM (rem)
1 sievert (Sv)
100 rem (rem)
1 millisievert (mSv)
100 millirem (mrem)
1 microsievert (:Sv)
100 microrem (:rem)
1 nanosievert (nSv)
100 nanorem (nrem)
NRCan Radiation Safety Manual
Annex D – March 2006
D–1
CURIE (Ci)
BECQUEREL (Bq)
1 kilocurie (kCi)
37 terabecquerel (TBq)
1 curie (Ci)
37 gigabecquerel (GBq)
1 millicurie (mCi)
37 megabecquerel (MBq)
1 microcurie (:Ci)
37 kilobecquerel (kBq)
1 nanocurie (nCi)
37 becquerel (Bq)
BECQUEREL (Bq)
CURIE (Ci)
1 terabecquerel (TBq)
27 curie (Ci)
1 gigabecquerel (Gbq)
27 millicurie (mCi)
1 megabecquerel (Mbq)
27 microcurie (:Ci)
1 kilobecquerel (kBq)
27 nanocurie (nCi)
1 becquerel (Bq)
27 picocurie (pCi)
NRCan Radiation Safety Manual
Annex D – March 2006
D–2
Annex E
Laboratory Classification
Level of Radioisotope
Laboratory
Permissible Quantity of Radioactivity
Storage
Stored without manipulation
Basic
Does not exceed 5 times corresponding ALI
Intermediate
Does not exceed 50 times corresponding ALI
High
Does not exceed 500 times corresponding ALO
Containment
Exceeds 500 times corresponding ALI
NRCan Radiation Safety Manual
Annex E – March 2006
E–1
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NRCan Radiation Safety Manual
Annex E – March 2006
E–2
NRCan Radiation Safety Manual
Annex F – March 2006
F–1
Annex F
Periodic Table
NRCan Radiation Safety Manual
Annex F – March 2006
F–2
INTENTIONALLY LEFT BLANK
Annex G
NRCan Internal Permits
Permit Number
Room Number
Permit Holder
Designation
555 Booth, Ottawa, ON
B-NCR-06-B1
B-1
Maureen Leaver
Storage
B-NCR-06-B4
B-4
Maureen Leaver
Basic
B-NCR-06-B5
B-5
Maureen Leaver
Basic
B-NCR-06-B53
B-53
Maureen Leaver
Storage
B-NCR-06-422
422
Regina Karwowska
Basic
B-NCR-06-426
426
Regina Karwowska
Basic
A-NCR-07-725
725
Mike Villeneuve
Basic
A-NCR-07-793C
793C
Bill Davis
Basic
A-NCR-07-798
798
Bill Davis
Basic
A-NCR-07-730/732
730/732
Bruce Taylor
Basic
A-NCR-07-B40A/B
B40/A/B
Gina LeCheminant
Storage
A-NCR-07-B44
B44
Bill Hyatt
Storage
A-NCR-07-Vehicle
Vehicles
Bill Hyatt
Sealed sources only
(vehicle)
A-NCR-07-Field
Field (Canada)
Mike Demuth
Sealed sources only
(field)
601 Booth, Ottawa, ON
Bells Corners Complex, Ottawa, ON
B-NCR-08-129, B9
129, Bldg 9
David Young
Sealed sources only
(SE)1
B-NCR-08-124, B9
124, Bldg 9
David Young
Sealed sources only
(SE)1
B-NCR-08-202, B9
202, Bldg 9
David Young
Sealed sources only
(Kr 85)
B-NCR-08-204, B13
204, Bldg 13
William Ridley
Sealed sources only
2
(ECD) (Ni 63)
NRCan Radiation Safety Manual
Annex G – March 2006
G–1
Permit Number
Room Number
Permit Holder
Designation
D-NCR-08-G1, B6
Lab G-1, Bldg 6
Raymond Burich
Sealed sources only
2
(ECD) (Ni 63)
D-NCR-08-208, B1
208, Bldg 1
Lufei Jia
Sealed sources only
(ECD) (Ni 63)
M317B
Ken Asprey
Sealed sources only
(NG)3
M107
Thierry Varem-Sanders
Sealed sources only
(GC)4
C-NB-01-210
0.210
Tannis Beardmore
LSC Room
C-NB-01-205
0.205
Tannis Beardmore
Basic
C-ON-04-C338/C340
C338/C340
Larry Gringorten
Basic gamma counter
C-ON-04-C416
C416
Rob Flemming
Sealed source only
(Vehicle) (PG)5
C-ON-04-D203
D203
Johanna Curry
Sealed sources only
(SE)1
C-ON-04-D431/D435
D431/D435
Fred Beall
Basic (with ECD in D435)
C-ON-04-E251
E251
Basil Arif
Basic
C-ON-04-E253
E253
Basil Arif
Basic
C-ON-04-E257A
E257A
Basil Arif
Basic
C-ON-04-E349
E349
Larry Gringorten
Basic
C-ON-04-F166
F166
Dean Thompson
Basic
C-ON-04-F297
F297
Basil Arif
LSC Room
C-ON-04-G150
G150
John Studens
Basic
C-ON-04-G270
G270
Basil Arif
Basic
C-ON-04-G272
G272
Basil Arif
Basic
C-ON-04-G274
G274
Basil Arif
Basic
Dartmouth, NS
A-NS-10-M317B
Edmonton, AB
C-AB-09-M107
Fredericton, NB
Sault Ste Marie, ON
NRCan Radiation Safety Manual
Annex G – March 2006
G–2
Permit Number
Room Number
Permit Holder
Designation
C-ON-04-G372
G372
Ross Milne
Basic
C-ON-04-Shed F
Shed F
Kerry MacDonald
Storage (PG)5
C-QUE-02-SS29
SS-29
Don Stewart
LSC Room
C-QUE-02-SS32B
SS-32B
Don Stewart
Basic
C-QUE-02-SS67
SS-67
Don Stewart
Waste Storage
C-QUE-02-54A
2-46 / 2-50 /
2-54A
Michel Cusson
Basic
B-ON-05-132
132
Gary Bonnell
Sealed sources only
(ECD)2
B-ON-05-208
208
Eric Edwardson
Sealed sources only
(ECD)2
C-BC-03-220A
220A
Brett Foord
Sealed sources only
(PG)5
C-BC-03-Vehicle
Vehicles
Brett Foord
Sealed sources only
(PG)5 (vehicles)
Ste-Foy, QC
Sudbury, ON
Victoria, BC
1
SE
Static Eliminate
2
ECD
Electron Capture Detector
3
NG
Non-portable gauge
4
GC
Gas Chromatograph
5
PG
Portable Gauge
NRCan Radiation Safety Manual
Annex G – March 2006
G–3
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NRCan Radiation Safety Manual
Annex G – March 2006
G–4
Annex H
Exemption Quantities
Nuclear
Substance
Quantity (in Bq)
Nuclear
Substance
Quantity (in Bq)
Nuclear
Substance
Quantity (in Bq)
Americium 241
1 x 103
Cobalt 60
1 x 105
Niobium 95
1 x 105
Americium 243
1 x 103
Copper 60
1 x 105
Nitrogen 13
1 x 105
Antimony 124
1 x 104
Copper 64
1 x 105
Oxygen 15
1 x 106
Antimony 125
1 x 105
Copper 67
1 x 105
Phosphorous 32
1 x 104
Arsenic 73
1 x 105
Dysprosium 159
1 x 106
Phosphorous 33
1 x 106
Arsenic 74
1 x 104
Erbium 169
1 x 106
Polonium 210
1 x 104
Arsenic 76
1 x 104
Erbium 171
1 x 104
Potassium 42
1 x 104
Barium 131
1 x 105
Fluorine 18
1 x 104
Promethium 147
1 x 107
Barium 133
1 x 105
Gadolinium 153
1 x 104
Radium 226
1 x 104
Barium 140
1 x 104
Gallium 67
1 x 106
Rubidium 86
1 x 104
Beryllium 7
1 x 106
Gallium 68
1 x 104
Samarium 153
1 x 104
Bismuth 206
1 x 105
Germanium 68
1 x 104
Scandium 46
1 x 105
Bismuth 207
1 x 105
Gold 195
1 x 105
Scandium 47
1 x 105
Bismuth 210
1 x 104
Gold 198
1 x 104
Selenium 75
1 x 105
Bromine 82
1 x 105
Hydrogen 3
1 x 109
Selenium 79
1 x 107
Cadmium 107
1 x 107
Indium 111
1 x 105
Sodium 22
1 x 104
Cadmium 109
1 x 106
Indium 113 m
1 x 105
Sodium 24
1 x 104
Cadmium 113 m
1 x 104
Indium 115
1 x 105
Strontium 85
1 x 105
Cadmium 115
1 x 104
Iodine 123
1 x 107
Strontium 87 m
1 x 105
Cadmium 115 m
1 x 104
Iodine 125
1 x 106
Strontium 89
1 x 104
Calcium 45
1 x 106
Iodine 129
1 x 106
Strontium 90
1 x 104
Calcium 47
1 x 104
Iodine 131
1 x 104
Sulphur 35
1 x 108
Carbon 11
1 x 105
Iridium 192
1 x 104
Technetium 99
1 x 106
Carbon 14
1 x 108
Iron 52
1 x 104
Technetium 99 m
1 x 107
Cerium 139
1 x 106
Iron 55
1 x 106
Thallium 201
1 x 106
Cerium 141
1 x 106
Iron 59
1 x 105
Thallium 204
1 x 104
Cerium 144
1 x 105
Krypton 77
1 x 1010
Thorium 232
1 x 102
Cesium 134
1 x 105
Krypton 85
1 x 1011
Tin 113
1 x 105
NRCan Radiation Safety Manual
Annex H – March 2006
H–1
Nuclear
Substance
Quantity (in Bq)
Nuclear
Substance
Quantity (in Bq)
Nuclear
Substance
Quantity (in Bq)
Cesium 134 m
1 x 107
Krypton 87
1 x 1010
Uranium (natural)
in dispersable
form
1 x 104
Cesium 137
1 x 104
Lead 210
1 x 104
Uranium (natural)
in nondispersable form
1 x 107
Chlorine 36
1 x 104
Magnesium 28
1 x 104
Xenon 123
1 x 1011
Chlorine 38
1 x 104
Manganese 52
1 x 105
Xenon 129 m
1 x 1011
Chromium 49
1 x 105
Manganese 54
1 x 105
Xenon 133
1 x 1011
Chromium 51
1 x 106
Mercury 203
1 x 105
Xenon 135
1 x 1010
Cobalt 56
1 x 105
Molybdenum 99
1 x 104
Yttrium 90
1 x 104
Cobalt 57
1 x 105
Nickel 59
1 x 108
Zinc 65
1 x 106
Cobalt 58
1 x 105
Nickel 63
1 x 107
Zirconium 95
1 x 105
Cobalt 58 m
1 x 107
Nickel 65
1 x 104
NRCan Radiation Safety Manual
Annex H – March 2006
H–2
Annex I
Regulatory Quantities for Typical Radionuclides
Radionuclide
EQ
MBq
ALI
estimate
(ingest)
Mbq/yr
Basic
Level
Mbq
Interm
Level
Mbq
High
Level
Mbq
Wipes
Controlled
Area
Bq/cm2
Wipes
Public
Area
Bq/cm2
Garbage
MBq/kg
Sewer
MBq/yr
Br-82
0.1
37
185
1850
18500
30
3
C-14
100
34
170
1700
17000
300
Co-57
0.1
95
475
4750
47500
Co-58
0.1
27
135
1350
Co-60
0.1
6
30
Cr-51
1
530
F-18
0
Fe-59
30
3.7
10000
300
30
0.37
1000
13500
30
3
0.37
100
300
3000
3
0.3
0.01
0.1
2650
26500
265000
300
30
3.7
100
400
2000
20000
200000
30
3
0.1
0.1
10
50
500
5000
30
3
0.01
1
Ga-67
1
100
500
500
50000
30
3
0.037
100
H-3
1000
1000
5000
5000
500000
300
30
37
1000000
37
I-123
10
95
475
4750
47500
300
30
3.7
1000
3
I-125
1
1
5
50
500
300
30
0.037
100
0.03
I-131
0
1
5
50
500
30
3
0.037
10
0.175
In-111
0.1
70
350
3500
35000
30
3
0.037
100
Na-22
0
6
30
300
3000
3
0.3
0.01
0.1
P-32
0
8
40
400
4000
300
30
0.37
1
P-33
1
80
400
4000
40000
300
30
1
10
Ra-226
0
0.07
0.35
3.5
35
3
0.3
0.01
1
S-35
100
26
130
1300
13000
300
30
0.37
1000
Sb-124
0
8
40
400
4000
3
0.3
0.37
Sr-85
0.1
36
180
1800
18000
30
3
0.37
10
Tc-99m
10
900
4500
45000
450000
300
30
3.7
1000
Tl-201
1
210
1050
10500
105000
300
30
0.037
100
Xe-133
100 GBq
300
30
1
NRCan Radiation Safety Manual
Annex I – March 2006
I–1
Air
kBq/
m3
0.175
3.7
INTENTIONALLY LEFT BLANK
NRCan Radiation Safety Manual
Annex I – March 2006
I–2
Annex J
Information on Elements at NRCan
TRITIUM
Physical Characteristics
Biological Data
Safety Data
Biological Half
Life
12.0 days
Exemption
Quantity
10 x 109 Bq
H
Effective Half
Life
12.0 days
Maximum
Range in Air
5 mm
Atomic
Number
1
I.A.E.A.
Radiotoxicity
Slight
Maximum
Range in
Water
6 x 10-3mm
Half Life
12.26 years
Target Organ
Whole Body
Shielding
Required
None
Mode of
Decay
Beta 100%
ALI
3 GBq
Energy
Maximum/
Average
0.0186MeV/
0.0057 MeV
DAC
185 kBqm-3
Symbol
H
Isotope
3
Decay Product
3
He
Dose Rate
Values are not given for the weak B-emitters such as 3H because such figures are negligible in most
practical circumstances. Dose from these radionuclides is only important when the activity is ingested,
or when in direct contact with the skin.
Contamination Monitoring
Counting swipe tests with a liquid scintillator.
Precaution
C
Disposable gloves and lab coat should be worn when handling 3H.
C
Bioassay must be done if 3H is used as follows:
Operation Compounds
Tritiated Water
Nucleic Acid
Precursors
Tritiated
Open Bench
10 mCi (400MBq)
10 mCi (400MBq)
100 Mci (4GBq )
Fume Hood
19 mCi (700MBq)
54 mCi (2GBq)
540 mCi (20GBq)
NRCan Radiation Safety Manual
Annex J – March 2006
J–1
CARBON 14
Physical Characteristics
Biological Data
Safety Data
Biological Half
Life
12.0 days
Exemption
Quantity
1 x 108 Bq
C
Effective Half
Life
12.0 days
Maximum
Range in Air
22 mm
Atomic
Number
6
I.A.E.A.
Radiotoxicity
Moderate
Maximum
Range in
Water
0.3 mm
Half Life
5730 years
Target Organ
Fatty Tissue
Shielding
Required
1 cm Plexiglas
Mode of
Decay
Beta 100%
ALI
90 MBq
Energy
Maximum/
Average
0.156 MeV/
DAC
148 kBqm-3
Symbol
Isotope
Decay Product
C
14
0.049 MeV
14
N
Dose Rate
Values are not given for the weak B-emitters such as 14C because such figures are negligible in most
practical circumstances. Dose from these radionuclides is only important when the activity is ingested,
or when in direct contact with the skin.
Contamination Monitoring
Counting swipe tests with a liquid scintillator.
Precaution
Disposable gloves and lab coat should be worn when handling 14C.
Use extra caution when handling 14C labelled nucleic acid or their precursors.
NRCan Radiation Safety Manual
Annex J – March 2006
J–2
SULFUR 35
Physical Characteristics
Symbol
S
Biological Data
Safety Data
Biological Half
Life
90.0 days
Exemption
Quantity
1 x 108 Bq
Isotope
35
S
Effective Half
Life
44.3 days
Maximum
Range in Air
26 cm
Atomic
Number
16
I.A.E.A.
Radiotoxicity
Moderate
Maximum
Range in
Water
0.3 mm
Half Life
87.32 days
Target Organ
Testis
Shielding
Required
1 cm Plexiglas
Mode of
Decay
Beta 100%
ALI
200 MBq
Energy
Maximum/
Average
0.167 MeV/
DAC
11 kBqm-3
Decay Product
0.049 MeV
35
Cl
Dose Rate
Values are not given for the weak B-emitters such as 35S because such figures are negligible in most
practical circumstances. Dose from these radionuclides is only important when the activity is ingested,
or when in direct contact with the skin.
Contamination Monitoring
Counting swipe tests with a liquid scintillator.
Precaution
Disposable gloves and lab coat should be worn when handling 35S.
NRCan Radiation Safety Manual
Annex J – March 2006
J–3
PHOSPHORUS 32
Physical Characteristics
Symbol
P
Biological Data
Safety Data
Biological Half
Life
257 days
Exemption
Quantity
1 x 104 Bq
Isotope
32
P
Effective Half
Life
13.5 days
Maximum
Range in Air
618 cm
Atomic
Number
15
I.A.E.A.
Radiotoxicity
Moderate
Maximum
Range in
Water
8 mm
Half Life
14.28 days
Target Organ
Bone
Shielding
Required
1 cm Plexiglas
Mode of
Decay
Beta 100%
ALI
30 MBq
Energy
Maximum/
Average
1.710 MeV/
DAC
2.6 kBqm-3
Decay Product
0.7 MeV
32
S
Dose Rate of a 1.0 Mbq source in 1 ml:
Contact: 210 mSv/h
1.0 M: 2.5 :Sv/h
Contamination Monitoring
Counting swipe tests with a liquid scintillator or Geiger-Müller Tube.
Precaution
Phosphorus 32 is the highest radionuclide commonly encountered in research laboratories and as such
requires special care:
C
Double glove (all direct contact with 32P must be avoided);
C
Safety glasses or Plexiglas shielding are to be used if handling quantities in excess of 1.0 mCi;
C
Finger badges are to be worn if handling quantities in excess of 1.35 mCi;
C
Remote handling devices (tongs, etc.) should be used when handling mCi amounts;
C
Use syringe or pipet shields when manipulating stock solutions in excess of 1.0 mCi; and
C
The use of low-density shielding should be used to minimize the production of gamma radiation
(bremsstrahlung). Some lead shielding may be required in addition to Plexiglas when tens of
millicuries are used.
NRCan Radiation Safety Manual
Annex J – March 2006
J–4
IODINE 125
Physical Characteristics
Symbol
I
Isotope
125
Atomic
Number
Biological Data
Safety Data
Biological
Half Life
138 days
Exemption
Quantity
Effective
Half Life
41.9 days
Maximum
Range in Air
53
I.A.E.A.
Radiotoxici
ty
High
Maximum
Range in
Water
Half Life
60.1 days
Target
Organ
Thyroid
Shielding
Required
Mode of
Decay
Beta 100%
ALI
2 MBq
0.035 MeV 7%/
DAC
296 Bqm-3
Energy
Maximum/
Average
I
1 x 106 Bq
Lead 0.03 mm
0.027 MeV 128%
Decay Product
125
Te
Dose Rate of a 1.0 GBq point source at 1 metre: 41 :Sv/h
Contamination Monitoring : Counting swipe tests with a liquid scintillator or Geiger-Müller Tube.
Precaution
Special consideration:
Volatilization of iodine is the most significant problem with this isotope. Simply opening a vial of sodium
(125I) iodine at high radioactive concentration can cause minute droplets to become airborne. Solutions
containing iodine ions should not be made acidic nor stored frozen, both lead to formation of volatile
elemental iodine. As some iodo-compounds can gradually penetrate certain types of gloves, it is
advisable to change gloves often unless it has been determined that the gloves are impervious to the
compound being used. Note, however, that the quantity of radioiodine in normal RIA kits (usually
<10uCi) is such that these can be handled safely with reasonable care on the open bench.
C
Double glove and lab coat should be worn when handling 125I.
C
Bioassay must be done if 125I is used as follows:
C
Operation
C
Activity 135
C
Open Bench
C
1.35 :Ci(5MBq)*
C
Fume Hood
C
1.35 mCi (50MBq)
C
Glove Box(vented)
C
13.5 mCi (500 MBq)
NRCan Radiation Safety Manual
Annex J – March 2006
J–5
C
If a spill occurs the spill should be treated with a solution of excess sodium thiosulphate.
C
Whenever possible keep radioiodine solutions above pH 8.0.
C
Vials containing radioidine should be opened in the fume hood.
C
Avoid direct contact with unshielded containers of radioiodine.
C
Waste radioiodine should be kept in a shielded waste container in a fume hood or other well
ventilated area. (Volatile iodine can pass through most plastics).
*Processes that involve the generation of significant quantities of volatile iodine must be carried out in a
fume hood.
NRCan Radiation Safety Manual
Annex J – March 2006
J–6
The following is a listing of companies that offer services in various areas of radiation protection. The CNSC neither endorses
any of the consultants listed nor guarantees any of their services . For further information regarding this listing or for any
changes or additions to the list, contact:
Larry Wong, Laboratory Services
Phone: (613)990-2946
E-mail:[email protected]
Services:
1. [RP] General consultant in Health Physics or in Radiation Protection. This may include general advice and RP program setup.
2. [Training] Training course development. This may include the development and delivery of various courses in radiation protection or the
specific development of courses for in-house self study.
3. [Docs] Document preparation and review. This includes the preparation of procedure manuals or in-house documentation for radiation
protection. This may also include the preparation of CNSC radioisotope licence application forms.
4. [Survey] Contamination or radiation surveys. This may include the conducting of radiation surveys or contamination surveys in storage
or
work areas.
5. [LT] [R-116] Leak Testing. This may include the sampling of devices or sources for leakage and/or the measurement of samples for
leakage
against the CNSC criteria limit of 200 Bq of the isotope. If the company has had their procedures and/or measurement instrumentation
verified against the AECB guide #R-116, then this is noted.
6. [Decom] Decontamination or Decommissioning services. This may include the cleanup of areas or equipment contaminated with
radioactive material, or the decommissioning of areas previously containing radioactive material.
7. [Inst Rep] Instrumentation repair and servicing. This includes the repair or possible modification of radiation detection instrumentation.
8. [Inst Cal] [R-117] This includes the calibration of various types of radiation detection instrumentation. If the company has had their
procedures and calibration setup verified against the AECB guide #R-117, then this has been noted.
9. [WM] Waste Management. This may include consultation servicesor management of radioactive waste material or facilities.
10.[Trans] Transportation and Packaging. This may include the preparation and/or transportation of radioactive material or devices.
11.[Emerg] Emergency planning. This may include the preparation of procedures, advice on instrumentation, or guidance during an
emergency situation.
12.[Emerg 24h] Emergency Response within 24 hours. This includes the response to an emergency situation within 24 hours from the time
of
notification. This may include consultation services or actual clean-up team response.
13.[Dose] Dosimetry. This includes companies that will either provide or consult in the application of dosimetry services.
14.[Bio] Bioassay. This includes companies that will either provide or consult in the application of bioassay services.
15.[A/L/T] Analytical, Labelling or Tracer preparation. This includes companies that will provide radioanalytical analysis, isotopic labelling or
tracer preparation.
16.[Equipt] Equipment design or assessment. This includes companies that will provide specialized design of nuclear instrumentation or
the
assessment of instrumentation for special purposes.
17.[Env] Environmental Assessment. This includes companies that will provide or consult in the requirements for environmental
assessments.
18.[Rn] Radon Gas Assessment. This includes companies that will provide or consult in the analysis or radon gas or radon daughter
products.
Note: Additional information and company listing regarding guides R-116 (Leak Testing) and R-117 (Gamma Survey Meter
Tuesday, April 12, 2005
Consultant Database
Page 1 of 32
COMPANY
25 Bannisdale Way
1125944 Ontario Inc.
Carlisle
ON
L0R 1H2
[email protected]
PHONE
Peter Ernst
(905)689-9983
FAX
(905)689-9983
Yes
Rad. Prot.
No
LT
Yes
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Training
No
Decom
Yes
Transport.
No
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
Emerg 24hr
No
Equip
No
R117
No
No
COMPANY
Box 33026 - Glamorgan P.O.
ABG Atomic Instruments
Calgary
AB
T3E 7E3
PHONE
Don Cooper
No
Rad. Prot.
No
Training
No
Docs
Survey
Yes
(403)249-5376
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Instr. Cal
No
Emerg 24hr
Equip
No
R117
Yes
No
Yes
COMPANY
PO Box 48088 - 1881 Young St.
Ace Radiation Protection Advisor
Toronto
ON
M4S 1Y6
[email protected]
PHONE
Ashley Chinapen
(416)818-4368
FAX
4164801421
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
No
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
No
Yes
Anal/Lab/Trace
Yes
R116
Equip
Yes
R117
COMPANY
P.O. Box 429
Acsion Industries
Pinawa
SK
Chris Saunders
R0E 1L0
[email protected]
PHONE
Scott Wooster
2047532255
FAX
2047538466
No
Rad. Prot.
Yes
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
Yes
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
Tuesday, April 12, 2005
Consultant Database
Page 2 of 32
COMPANY
AECL - Chalk River Labs
Chalk River
ON
Mr. J. Bond
Yes
No
Yes
No
Rad. Prot.
Training
Docs
Survey
K0J 1J0
PHONE
Kazysztof Szornel
No
Yes
No
Yes
(613)584-3311
FAX
(613)584-4108
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
No
R116
Yes
R117
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Instr. Cal
Yes
Emerg 24hr
No
Equip
COMPANY
1411 - 25th Avenue NE; Bay 3
AGAT Laboratories
Calgary
AB
T2E 7L6
PHONE
Bruce Underwood
No
Rad. Prot.
No
Training
No
No
(403)299-2080
FAX
(403)299-2099
LT
No
Waste Manag.
No
Dosimetry
Yes
Environ
No
Decom
No
Transport.
No
BioAssay
Yes
Radon
Docs
No
Instr. Repair
No
Emerg planning
Survey
No
Instr. Cal
No
Emerg 24hr
Yes
Yes
No
Anal/Lab/Trace
No
R116
Equip
No
R117
COMPANY
9528-27 Avenue
ALARA Consultants Inc.
Edmonton
AB
Allan Seitz
T6N 1B2
[email protected]
PHONE
George Zomber
(780)944-2557
FAX
(780)944-2558
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
Yes
R117
COMPANY
4200B - 10 Street N.E.
ARCT Chemtech
Calgary
AB
T2E 6K3
[email protected]
PHONE
Dr. Norman W. Chiu
No
Rad. Prot.
Yes
LT
No
Waste Manag.
No
Training
Yes
Decom
No
No
Docs
No
Instr. Repair
No
Survey
No
Instr. Cal
Yes
Tuesday, April 12, 2005
Yes
(403)250-1715
FAX
(403)250-8265
No
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
No
R117
Emerg 24hr
Consultant Database
No
Equip
Page 3 of 32
COMPANY
PO Box 88 - 1881 Young St.
Ashley Chinapen Enterprises Inc.
Toronto
ON
M4S 1Y6
[email protected]
PHONE
Ashley Chinapen
(416)818-4368
FAX
4164801421
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
No
R117
COMPANY
500 Beaverbrook, Box 1268
Atlantic Nuclear Services Ltd.
Fredricton
NB
C. Keith Scott
E3B 5C8
PHONE
Mamdooh Abdelbaky
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Transport.
Yes
Docs
Instr. Repair
Yes
Emerg planning
Yes
Survey
Emerg 24hr
No
Yes
Instr. Cal
No
(506)458-9552
FAX
(506)451-0525
Yes
Dosimetry
Yes
Environ
No
BioAssay
No
Radon
Yes
Anal/Lab/Trace
No
R116
Yes
Equip
No
R117
COMPANY
R.P.O Box 27038
Atomic Solutions Canada
Red Deer
AB
T4N 6X8
[email protected]
PHONE
Scott Hahn
(403)309-2014
FAX
(403)309-0845
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
No
R117
COMPANY
#303 - 18 Lower Village Gate
AWL Segel
Toronto
ON
M5P 3M1
[email protected]
PHONE
A.W.L. Segel
(416)322-8363
FAX
(416)322-8362
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
No
Tuesday, April 12, 2005
Consultant Database
Page 4 of 32
COMPANY
7845 Edmonds Street
B.C. Biomedical Labs
Burnaby
BC
V3N 1B9
PHONE
Anne Jang
Rad. Prot.
No
LT
No
Training
No
Decom
No
No
Docs
No
Instr. Repair
No
Survey
No
Instr. Cal
Yes
FAX
(604)525-7247
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
Yes
Waste Manag.
(604)525-1441
COMPANY
BC Ministry of Health-Rad Prot Services
Burnaby
BC
Brian Phillips
Yes
210 - 4940 Canada Way
Rad. Prot.
V5G 4K6
PHONE
David Morley
Yes
LT
No
Waste Manag.
(604)660-6633
FAX
(604)660-6663
Yes
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
Yes
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Emerg 24hr
No
Equip
No
R117
Yes
Survey
Yes
Instr. Cal
Yes
COMPANY
3700 Willingdon Ave.
BCIT
Burnaby
BC
V5G 3H2
PHONE
Randy Singer
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Survey
6044516993
FAX
6044321816
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
Yes
COMPANY
14 Abacus Road
Beak Consultants Limited
Brampton
ON
Karen Clarke-Whistle
Yes
Rad. Prot.
No
LT
Yes
Yes
Decom
Yes
Docs
Yes
Instr. Repair
Yes
Survey
Yes
Instr. Cal
Tuesday, April 12, 2005
PHONE
Donald Lush
Training
No
L6T 5B7
No
Yes
No
(905)794-2325
FAX
(905)794-2338
Waste Manag.
Yes
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Equip
No
R117
Emerg 24hr
Consultant Database
No
Page 5 of 32
COMPANY
6790 Kitimat Road; Unit #4
Becquerel Laboratories Inc.
Mississauga
ON
Steven Simpson
L5N 5L9
[email protected]
PHONE
Don Burgess
(905)826-3080
FAX
(905)826-4151
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
Yes
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Survey
No
Instr. Cal
No
Emerg 24hr
Yes
No
Anal/Lab/Trace
No
R116
Equip
No
R117
COMPANY
P.O. Box 100; Highway 17
Bubble Technology Industries Inc
Chalk River
ON
Dr. R.C. Miller
K0J 1J0
PHONE
Dr. H. Ing
Rad. Prot.
Yes
LT
No
Waste Manag.
No
Training
Yes
Decom
No
No
Docs
Instr. Repair
Instr. Cal
Yes
Yes
Survey
No
Yes
(613)589-2456
FAX
(613)589-2763
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
Yes
Radon
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
No
Emerg 24hr
Equip
Yes
R117
Yes
COMPANY
1403-29 St. N.W.
Calgary Regional Health Authority
Calgary
AB
Percy Kung
T2N 2T9
[email protected]
PHONE
Dr L. Hahn
4036701952
FAX
4036701687
Yes
Rad. Prot.
Yes
LT
No
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
No
Transport.
Yes
BioAssay
No
Radon
Yes
Docs
Yes
Survey
No
Yes
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Instr. Cal
Yes
Emerg 24hr
No
Equip
Yes
R117
COMPANY
1120 Finch Ave. W Suite 607
Canadian Institute for Rad Safet
Toronto
ON
Dr. Reza Moridi
M3J 3H7
[email protected]
PHONE
Tina de Geus
Yes
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Training
No
Decom
No
Yes
Docs
No
Instr. Repair
Yes
Survey
Instr. Cal
Tuesday, April 12, 2005
Yes
4166509090
FAX
4166509920
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
Yes
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
Consultant Database
Page 6 of 32
COMPANY
6470 Van Deemeter Crescent
Canberra Packard Canada
Mississauga
ON
L5T 1S1
PHONE
Bob Snell
(905)795-2599
FAX
(905)795-2598
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
7450-18 Street
Canspec Group Inc
Edmonton
AB
Mr. Tom Levy
T6P 1N8
[email protected]
PHONE
Gary Stuart
(780)440-2131
FAX
7804902426
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
COMPANY
3350 Fairview St. 3-165
CERTA INC.
Burlington
ON
John Hostt
L7N 3L5
PHONE
Scott Morrow
9053363822
FAX
9053363844
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
No
BioAssay
Yes
Radon
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
Yes
Emerg 24hr
No
Equip
No
R117
COMPANY
622 Trillium Dr.
Certified Testing Systems Inc.
Kitchener
ON
Mr G.W. Porter
N2R 1E6
PHONE
Andy Wyszomierski
(519)748-2880
FAX
(519)748-2783
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Tuesday, April 12, 2005
Yes
Consultant Database
Page 7 of 32
COMPANY
4 Gold Crescent
Chaloner Leak Test Service
Russell
ON
K4R 1B9
PHONE
Paul Chaloner
No
Rad. Prot.
No
Training
No
No
[email protected]
(613)445-3260
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
1 Yonge Street, Suite 1801
Contex Environment Inc.
Toronto
ON
Jean-Pierre Gauvin
M5E 1W7
PHONE
Alexandra Roy
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Yes
Docs
Yes
Survey
No
Yes
[email protected]
8009657522
FAX
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Transport.
Yes
BioAssay
Yes
Radon
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
Yes
R117
No
COMPANY
820 - 2155 Guy
Contex Environnement Inc.
Montréal
QC
Jean-Pierre Gauvin
H3H 2R9
PHONE
Plamen Stefanov
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Yes
Docs
Yes
Survey
No
Yes
[email protected]
(514)932-9552
FAX
(514)932-9419
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Transport.
Yes
BioAssay
Yes
Radon
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
No
R117
No
COMPANY
1055 Sarnia Road, Unit B2
CSP Medical
London
ON
Steve Gensens
N6H 5J9
[email protected]
PHONE
David Spriet
800-265-3460
FAX
519-473-2585
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Tuesday, April 12, 2005
Consultant Database
Page 8 of 32
COMPANY
936 Berkley Drive, NW
D.R. Novitsky Enterprises
Calgary
AB
T3K 1A2
PHONE
Dennis Novitsky
Yes
Rad. Prot.
Yes
Training
No
Decom
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
Yes
LT
FAX
4037309434
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
No
Equip
No
R117
Yes
No
Waste Manag.
(403)730-8286
COMPANY
70 Abbeyhill Dr.
DBS LOGIC
Kanata
ON
K2L 1H1
[email protected]
PHONE
Howie Montone
(613)836-5121
FAX
6138365121
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
920 ch. Cook
Detec
Alymer
QC
J9H5C9
PHONE
Jacques Dubeau
Rad. Prot.
No
LT
No
Waste Manag.
No
Training
No
Decom
No
No
Docs
No
Instr. Repair
No
Survey
No
Instr. Cal
Yes
8198850500
FAX
8196859218
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
Equip
No
R117
Yes
COMPANY
7832 Tranmere Drive
Dupont Pharma
Mississauga
ON
L5S 1L9
PHONE
Paul Denharttog
No
Rad. Prot.
No
Training
No
No
9056789132
FAX
9056789132
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 9 of 32
COMPANY
#2 2616-16 Street N.E.
Eagle Engineering Corp.
Calgary
AB
T2E 7J8
[email protected]
PHONE
Kim Biddle
403 291-4633
FAX
403 291-1291
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
No
COMPANY
Edmonton Radiopharmaceutical Centre
Edmonton
11560 University Ave.
AB
T6G 1Z2
PHONE
Mr. J.R. Scott
No
Rad. Prot.
No
Training
No
No
(403)432-8970
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
323 Queen Street
Egmond Associates Ltd
Acton
ON
L7T 1R1
PHONE
John Van Egmond
No
Rad. Prot.
No
Training
No
Docs
Survey
Yes
[email protected]
No
LT
Yes
8002674797
FAX
4162832459
Waste Manag.
No
Dosimetry
Yes
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
COMPANY
2236 - 80 Avenue
Enviropac Inc.
Edmonton
AB
R.M. Masnyk
T6P 1N2
[email protected]
PHONE
Marilyn A. Melnyk
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Yes
Docs
Yes
Instr. Repair
Yes
Survey
Yes
Instr. Cal
Tuesday, April 12, 2005
(780)440-1942
FAX
(780)440-1952
No
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Yes
Emerg 24hr
Yes
Equip
Yes
R117
Consultant Database
Page 10 of 32
COMPANY
10158-103 Street
Enviro-Test Laboratories
Edmonton
AB
Marian Kornicki
No
Rad. Prot.
No
Training
No
No
T5J 0X6
[email protected]
PHONE
Larry Serbin
7804135265
FAX
7804244602
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
160 - 7070 Mississauga Rd.
Goodfellow Consultants Inc.
Mississauga
ON
Archie Kerr
Yes
Rad. Prot.
Yes
Training
Yes
Yes
L5N 7G2
PHONE
Dave Gilbert
(905)858-4424
FAX
(905)858-4426
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
COMPANY
775 Brookfield
Health Canada, RPB
Ottawa
ON
K1A 1C1
PHONE
Robert Bradley
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Training
No
Decom
No
No
Docs
No
Instr. Repair
No
Survey
No
Instr. Cal
6139546697
FAX
6139578698
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
COMPANY
235 Yorkland Blvd, Suite 300
Industrial Dynamics Co. Ltd.
North York
ON
M2J 4Y8
PHONE
Graham Gore
No
Rad. Prot.
No
Training
No
No
(416)495-4339
FAX
(416)491-4383
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 11 of 32
COMPANY
P.O. Box 821
Inspectaweld
Beresford
NB
E0B 1H0
PHONE
M. Lebel
No
Yes
Rad. Prot.
Training
Yes
No
LT
No
Waste Manag.
(506)542-1215
FAX
(506)542-2884
Yes
Dosimetry
No
Environ
Decom
Yes
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Emerg 24hr
No
Equip
No
R117
No
Docs
Yes
Instr. Repair
No
Survey
Yes
Instr. Cal
No
COMPANY
450 Midwest Road
INSPECTECH
Scarborough
ON
Alan Richardson
M1P 3A9
PHONE
Jeff Gavey
4167571179
FAX
4167578096
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
COMPANY
International Radiochemical Centre Inc.
Edmonton
8444 - 45 Street
AB
Dr. John W. Tse
T6B 2N6
[email protected]
PHONE
Mr. Lyle Wahl
4034690653
FAX
4034384839
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
No
R117
COMPANY
188 des Grottes
Jacques P. Morel Inc.
Boischatel
QC
G0A 1H0
PHONE
Mr. Jacques Morel
Yes
Rad. Prot.
Yes
Training
No
Yes
[email protected]
(418)822-2972
FAX
(418)822-2630
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 12 of 32
COMPANY
Unit #9 - 52 Steeles Ave. Ea
Kodiac Quality Control Ltd.
Milton
ON
E.F. Haugen
L9T 4X1
PHONE
Molly Leach
(905)875-2030
FAX
(905)875-2997
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
225, rue Dessureault
LABCAN (1989) LT E
Cap-de-la-Madeleine
QC
Isabelle Lemieux
No
Rad. Prot.
No
Training
Yes
No
G8T 2L7
[email protected]
PHONE
Michel Rodier
8193788612
FAX
8193789449
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
225, rue Dessureault
LABCAN (1989) LTÉE
Cap-de-la-Madeleine
QC
Isabelle Lemieux
No
Rad. Prot.
No
Training
Yes
No
G8T 2L7
[email protected]
PHONE
Michel Rodier
8193788612
FAX
8193789449
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
2 Science Road
Landauer Inc.
Glenwood
Il
60425
landauerinc.com
PHONE
Yes
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Training
No
Decom
No
No
Docs
No
Instr. Repair
No
Survey
No
Instr. Cal
Tuesday, April 12, 2005
8003238830
FAX
7087557016
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
Yes
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
Consultant Database
Page 13 of 32
COMPANY
31 Dundas St. E.; Highway #5
M&L Testing Equipment (1995) Inc
Dundas
ON
Mike Mizener
No
Yes
Rad. Prot.
Training
L9H 7H8
PHONE
Max Pizzingrilli
Yes
No
(905)689-7327
FAX
(905)689-3978
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
7832 Tranmere Drive
Mallinckrodt Medical Inc.
Mississauga
ON
Paul Denhartog
No
Rad. Prot.
No
Training
No
No
L5S 1L9
[email protected]
PHONE
Garry Morrissey
(905)678-9114
FAX
(905)678-9132
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
Manitoba Cancer Treatment & Research
Winnipeg
AB
Dr. H.M. Johnson
Yes
100 Olivia St.
Rad. Prot.
R3E 0V9
PHONE
Mr. J. Sandeman
Yes
LT
No
[email protected]
(204)787-2213
FAX
(204)775-1684
Waste Manag.
No
Dosimetry
No
Environ
No
Radon
Training
No
Decom
Yes
Transport.
No
BioAssay
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Yes
Survey
Instr. Cal
Yes
Emerg 24hr
No
Equip
Yes
R117
No
Yes
COMPANY
3534 University Street
McGill University; Environmental
Montréal
QC
H3A 2A7
[email protected]
PHONE
Joseph Vincelli
5143981538
FAX
(514)398-8047
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Transport.
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
No
Equip
No
R117
Tuesday, April 12, 2005
Consultant Database
No
Dosimetry
Yes
Environ
Yes
BioAssay
Yes
Radon
Page 14 of 32
COMPANY
447 March Road
MDS Nordion Inc.
Kanata
ON
Tham Tran
No
Rad. Prot.
No
Training
No
Docs
No
Survey
K2K 1X8
[email protected]
PHONE
Lloyd Hillier
(613)592-2790
FAX
(613)592-2006
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
Yes
COMPANY
1000 de Serigny
Measurex Inc.
Longueuil
QC
J4K 5B1
PHONE
Raymond Roy
No
Rad. Prot.
No
Training
No
No
(514)651-2410
FAX
(514)651-0371
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
Medical Industrial Systems Consulting
Safety Harbor
2424 Dana Drive
FL
346 95
PHONE
Mr. Ravaschieri
No
Rad. Prot.
No
Training
No
No
(813)791-4480
FAX
(813)726-7190
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
3860 - 5199 Sherbrooke Est
Min de L'Env. du Quebec
Montreal
QC
H1T 3X9
PHONE
Jean-Marc Legare
(514)873-1978
FAX
Yes
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Yes
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
No
Instr. Cal
Emerg 24hr
No
Equip
No
R117
Tuesday, April 12, 2005
Yes
No
Consultant Database
Page 15 of 32
COMPANY
190 Wilkinson Road, Unit #2
Monserco Limited
Brampton
ON
Mr Roger Bojanowski
L6T 4W3
[email protected]
PHONE
Mr. Richard Chayer
(905)450-3507
FAX
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Transport.
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
No
Equip
(905)450-8523
No
Dosimetry
No
Environ
Yes
BioAssay
No
Radon
Yes
R116
No
R117
COMPANY
111 Anderson
NDS Products Inc.
Pasadena
TX
Noel Smith
No
Rad. Prot.
No
Training
No
No
775 06
PHONE
1-800-413-4750
(713)475-2986
FAX
(713)477-6741
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
45 Caroline Avenue
NOREMTECH INC.
Ottawa
ON
K1Y 0S8
[email protected]
PHONE
Norm Barton
(613)798-8353
FAX
(613)798-8011
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
No
Dosimetry
No
Environ
Yes
Training
Yes
Decom
Yes
Transport.
No
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R116
No
R117
COMPANY
9420 Cote de Liesse
Novamann Quebec Inc.
Lachine
QC
H8T 1A1
PHONE
John Fenwick
No
Rad. Prot.
No
Training
No
No
(514)636-6218
FAX
(514)631-9814
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 16 of 32
COMPANY
251 Mt. Victoria Pl. S.E.
Nuclear Services Canada Ltd.
Calgary
AB
Paul Kennedy
T2Z 1P4
PHONE
1-800-291-5789
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Yes
Docs
Instr. Repair
Yes
Survey
No
Yes
[email protected]
(403)257-0633
FAX
(403)257-0632
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Transport.
No
BioAssay
Yes
Radon
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Emerg 24hr
Yes
Equip
Yes
R117
No
Instr. Cal
No
COMPANY
P.O. Box 1054
Ontario Assoc. of Med Radiation
Brantford
ON
N3T 5S7
[email protected]
PHONE
R. Hesler
Yes
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Training
No
Decom
No
Yes
Docs
No
Instr. Repair
Survey
No
Instr. Cal
No
(519)753-6037
FAX
(519)753-6408
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
COMPANY
7 Innovation Drive, Suite 121
Ontario Isotopes Inc.
Flamborough
ON
Dr. Adam Dodd
Yes
No
L9H 7H9
PHONE
Reinhard Koplin
Rad. Prot.
Yes
LT
Training
Yes
Decom
[email protected]
No
Yes
9056895990
FAX
9056890855
Waste Manag.
Yes
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Yes
Anal/Lab/Trace
No
R116
Equip
No
R117
Yes
Docs
No
Instr. Repair
No
Emerg planning
Yes
Survey
No
Instr. Cal
No
Emerg 24hr
No
COMPANY
81 Resources Rd.
Ontario Ministry of Labour
Weston
ON
J. Tai-Pow
No
Rad. Prot.
No
Training
No
No
M9P 3T1
PHONE
Ken Gilmer
(416)235-5916
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 17 of 32
COMPANY
6495 Northam Drive
Outokumpu Mintec
Mississauga
ON
L4V 1J2
PHONE
Mr. D. Brand
No
Rad. Prot.
No
Training
No
Docs
No
Survey
Yes
No
Yes
No
(905)671-3304
FAX
(905)671-8413
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
2136 Heidi Avenue
OVERWATCH CONSULTING
Burlington
ON
L7M 3X2
[email protected]
PHONE
Don A. Rickard
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Yes
Docs
Yes
Survey
No
Yes
9053191555
FAX
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Transport.
Yes
BioAssay
No
Radon
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Instr. Cal
Yes
Emerg 24hr
Yes
Equip
No
R117
No
COMPANY
Proactive Health and Safety Services
Toronto
546 Sundown Cres.
ON
l1v6a5
[email protected]
PHONE
Ray Ilson
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Yes
Docs
Yes
Instr. Repair
Yes
Yes
Survey
Yes
Instr. Cal
No
(416) 978-2374
FAX
No
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Emerg 24hr
Yes
Equip
No
R117
COMPANY
1160 Dairy Ashford, Suite 444
ProTechnics Environmental
Houston
TX
Larry Stephenson
77079
[email protected]
PHONE
W. Hampton
2814963734
FAX
2816799876
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
No
BioAssay
No
Radon
Yes
Docs
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Yes
Survey
Emerg 24hr
Yes
Equip
Yes
R117
Tuesday, April 12, 2005
No
Yes
Instr. Cal
No
Consultant Database
Page 18 of 32
COMPANY
164 St. Jean-Baptiste
Quality NDE Ltd.
Mercier
QC
Robert Demers
J6R 2C2
PHONE
Alain Poupart
No
Rad. Prot.
No
Training
No
Docs
Yes
Instr. Repair
No
Survey
Yes
Instr. Cal
Yes
No
LT
(450)691-9090
FAX
(450)691-6101
Waste Manag.
No
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
No
Emerg 24hr
No
Equip
Yes
R117
No
Decom
[email protected]
Yes
COMPANY
P.O. Box 33030
Rad. Env. Mgmt. Systems Inc.
Waterloo
ON
H.D. Sharma
N2T2M9
PHONE
Christine Sharma
No
Rad. Prot.
Yes
LT
Yes
Waste Manag.
No
Training
Yes
Decom
Yes
(519)885-2520
FAX
(519)746-0435
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
Yes
Radon
Yes
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
Radiation Health and Safety Consulting
Toronto
64 Donlea Drive
ON
M4G 2M4
PHONE
Dr. Anthony Muc
(416)425-3110
FAX
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
COMPANY
757 McKay Road, Unit #1
Radiation Management Services Inc
Pickering
ON
Mike White
Yes
Rad. Prot.
Yes
Training
Yes
Docs
Yes
Survey
Tuesday, April 12, 2005
L1W 3C8
PHONE
Heather Geroir
Yes
LT
No
FAX
(905)428-8451
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
BioAssay
No
Radon
Decom
Yes
Transport.
Yes
Instr. Repair
Yes
Emerg planning
Yes
Instr. Cal
Yes
Emerg 24hr
No
(905)428-8060
Consultant Database
No
Yes
Anal/Lab/Trace
Yes
R116
Equip
Yes
R117
Page 19 of 32
COMPANY
Radiation Prot. Bureau, Health Canada
Ottawa
775 Brookfield Rd.
ON
Dr. Gary Kramer
Yes
Rad. Prot.
Yes
Training
Yes
Docs
Yes
Survey
K1A 1C1
PHONE
Maria Limson Zamara
(613)954-6668
FAX
(613)957-1089
LT
No
Waste Manag.
Yes
Dosimetry
No
Environ
No
Decom
No
Transport.
Yes
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
Yes
COMPANY
1120 Finch Ave. W Suite 607
Radiation Safety Institute of Canada
Toronto
ON
Dr. Reza Moridi
M3J 3H7
[email protected]
PHONE
Tina de Geus
Yes
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Training
No
Decom
No
Yes
Docs
No
Instr. Repair
Yes
Survey
Instr. Cal
Yes
4166509090
FAX
4166509920
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
Yes
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
COMPANY
508 Hager Avenue
Radiation Safety Services
Burlington
ON
L7S 1P3
PHONE
Steve Staniek
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Instr. Repair
No
Yes
Docs
Survey
No
Yes
FAX
Waste Manag.
No
Dosimetry
No
Environ
Yes
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Emerg 24hr
No
Equip
Yes
R117
No
Instr. Cal
(905)681-1999
No
COMPANY
2081 Leonard de Vinci
Radioprotection Inc.
Sainte-Julie
QC
Michel Deschamps
J3E 1Z2
PHONE
Stephane Trudeau
(450)649-5213
FAX
(450)649-5213
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
No
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
No
Equip
Yes
R117
Tuesday, April 12, 2005
Consultant Database
Page 20 of 32
COMPANY
4855 Boul. Lévesque Est
Radioprotection J.M. LÉGARÉ
Laval
QC
H7C 1N2
PHONE
Jean-Marc Légaré, Ph.D.
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
No
Yes
LT
FAX
4506619065
Waste Manag.
Yes
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
Yes
Equip
No
R117
Yes
Decom
4506610844
No
COMPANY
4855 Boul. L‚vesque Est
Radioprotection J.M. L GAR
Laval
QC
H7C 1N2
PHONE
Jean-Marc L‚gar‚, Ph.D.
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
No
Yes
LT
FAX
4506619065
Waste Manag.
Yes
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Yes
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
Yes
Equip
No
R117
Yes
Decom
4506610844
No
COMPANY
211 Hinks St
Radsafe Canada Ltd
Pembroke
ON
K8A 4N7
[email protected]
PHONE
Gerard Peplinskie
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
No
Yes
6137353168
FAX
6133500349
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
No
Equip
No
R117
COMPANY
211 Hincks St.
RadSafe Canada Ltd.
Pembroke
ON
K8A 4N7
PHONE
Gerard Peplinskie
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
Tuesday, April 12, 2005
[email protected]
No
Yes
6137353168
FAX
6137350349
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
No
Equip
No
R117
Consultant Database
Page 21 of 32
COMPANY
921 College Hill Road
Research and Productivity Council
Fredricton
NB
E3B 6Z9
PHONE
Peter Silk
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Training
No
Decom
No
No
Docs
No
Instr. Repair
Survey
No
Instr. Cal
Yes
(506)452-8994
FAX
(506)452-0594
No
Dosimetry
No
Environ
Transport.
Yes
BioAssay
Yes
Radon
No
Emerg planning
Yes
Anal/Lab/Trace
No
R116
No
Emerg 24hr
Equip
No
R117
No
COMPANY
389 Davis Road
R-Metrics Ltd.
Oakville
ON
Mr. S. Cathcart
No
Rad. Prot.
No
Training
No
Docs
No
Survey
L6J 2X2
PHONE
Kasey Fedorwin
(905)338-1857
FAX
(905)845-9551
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
No
COMPANY
35 Foothills Drive
Roger Eaton and Associates
Nepean
ON
Dr. Roger Eaton
Rad. Prot.
No
LT
Yes
Training
No
Decom
Docs
No
Instr. Repair
Survey
No
Instr. Cal
Yes
PHONE
Beatrice Dunning-Eaton
Yes
No
K2H 6K6
(613)828-2193
FAX
(613)828-2193
Waste Manag.
No
Dosimetry
Yes
Environ
Transport.
No
BioAssay
Yes
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
No
Equip
No
R117
Yes
No
COMPANY
32 Bermondsey Road
Ronan Engineering Ltd.
Toronto
ON
M4B 1Z5
PHONE
Mr. M. Murji
No
Rad. Prot.
Yes
(416)752-0310
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Radon
Training
No
Decom
No
Transport.
No
BioAssay
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Tuesday, April 12, 2005
(416)752-8072
Consultant Database
Yes
R116
No
R117
Page 22 of 32
COMPANY
4909-75 Avenue N.W.
Russell Technologies Corporation
Edmonton
AB
T6B 2S3
[email protected]
PHONE
Derek Brent
(780)469-4461
FAX
(780)462-9378
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
COMPANY
15 Dineen Drive, GC128
SAIC Canada (NB)
Fredricton
nb
Edward Waller
E3B 5A3
[email protected]
PHONE
Espin Hussein
5064473422
FAX
5064473380
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
310 - 1657 Barrington St.
SAIC Canada (NS)
Halifax
NS
Jim Bruce
B3J 2A1
[email protected]
PHONE
Lisa Moulton
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Transport.
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
Yes
Survey
No
Instr. Cal
Yes
Emerg 24hr
(902)422-4255
FAX
(902)422-4293
Yes
Dosimetry
Yes
Environ
No
BioAssay
Yes
Radon
Yes
No
Anal/Lab/Trace
No
R116
Equip
No
R117
COMPANY
60 Queen St. , Suite 702
SAIC Canada (Ottawa)
Ottawa
ON
David Cole
Yes
No
K1P 5Y7
[email protected]
PHONE
Terry Jamieson
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Training
Yes
Decom
Yes
FAX
6135633399
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
No
Radon
No
Anal/Lab/Trace
No
R116
Equip
No
R117
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
Yes
Survey
No
Instr. Cal
Yes
Emerg 24hr
Tuesday, April 12, 2005
6135637242
Consultant Database
Yes
Page 23 of 32
COMPANY
455 St. Antoine Ouest
SAIC Canada (QC)
Montréal
QC
H2Z 1J1
PHONE
Michel Doré
Yes
Rad. Prot.
Yes
LT
No
Waste Manag.
Yes
Training
Yes
Decom
No
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
(514)874-1644
FAX
(514)874-0092
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
Equip
No
R117
Yes
COMPANY
4 Lansing Square , Suite 119
SAIC Canada (Toronto)
North York
ON
David Walters
M2J 5A2
[email protected]
PHONE
Stuart Harvey
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
4164986071
FAX
4164988443
Yes
Dosimetry
Yes
Environ
Transport.
No
BioAssay
Yes
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Emerg 24hr
Equip
No
R117
Yes
COMPANY
2100 Unit Ave. Saint John
Saint John Regional Hospital
St. John
NB
Narayan Kulkarni
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Survey
E2L 4L2
PHONE
Debbie Boudreau
LT
No
Waste Manag.
No
Decom
No
No
Instr. Repair
No
Yes
Yes
Instr. Cal
Yes
(506)648-6884
FAX
(506)648-6880
Yes
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Equip
Yes
R117
Emerg 24hr
Yes
COMPANY
113 Black Hawkway
Sandu Sonuc
Toronto
ON
M2R 3L7
[email protected]
PHONE
Sandu Sonuc
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Training
Yes
Decom
Yes
Yes
Docs
Yes
Instr. Repair
Yes
Survey
Yes
Instr. Cal
No
Tuesday, April 12, 2005
No
416 661-6109
FAX
No
Dosimetry
Yes
Environ
Transport.
Yes
BioAssay
Yes
Radon
Emerg planning
Yes
Anal/Lab/Trace
No
R116
Emerg 24hr
Yes
Equip
No
R117
Consultant Database
Page 24 of 32
COMPANY
225 Traders Blvd. E., Unit 3
Sartell Instruments Ltd.
Mississauga
ON
Mr. P. Sartell
L4Z 3E4
[email protected]
PHONE
Anna Chiappetta
(905)890-1090
FAX
(905)890-1744
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
No
Yes
COMPANY
1870 Albert St. Sask Place
Saskatchewan Labour, OHSD
Regina
SK
S4P 3V7
PHONE
Vaidy Bala
No
Rad. Prot.
No
Training
No
Docs
No
Survey
(306)787-4006
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R117
Yes
Yes
COMPANY
15 Innovation Blvd.
Saskatchewan Research Council
Saskatoon
SK
S7N 2X8
PHONE
Jeff Zimmer
No
Yes
No
Yes
(306)933-5400
FAX
(306)933-7446
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
222 Snidercroft Road
Scintrex
Concord
ON
L4K 1B5
PHONE
Larry McNelles
No
Rad. Prot.
No
Training
No
No
9056692280
FAX
9056695132
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Tuesday, April 12, 2005
Yes
Consultant Database
Yes
R116
No
R117
Page 25 of 32
COMPANY
P.O. Box 360
Scitech Services
Gloucester
ON
K1C 1S8
PHONE
Ron or Rita Gray
(613)824-0301
FAX
(613)824-0301
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
Equip
No
R117
Yes
No
Yes
No
Emerg 24hr
Yes
COMPANY
121 Granton Drive, Unit 12
SENES Consultants Limited
Richmond Hill
ON
Dr. Leo M. Lowe
L4B 3N4
[email protected]
PHONE
Morley W. Davis
(905)764-9380
FAX
(905)764-9386
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
3910 de la Peltrie
Soltec Consultation
Montréal
QC
Mme Martha Ortiz
Yes
No
No
Yes
LT
[email protected]
PHONE
Émile Haddad
Rad. Prot.
Training
H3S 1V3
No
Waste Manag.
(514)733-9412
FAX
No
Dosimetry
Yes
Environ
Yes
BioAssay
No
Radon
Decom
Yes
Transport.
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Emerg 24hr
No
Equip
No
R117
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
No
COMPANY
544 McDonnel St. P.O. Box 687
Spectrum Consulting Inc.
Peterborough
ON
J.B. Graham
Yes
Rad. Prot.
Yes
Training
Yes
Docs
No
Survey
Tuesday, April 12, 2005
K9J 6Z8
PHONE
J.D. Beath
Yes
No
Yes
No
(705)743-7520
FAX
(705)743-9878
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Instr. Cal
No
Emerg 24hr
Consultant Database
Yes
Equip
Yes
R116
No
R117
Page 26 of 32
COMPANY
8045 Coronet Rd. N.W.
Spencer Manufacturing Ltd.
Edmonton
AB
Jerry Spencer
T6E 4N7
PHONE
Chris Spencer
No
Rad. Prot.
No
Training
No
Docs
Yes
Instr. Repair
No
Survey
Yes
Instr. Cal
Yes
No
LT
FAX
(780)469-4642
Waste Manag.
No
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
Yes
R116
No
Emerg 24hr
No
Equip
Yes
R117
No
Decom
(780)469-4619
Yes
COMPANY
1590 Burlington Street East
Stern Laboratories Inc.
Hamilton
ON
L8H 3L3
PHONE
Ted Ayers
No
Rad. Prot.
No
Training
No
No
(905)548-5306
FAX
(905)545-5399
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
COMPANY
26 Rayborn Crescent
Stuart Hunt and Associates
St. Albert
AB
Stuart Hunt
T8N 5C1
1-800-661-4591
PHONE
Sean Hunt
(780)458-0291
FAX
(780)459-0746
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
Equip
Yes
R117
No
COMPANY
#500, 130 Dundas St. East
Stuart Hunt and Associates
Mississauga
ON
Stuart Hunt
L5A 3V8
1-800-661-4591
PHONE
Sean Hunt
(905)212-1320
FAX
(905)212-1318
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
Yes
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
Yes
BioAssay
Yes
Radon
Yes
Docs
Yes
Instr. Repair
Yes
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Yes
Survey
Yes
Instr. Cal
Yes
Emerg 24hr
Equip
Yes
R117
Tuesday, April 12, 2005
Consultant Database
No
Page 27 of 32
COMPANY
1228 Meadowbrook Drive
SUBRI NDT Consulting & Training
Airdrie
AB
T4A 1W5
[email protected]
PHONE
Brian Rosebrugh
(403)948-4988
FAX
(403)948-0555
Yes
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Yes
Training
No
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
Emerg 24hr
No
Equip
No
R117
No
Yes
No
COMPANY
986 Farrell Street
TDT Assiciates
Ottawa
ON
K2B 6C7
[email protected]
PHONE
Tham Tran
Yes
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Training
No
Decom
No
Transport.
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
Yes
No
Emerg planning
Emerg 24hr
(613)828-0882
FAX
No
Dosimetry
Yes
Environ
Yes
BioAssay
No
Radon
Anal/Lab/Trace
No
R116
Equip
No
R117
No
Yes
COMPANY
1050 Baxter Rd.
Thomson & Nielson Electronics Ltd
Ottawa
ON
Michael Spender
K2C 3P1
PHONE
Ian Thomson
(613)596-4563
FAX
(613)596-5243
No
Rad. Prot.
No
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
No
BioAssay
Yes
Radon
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Survey
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
Yes
COMPANY
14 Gormley Industrial Ave
TN Technologies Canada
Gormley
ON
Doug Young
L0H 1G0
[email protected]
PHONE
Fred Bergeron
(905)888-8808
FAX
(905)888-8828
Rad. Prot.
Yes
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Yes
Training
Yes
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Docs
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
Survey
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
No
Tuesday, April 12, 2005
Consultant Database
Yes
R116
No
R117
Page 28 of 32
COMPANY
13-7125 Pacific Circle
Troxler Electronics (Canada) Ltd.
Mississauga
ON
Don Wilgosh
No
Rad. Prot.
No
Training
No
Docs
No
Survey
L5T 2A5
PHONE
Dawn Chaykowsky
9055650633
FAX
9055647092
LT
No
Waste Manag.
No
Dosimetry
No
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Yes
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Yes
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
No
Yes
R116
No
R117
COMPANY
R.R. #2
Twin Oaks Consulting
Omemee
ON
K0L 2W0
PHONE
Vera Carter
(705)799-5000
FAX
(705)799-0541
Yes
Rad. Prot.
Yes
LT
Yes
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
Yes
Transport.
No
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
Yes
Emerg planning
No
Anal/Lab/Trace
Yes
Survey
No
Instr. Cal
Yes
Emerg 24hr
No
Equip
Yes
R116
No
R117
COMPANY
8440 - 112 Street
University of Alberta Hospital
Edmonton
AB
T6G 2B7
PHONE
Keith Murland
(403)492-6380
FAX
(403)492-6176
No
Rad. Prot.
No
LT
No
Waste Manag.
Yes
Dosimetry
No
Environ
No
Training
No
Decom
No
Transport.
Yes
BioAssay
No
Radon
Yes
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
2211 Wesbrook Mall
University of British Columbia
Vancouver
BC
V6T 2B5
PHONE
Craig Smith
No
Rad. Prot.
[email protected]
Yes
(604)822-7052
FAX
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Radon
Training
No
Decom
No
Transport.
No
BioAssay
No
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
Survey
No
Instr. Cal
Emerg 24hr
No
Equip
Yes
Tuesday, April 12, 2005
(604)822-8065
Yes
Consultant Database
Yes
R116
No
R117
Page 29 of 32
COMPANY
191 Frank Kennedy Centre
University of Manitoba
Winnipeg
MB
R3T 2N2
PHONE
Danny Buksak
No
Yes
No
Yes
Rad. Prot.
[email protected]
Yes
2044746315
FAX
2044747629
LT
Yes
Waste Manag.
No
Dosimetry
No
Environ
Yes
Transport.
No
BioAssay
No
Radon
Training
No
Decom
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
R116
No
R117
COMPANY
110 - 1280 Main Street West
University of McMaster
Hamilton
ON
Dr. J.W. Harvey
No
Rad. Prot.
No
Training
No
Docs
No
Survey
L8S 4K1
PHONE
Steve Staniek
(905)525-9140
FAX
(905)528-4339
LT
No
Waste Manag.
Yes
Dosimetry
No
Environ
No
Decom
No
Transport.
Yes
BioAssay
No
Radon
No
Instr. Repair
No
Emerg planning
Yes
Anal/Lab/Trace
Yes
R116
Instr. Cal
No
Emerg 24hr
Equip
Yes
R117
Yes
Yes
No
COMPANY
44 Campus Drive
University of Saskatchewan
Saskatoon
SK
S7N 5B3
PHONE
Ms. D. Frattinger
No
Rad. Prot.
No
Training
No
No
3069668493
FAX
3069668394
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
Yes
Yes
R116
No
R117
COMPANY
1163 Rue Benoit
Uni-vert Tech Inc.
Chambly
QC
[email protected]
PHONE
Mr. Willy Rheln
Yes
Rad. Prot.
Yes
LT
Yes
Training
Yes
Decom
Yes
Docs
Yes
Yes
Survey
Yes
Tuesday, April 12, 2005
5145732858
FAX
5149379440
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Transport.
No
BioAssay
Yes
Radon
Instr. Repair
Yes
Emerg planning
Instr. Cal
Yes
Emerg 24hr
No
Consultant Database
Yes
No
Anal/Lab/Trace
No
R116
Equip
No
R117
Page 30 of 32
COMPANY
159 Shearer Cr.
U-Train Consulting Ltd.
Kanata
ON
K2L 3W3
PHONE
Cameron Haigh
Yes
Rad. Prot.
No
LT
Yes
Training
No
Decom
Yes
Docs
No
Instr. Repair
Survey
No
Instr. Cal
No
[email protected]
6135996517
FAX
(613)599-9845
Waste Manag.
No
Dosimetry
No
Environ
Yes
Transport.
No
BioAssay
No
Radon
Yes
Emerg planning
No
Anal/Lab/Trace
No
R116
Emerg 24hr
No
Equip
No
R117
No
No
COMPANY
1401 Arlington Boulevard
Victor Clulow
Sudbury
ON
P3E 6H8
PHONE
Victor Clulow
No
Rad. Prot.
No
Training
Yes
No
No
Yes
LT
Yes
7056743802
FAX
(705)675-4859
Waste Manag.
No
Dosimetry
Yes
Environ
Decom
No
Transport.
No
BioAssay
No
Radon
Docs
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Survey
No
Instr. Cal
No
Emerg 24hr
No
Equip
No
R117
COMPANY
W&W Rad. & Env. Consultant Svcs Inc.
Toronto
115 Banstock Drive
ON
M2K 2H7
[email protected]
PHONE
Murray Walsh
4167308490
FAX
4167309224
Yes
Rad. Prot.
Yes
LT
No
Waste Manag.
No
Dosimetry
Yes
Environ
Yes
Training
Yes
Decom
No
Transport.
No
BioAssay
Yes
Radon
Yes
Docs
No
Instr. Repair
Emerg planning
No
Anal/Lab/Trace
No
R116
Yes
Survey
No
Instr. Cal
Equip
No
R117
Yes
No
Emerg 24hr
Yes
COMPANY
1870 Albert Street
Wayne Tiefenbach
Regina
SK
S4P 3V7
PHONE
Wayne Tiefenbach
Yes
Rad. Prot.
Yes
Training
Docs
No
Yes
Survey
Tuesday, April 12, 2005
(306)787-4538
FAX
(306)787-2208
LT
No
Waste Manag.
No
Dosimetry
No
Environ
No
Decom
No
Transport.
No
BioAssay
Yes
Radon
No
Instr. Repair
No
Emerg planning
No
Anal/Lab/Trace
No
R116
Emerg 24hr
No
Equip
No
R117
Yes
Yes
Instr. Cal
Yes
Consultant Database
Page 31 of 32
COMPANY
714-32 Avenue S.W.
Wood & Associates (Canada) Ltd
Calgary
AB
T2S 0S6
PHONE
Kelvin Wood
Yes
Rad. Prot.
No
LT
Yes
Training
No
Decom
Yes
Docs
No
Instr. Repair
Yes
Survey
No
Instr. Cal
Tuesday, April 12, 2005
[email protected]
(403)243-6560
FAX
(403)243-6560
Waste Manag.
No
Dosimetry
No
Environ
Transport.
No
BioAssay
No
Radon
No
Emerg planning
No
Anal/Lab/Trace
No
R116
No
Emerg 24hr
No
Equip
No
R117
No
Yes
Consultant Database
Page 32 of 32
17-Mar-05
Telephone: (613) 990-2946
[email protected]
R116/7 Database
Le matériel et les procédures des organismes suivants répondent aux critères de la Commission
canadienne de sûreté nucléaire pour les épreuves d'étanchéité de sources scellées de
rayonnement et l'étalonnage des gammamètres. S'il est vraisemblable que les résultats des services
d'épreuves d'étanchéité ou d'étalonnage offerts par ces organismes puissent satisfaire aux
exigences de la CCSN, la CCSN n'assume aucune responsabilité pour un aspect quelconque du
travail exécuté ou des services offerts par l'un de ces organismes. Des noms peuvent être ajoutés
à la liste ou retirés à tout moment par la CCSN sur la base des dispositions des textes de
réglementation R-116 (Normes d'épreuves d'étanchéité des sources scellées de rayonnement) et
R-117 (Normes d'étalonnage des gammamètres).
Pour de plus amples mise à jour ou renseignements au sujet de cette liste, veuillez communiquer
avec le bureau local de la CCSN ou avec :
Agente d'administration
Ottawa
Téléphone : (613) 943-1568 ou 1-888-229-2672
Télécopieur : (613) 995-5086
Telephone: (613) 943-1568
Fax: (613) 995-5086
For further updates or information regarding this list, please contact your local CNSC office or
Directorate of Nuclear Substance
Regulation
Administrative Officer Laboratory Services
OR
Mr. Larry Wong (for Technical inquiries)
CNSC / CCSN
Listing of Leak Test Measurement and Instrument Calibration Agencies
Liste d'organismes offrant des services d'épreuve d'étanchéité et d'étalonnage de gammamètres
The following are names of organizations whose equipment and procedures have been found to
meet the Canadian Nuclear Safety Commission's criteria with respect to the leak testing of sealed
radiation sources and the calibration of radiation survey instruments. While the results of the leak
testing or calibration services performed by these organizations are likely to satisfy CNSC
requirements, the CNSC assumes no liability for any aspect of the work performed or services
provided, by any organization on this list. Names may be added to, or deleted from, the list at
any time as determined by the CNSC, and guided by regulatory documents R-116 (Requirements
for Leak Testing Selected Sealed Radiation Sources) and R-117 (Requirements for Gamma
Radiation Survey Meter Calibration).
Page 1 of 6
9556 - 27 Avenue
4200B- 10 Street NE
650 Ackerman Road, PO. box
82186
1730 Aimco Boulevard
210-4940 Canada Way
101 Corporation Dr. Hopewell
Park
HWY. 17
675 McDermot Ave
4 Gold Crescent
2155 rue Guy, bureau 820
7832 Tranmere Drive
11560 University Ave.
11 Innovation Blvd
2236-80 Avenue
1403-29 St. N.W.
551-D Pylon Drive
ALARA Consultants Inc.
ARCT Chemtech
Automation and Control
Technology Inc.
Barringer
BC Radiation Protection
Services (MOH)
Berthold Systems, Inc.
Bubble Technology Industries
CancerCare Manitoba
Chaloner Leak Test Service
Contex Hygiene Industrielle et
Environnementale
Dupont Pharma
Edmonton Radiopharmaceutical
Centre
Environment Canada National
Hydrology Institute
Enviropac Inc
Foothills Hospital
Humboldt Scientific Inc.
17-Mar-05
Whiteshell Laboratories
ADDRESS:
AECL Research , Pinawa
COMPANY:
Raleigh
Calgary
Edmonton
Saskatoon
Edmonton
TN.USA
AB
AB
SK
AB
ON
QC
ON
MB
ON
PA. USA
BC
ON
OH. USA
AB
AB
MB
PROV:
27606
T2N 2T9
T6P 1N2
S7N 3H5
T6G 1Z2
L5S 1L9
H3H 2R9
K4R 1B9
R3E 0V9
K0J 1J0
15001
V5G 4K6
L4W 1V1
43202-21
T2E 6K3
T6N 1B2
R0E 1L0
PC:
R116/7 Database
Mississauga
Montréal
Russel
Winnipeg
Chalk River
Aliquippa
Burnaby
Mississauga
Columbus
Calgary
Edmonton
Pinawa
CITY:
Mahir Al-Nadaf
Percy Kung
Bob Masnyk
Eric Marles
Mr. J.R. Scott
Paul Denhartog
Plamen Stefanov
Paul Chaloner
Dr. Johnson
John Jevcak
Mary Keller
Dave Morley
Dr. Lucy
Danylewych-May
Charles Bayles
Dr. Norman Chiu
Allan Seitz
Stan Pleskach
CONTACT1:
(919)832-6509
(403) 670-1952
(403) 440-1942
(306)975-5763
(403)432-8970
(905) 678-9132
(514) 932-9552
(613) 445-3260
(204)787-2166
(613) 589-2456
(412) 378-1900
(604) 660-6633
(905) 238-8837
(614) 261-2581
(403) 250-1715
(780) 944-2557
(204) 753-2311
PHONE:
Page 2 of 6
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
Yes
Yes
No
No
No
No
No
Yes
Yes
No
No
No
No
No
Yes
Yes
Service Provider
R116
R117
235 Yorkland Blvd., Suite 300
650 Ackerman Road
#3, 1216 - 34th Avenue, NE
188 des Grottes
84 Gloucester Cres.
225 rue Dessureault
1650 Cedar Ave
447 March Road; P.O. 13500
1000 de Sérigny
2424 Dana Drive
113 Anderson
190 Wilkinson Road, Unit #2
5314 North Irwindale Avenue
111 Anderson
P.O. Box 2000
45 Caroline Avenue
Industrial Dynamics Co. Ltd.
IRMS Inc.
Isotopes Canada Ltd.
Jacques P. Morel
KD RADPRO SERVICES
LABCAN (1989) LTEE
McGill University Health Centre
(MGH, RVH, JGH)
MDS Nordion Inc.
Measurex Inc. (Uses R.D.C.
USA for measurement)
Medical Industrial Systems
Consultants
Microtec Services Inc.
Monserco Limited
NDC Systems
NDS Products Inc.
New Brunswick Power
Corporation
NOREMTECH INC.
17-Mar-05
4900 boul Bécancour
ADDRESS:
Hydro-Québec, Gentilly
COMPANY:
Ottawa
ON
NB
TX. USA
CA. USA
ON
TX. USA
FL. USA
QC
ON
QC
QC
NB
QC
AB
OH. USA
ON
QC
PROV:
K1Y 0S8
E3B 4X1
77506
91706
L6T 4W3
77506
34695
J4K 5B1
K2K 1X8
H3G 1A4
G8T 2L7
E3B 6E6
G0A 1H0
T2E 6L9
43202
M2J 4Y8
G0X 1G0
PC:
R116/7 Database
Fredericton
Pasadena
Irwindale
Brampton
Pasadena
Safety Harbor
Longueuil
Kanata
Montréal
Cap-de-laMadeleine
Fredericton
Boischatel
Calgary
Columbus
North York
Gentilly,
Bécancour
CITY:
Norm Barton
Joe McCully
Noel Smith
Holly McKnight
Maureen McQueen
Quintin Stokely
Mr. Ravaschieri
Raymond Roy
Llyod R. Hillier
Dr. Erwin
Podgorsak
M. Rodier
Keith Davies
Jacques Morel
H. Bruce Freeman
Dennis Clum
Graham Gore
Michel R.
Rhéaume
CONTACT1:
(613) 798-8353
(506) 458-3161
(713)475-2986
(818) 960-3300
(905)450-3507
(713)475-2274
(813)791-4480
(514) 651-2410
(613)592-2790
(514) 934-8052
(819) 378-8612
(506) 459-1352
(418)822-2972
(403) 250-3968
(614) 261-5500
(416)495-4339
(819) 298-2943
PHONE:
Page 3 of 6
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
No
No
No
No
No
No
No
Yes
No
No
No
No
No
No
No
No
Service Provider
R116
R117
251 Mt. Victoria Pl. S.E.
4241 Allendorf Drive
1549 Victoria Street East
81A Resources Rd.
1549 Victoria Street East
1160 Dairy Ashford, Suite 444
164 St-Jean-Baptiste
see- (University of Dalhousie,
RS)
162 Wolfe Road, P.O Box 3414
757 McKay Road, Unit #1
102-110 Research Drive
2081 Léonard de Vinci
510 County Highway V
389 Davis Road
32 Bermondsey Road
P.O. Box 17000, Stn. Forces
Nuclear Services Canada Ltd.
Ohmart Vega
Ontario Hydro, Health Physics
Ontario Ministry of Labour
Ontarion Power Generation ,
Whitby Pickering Darlington
ProTechnics International
Quality NDE
Queen Elizabeth II (Health
Sciences Centre)
Radiation Detection Company
Radiation Management
Services Inc.
Radiation Safety Institute of
Canada
Radioprotection Inc.
RAM Services Inc.
R-Metrics Ltd.
Ronan Engineering Ltd.
Royal Military College of Canada
17-Mar-05
9420 Cote de Liesse
ADDRESS:
Novamann (Quebec) Inc.
COMPANY:
Kingston
Toronto
Oakville
ON
ON
ON
WI. USA
QC
SK
ON
CA. USA
QC
TX. USA
ON
ON
ON
OH. USA
AB
QC
PROV:
K7K 7B4
M4B 1Z5
L6J 2X2
54241
J3E 1Z2
S7N 3R3
L1W 3C8
94088-34
J6R 2C2
77079
L1N 9E3
M9P 3T1
L1N 9E3
45209-99
T2Z 1P4
H8T 1A1
PC:
R116/7 Database
Two Rivers
Ste-Julie
Saskatoon
Pickering
Sunnyvale
Mercier
Houston
Whitby
Weston
Whitby
Cincinnati
Calgary
Lachine
CITY:
R. D. Weir
Mr. Mohamed Murji
Mr. S. Cathcart
Jerry Wiza
Michel Deschamps
Brian Bjorndal
Mike White
Grant Ceffalo
Mrs. Pauline Jones
Alain Poupart
Larry J.
Stephenson
Spencer Fisher
J. Tai-Pow
Ms. J.L. Noronha
George Brown
Paul Kennedy
Dr. J.D. Fenwick
CONTACT1:
(613) 541-6612
(416)752-0310
(905)338-1857
(920) 686-3889
(450) 649-5213
(306) 975-0566
(905)428-8060
(408) 735-8700
(902) 473-2677
(514) 691-9090
(713) 496-3734
(905) 430-2215
(416)235-5916
(905) 430-2215
(513) 272-0131
(403)257-0633
(514) 636-6218
PHONE:
Page 4 of 6
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
No
Yes
No
Yes
Yes
Yes
No
No
Yes
Yes
No
No
No
Yes
Yes
No
Service Provider
R116
R117
222 Snidercroft Road
544 McDonnel St.P.O. Box 687
8045 Coronet Rd. N.W.
26 Rayborn Crescent
1818 East Main Street
14 Gormley Industrial Avenue
unit #7-27 West Beaver Creek
Road
R.R. 2
Suite 50-2075 Wesbrook Mall
1278 Tower Road
SCINTREX
Spectrum Engineering Corp. Ltd.
Spencer Manufacturing Ltd.
Stuart Hunt and Associates
Suntrac Services Inc
TN Technologies-Canada
Troxler Electronics (Canada)
Ltd. (Measured by Troxler US)
Twin Oaks Consulting
University of British Columbia
University of Dalhousie,
Radiation Safety
Halifax
Vancouver
Omemee
17-Mar-05
MB
ON
NS
BC
ON
ON
ON
TX. USA
AB
AB
ON
ON
GA. USA
SK
SK
NB
IL.USA
PROV:
Dr. George Mawko
Craig Smith
Vera Carter
Don Wilgosh
Fred Bergeron
Ricky Crouch
Stuart/Sean Hunt
Jerry Spencer
J.B. Graham
Larry McNelles
Jack Ramsey
Jeff Zimmer
Vaidy Bala
Debbie Boudreau
Eli Port
CONTACT1:
R3T 2N2
Danny Buksak
N1G 2W1 Geoffrey Byford
B3H 2Y9
V6T 1Z1
K0L 2W0
L4B 1M8
L0H 1G0
77573
T8N 5B8
T6E 4N7
K9J 6Z8
L4K 1B5
30071
S7N 2X8
S4P 3V7
E2L 4L2
60053-27
PC:
R116/7 Database
Richmond Hill
Gormley
League City
St. Albert
Edmonton
Peterborough
Concord
Norcross
Saskatoon
Winnipeg
2915 Courtyards Drive, Suite B
Scan Technologies Inc.
191 Frank Kennedy Centre
15 Innovation Blvd.
Saskatchewan Research
Council
Regina
University of Manitoba
1870 Albert St. Sask Place
Saskatchewan Labour, OHSD
Saint John
Guelph
P.O. Box 2100
Saint John Regional Hospital
Morton Grove
CITY:
University of Guelph (Lepton
Laboratory)
6312 West Oakton Street
ADDRESS:
RSSI
COMPANY:
(204)474-6633
(519) 824-4120
(902) 473-2677
(604)822-2029
(705) 799-5000
(905)709-3665
(905) 888-8808
(281) 338-2133
(403)458-0291
(403)469-4619
(705)743-7520
(905) 669-2280
(770) 447-8008
(306) 933-5204
(306) 787-4006
(506)648-6852
(847) 965-1999
PHONE:
Page 5 of 6
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
No
No
No
No
No
No
No
Yes
Yes
No
No
No
No
Yes
Yes
Yes
Service Provider
R116
R117
44 Campus Drive
P.O. Box 1700
111 Granton Drive
35 Helmcken Road
University of Saskatchewan
University of Victoria
Valmet Automation (Canada)
Ltd. (Sampling only)
Victoria General Hospital (Nuc.
Med)
17-Mar-05
1280 Main Street West
ADDRESS:
University of McMaster - Health
Physics
COMPANY:
Victoria
BC
ON
BC
SK
ON
PROV:
V8R 1J8
L4B 1L5
V8W 2Y2
S7N 5B3
L8S 4K1
PC:
R116/7 Database
Richmond Hill
Victoria
Saskatoon
Hamilton
CITY:
John Thomson
Cecilia Lugtu
Mr. Renato
Danesin
Ms. D. Frattinger
Dr. J. W. Harvey
CONTACT1:
(250) 727-4208
(905) 707-3000
(250) 721-8879
(306) 966-8493
(905)525-9140
PHONE:
Page 6 of 6
Yes
Yes
Yes
Yes
Yes
No
No
No
No
Yes
Service Provider
R116
R117