| Req ID | Category | Intent | Legal Status | Name | Subdomain(s) | Context | Conditions | Confidence |
|---|---|---|---|---|---|---|---|---|
| #Q001 | monitoring | health | recommended | Site-specific dose assessment | drinking water, wastewater, other | Where doses to workers or members of the public may exceed this value, a site-specific assessment should be carried out. | Doses potentially exceeding 0.3 mSv/a | high |
| #Q002 | monitoring | health | recommended | Radiation survey | drinking water, wastewater, other | Estimate doses to members of the public, and workers by conducting a radiation survey of the workplace/worksite. The survey should include evaluations of both gamma dose-rates and airborne radioactivity as required. | When initial review indicates NORM Investigation Threshold may be exceeded | high |
| #Q003 | monitoring | operational | recommended | Periodic review of work site and materials | drinking water, wastewater, other | Where the work site, feed and waste materials are subject to change, the work site, feed and waste material should be reviewed periodically to verify that conditions have not changed. | Under NORM Management Classification where site/materials are subject to change | high |
| #Q004 | prohibition | health | mandatory | Public access restriction | other | Public access would need to be restricted. | NORM Management Classification | high |
| #Q005 | administrative | health | recommended | Dose Management Program requirements | drinking water, wastewater, other | The program should include: Worker notification of radiation sources. Consideration of work procedures and protective clothing to limit worker dose from NORM. Application of engineering controls where appropriate (see 4.3.3). Training to control and reduce worker dose. Introduction of a worker radiation dose estimate program... Reporting of worker doses to the National Dose Registry (NDR) through the dosimetry service provider | Dose Management Classification | high |
| #Q006 | administrative | health | recommended | Radiation Protection Management Program implementation | drinking water, wastewater, other | Introduce a formal radiation protection program as described in Appendix F... Place those workers estimated to exceed 5 mSv/a in a personal radiation dosimetry program meeting the requirements of S-106 revision 1, Technical and Quality Assurance Requirements for Dosimetry Services. Provide protective equipment, clothing and work procedures to reduce worker dose and the spread of contamination. | Estimated annual effective dose to an occupationally exposed worker is greater than 5 mSv/a | high |
| #Q007 | administrative | operational | mandatory | Periodic review of NORM programs | drinking water, wastewater, other | Whenever a NORM Management, Dose Management or Radiation Protection Management Program has been implemented, a periodic review is needed. | Implementation of NORM Management, Dose Management, or Radiation Protection Management Programs | high |
| #Q008 | operational | health | recommended | Application of ALARA principle | other | From the time a NORM accumulation is expected to the implementation of a NORM Program, the ALARA principle should be the prime decision making criterion used to ensure minimal public and worker radiation dose. | high | |
| #Q009 | monitoring | health | recommended | Workplace radon assessment | other | As radon concentration can vary considerably it is recommended that all workplaces be assessed for potential elevated levels. | high | |
| #Q010 | operational | health | recommended | Radon NORM Management controls | other | Where the estimated annual average concentration of radon gas in an occupied area is more than 200 Bq/m3 but less than 800 Bq/m3, the NORM Classification is NORM Management. Steps to reduce this exposure should be taken and include: introduction of public and incidentally exposed worker access controls; changes in work practices; and reducing the radon concentration levels to below 200 Bq/m3. | Radon gas concentration between 200 and 800 Bq/m3 | high |
| #Q011 | operational | health | recommended | Engineering control of airborne radioactive material | other | Where annual intakes exceed 1/20 of the ALI, engineering control of the source of airborne radioactive material is the preferred management method. Controls include capture ventilation at the source to prevent escape into the air, and room ventilation rate increase. | Annual intakes exceed 1/20 of the ALI | high |
| #Q012 | administrative | health | recommended | Respiratory protection program and access limitations | other | If intakes exceed 25% of the ALI (equivalent to 5 mSv/a) after engineering controls are applied, a respiratory protection program and/or limiting worker access should be considered as part of the radiation protection program. | Intakes exceed 25% of the ALI after engineering controls | high |
| #Q013 | operational | health | mandatory | Respiratory protection standards compliance | other | Respiratory protection must follow the standards requirements specified for other hazardous dusts under the local jurisdiction. | When utilizing respiratory protection | high |
| #Q014 | administrative | health | mandatory | Consideration of non-radioactive hazards | other | In determining an acceptable material management option, other hazardous properties such as chemical toxicity must be considered. | high | |
| #Q015 | monitoring | operational | mandatory | NORM material shipment assessment | other | Prior to shipment, the NORM material must be assessed to determine the activity concentration. | Before transporting NORM shipments | high |
| #Q016 | administrative | operational | recommended | NORM shipments subject to Canadian Guidelines | other | A transport manifest is completed and contains the descriptor "Naturally Occurring Radioactive Material - NORM". The shipment is securely packaged in a manner that effectively prevents release or redistribution of any NORM contamination during transport. The shipment has taken into account any other potential hazardous properties of the materials. | Activity concentration is less than 10 times Table 6.1 value but greater than UDRLs | high |
| #Q017 | prohibition | reporting | recommended | Prohibition of radioactive placards for specific NORM shipments | other | no radioactive placards or labels should be affixed to the transport vehicle or to the exterior surfaces of the packaging. | For NORM shipments subject to Canadian Guidelines | high |
| #Q018 | administrative | operational | mandatory | Compliance with federal transport regulations | other | Shipments of NORM falling under federal jurisdiction are required to comply with the PTNSR, established by the CNSC. | When shipments fall under federal jurisdiction | high |
| #Q019 | operational | health | mandatory | Removal of loose surface contamination | other | Loose surface contamination must be completely removed or all accessible surfaces stripped to ensure complete removal. | Prior to release of surface contaminated objects | high |
| #Q020 | operational | health | recommended | Radiation Protection Program implementation | other | Employers that implement a radiation protection program should, as part of that program, keep the exposure to radon progeny and the effective dose received by and committed to persons as low as reasonably achievable through the implementation of: 1. management control over work practices; 2. personnel qualification and training; 3. control of occupational and public exposure to radiation; and 4. planning for unusual situations. | Implementation of a radiation protection program | high |
| #Q021 | monitoring | health | recommended | Ascertaining exposure to radon progeny and effective dose | other | An employer should ascertain the exposure to radon progeny and the effective dose by direct measurement as a result of monitoring; or by expert estimates. | high | |
| #Q022 | reporting | reporting | mandatory | Provision of information to occupationally exposed workers | other | The employer shall inform each occupationally exposed worker, in writing: 1. that he or she is an occupationally exposed worker; 2. of the risks associated with radiation to which the worker may be exposed in the course of his or her work, including the risks associated with the exposure of embryos and foetuses to radiation; 3. of the applicable radiation dose limits for occupationally exposed workers shown in Table 2.1; and 4. of the worker's radiation dose levels. | Occupationally exposed workers | high |
| #Q023 | administrative | reporting | recommended | Written acknowledgement from occupationally exposed workers | other | The employer should obtain from each occupationally exposed worker a written acknowledgement that the worker has received this information. | high | |
| #Q024 | monitoring | health | recommended | Use of licensed dosimetry service | other | Employers should use a dosimetry service, meeting the requirements of S-106, Technical and Quality Assurance Standards for Dosimetry Services in Canada, to measure the radiation doses to occupationally exposed workers who have a reasonable probability of receiving an effective dose greater than 5 mSv in a one-year dosimetry period. | Workers have a reasonable probability of receiving an effective dose > 5 mSv/year | high |
| #Q025 | reporting | reporting | recommended | Pregnant worker notification | other | Every occupationally exposed worker who becomes aware that she is pregnant should immediately inform the employer in writing. | When an occupationally exposed worker becomes pregnant | high |
| #Q026 | administrative | health | recommended | Employer accommodation for pregnant workers | other | On being informed by an occupationally exposed worker that she is pregnant, the employer should make accommodation to comply with Note (b), Table 2.1, that will not constitute undue hardship to the employer. | Upon being informed of worker pregnancy | high |
| #Q027 | corrective_action | health | mandatory | Actions when dose limit is exceeded | other | When an employer becomes aware that a dose of radiation received by and committed to a person may have exceeded an applicable dose limit shown in Table 2.1, the employer shall: 1. immediately notify the person and the Provincial Authorities of the dose; 2. require the person to leave any work that is likely to add to the dose; 3. conduct an investigation to determine the magnitude of the dose and to establish the causes of the exposure; 4. identify and take any action required to prevent the occurrence of a similar incident; and 5. within 21 days after becoming aware that the dose limit has been exceeded, report the results of the investigation to the appropriate government authority (reference Appendix B) or on the progress that has been made in conducting the investigation. | When dose limits in Table 2.1 are exceeded | high |
| #Q028 | administrative | reporting | recommended | Labelling of containers and devices | other | Containers that store NORM radioactive material should be labelled with: 1. the radiation warning symbol set out in Figure G-1 and the words "RAYONNEMENT - DANGER - RADIATION"; and 2. the name, quantity, date of measurement and form of the radioactive material in the container. | Unless container holds NORM for immediate use or quantity is below Table 5.1 limits | high |
| #Q029 | administrative | reporting | recommended | Posting of signs at boundaries and access points | other | The employer should place a durable and legible sign that bears the radiation warning symbol shown in Figure G-1 and the words "RAYONNEMENT - DANGER - RADIATION", at the boundary, and at every point of access to the area, room or enclosure: | When radioactive material exceeds 100 times Table 5.1 values or probability of dose rate > 25 µSv/h | high |
| #Q030 | administrative | reporting | recommended | Use of radiation warning symbol | other | Whenever the radiation warning symbol is used it should be: 1. prominently displayed; 2. of an appropriate size for the size of the container to which it is attached, or of the area, room, enclosure or vehicle for which it is posted; 3. oriented with one blade pointed downward and centred on the vertical axis; 4. no wording shall be superimposed on it. | high | |
| #Q031 | prohibition | reporting | recommended | Frivolous posting of signs prohibition | other | A radiation warning sign should not be posted at a place where the radiation dose rate or radioactive material indicated on the sign is not present. | high | |
| #Q032 | administrative | reporting | recommended | Records to be kept by employer | other | Every employer should keep a record of the name and job category of each occupationally exposed worker. | high | |
| #Q033 | design | operational | recommended | Radiation Protection Evaluator Qualification | other | It is strongly recommended that a person knowledgeable in radiation protection conduct the worksite radiological evaluation. | During worksite radiological evaluation | high |
| #Q034 | operational | health | mandatory | Five-Year Average Dose Compliance | other | Ensure that workers do not exceed the five-year average occupational dose limit of 20 mSv/a. | Under Measured Annual Effective Dose in Radiation Protection Management | high |
| #Q035 | administrative | reporting | recommended | Worker Information Provision Duty | other | An occupationally exposed worker should on request of the employer provide the worker's: 1. given names, surname and any previous surname; 2. Social Insurance Number; 3. gender; 4. date, province or state and country of birth; and 5. dose record for the current one-year and five-year dosimetry periods. | Upon request of the employer | high |
| #Q036 | reporting | reporting | recommended | Information Provision to Female Workers | other | The employer should inform each occupationally exposed female worker, in writing, of the applicable effective dose limits shown in Table 2.1. | high | |
| #Q037 | operational | health | mandatory | Pregnancy Effective Dose Limit | other | For the balance of a known pregnancy, the effective dose to an occupationally exposed worker must be limited to 4 mSv as stipulated in the "Radiation Protection Regulations", Canadian Nuclear Safety Act. | Known pregnancy of an occupationally exposed worker | high |
| #Q038 | monitoring | health | recommended | Elevated Radon Concentration Measurement | other | Where the annual average concentration of radon gas is expected to be above 200 Bq/m³, measurements should be made to estimate the average annual radon gas concentration. | Expected annual average radon concentration > 200 Bq/m³ | high |
| #Q039 | monitoring | operational | mandatory | Dose Management Site Assessment | other | Assess the work site periodically to measure changes in conditions and to facilitate worker dose calculations. | Under Dose Management or Radiation Protection Management classifications | high |
| #Q040 | operational | operational | recommended | Timely NORM Transport to Secure Site | other | Timely transportation of NORM to a secure central site is recommended. | When NORM shipments fall under federal jurisdiction | high |
| #Q041 | design | health | recommended | Chemical Toxicity Review | other | Chemical and radiological toxicity should be reviewed prior to setting workplace exposure limits. | When setting exposure limits for long-lived NORM radionuclides | high |
| #Q042 | monitoring | health | recommended | Long-term radon assessment in excavations | other | long-term assessment measurements are recommended. | In excavations and tunneling where there is no distinction between background radon and that introduced or released by the industrial practice | high |
| #Q043 | operational | health | mandatory | Respirator selection service and fitting program | other | A high protection factor can only be obtained if there is an effective respirator selection, service and fitting program. | When implementing a respiratory protection program | high |
| #Q044 | administrative | unknown | guidance | Provincial waste disposal agency consultation | other | It may be necessary to consult and obtain approval from Provincial waste disposal regulatory agencies regarding non-radiological properties. | Regarding non-radiological properties for unrestricted release/disposal | high |
| #Q045 | monitoring | operational | recommended | Thin window detector usage | other | A thin window radiation detector is recommended when monitoring beta/gamma sources of surface contamination. | monitoring beta/gamma sources of surface contamination | high |
| #Q046 | corrective_action | operational | recommended | Program Effectiveness Reassessment | drinking water, wastewater, other | The retrospective finding that a dose constraint, as opposed to a dose limit, has been exceeded does not imply a failure to comply with the recommendations of the guidelines. Rather it should call for a reassessment of the effectiveness of the program. | When a retrospective finding shows a dose constraint has been exceeded | high |
| #Q047 | administrative | operational | mandatory | Worker Classification for ALI Assignment | other | Two groups of workers must be considered in assigning ALIs: Occupationally Exposed Workers are employees who are exposed to NORM sources of radiation through their regular duties... Incidentally Exposed Workers are other employees whose regular duties do not include exposure to NORM sources of radiation. | When assigning Annual Limits on Intake (ALIs) for workers | high |
| #Q048 | monitoring | operational | mandatory | Radon Progeny Evaluation Methodology | other | The only approved personal dosimetry system measures progeny concentration (J/m³), therefore dose assessment as required in a Radiation Protection Management Program must be evaluated on that basis. | When performing dose assessments within a Radiation Protection Management Program for radon | high |
| Req ID | Category | Intent | Legal Status | Name | Subdomain(s) | Limit Type | Limit Value | Context | Conditions | Confidence |
|---|---|---|---|---|---|---|---|---|---|---|
| #P001 | radiological | health | guideline | Uranium-238 Series (all progeny) - Aqueous | drinking water, other | requirement | 1 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. Subsequent dilution of the release is assumed. | high |
| #P002 | radiological | health | guideline | Uranium-238 (U-238, Th-234, Pa-234m, U-234) - Aqueous | drinking water, other | requirement | 10 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P003 | radiological | health | guideline | Thorium-230 - Aqueous | drinking water, other | requirement | 5 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P004 | radiological | health | guideline | Radium-226 (in equilibrium with its progeny) - Aqueous | drinking water, other | requirement | 5 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P005 | radiological | health | guideline | Lead-210 (in equilibrium with bismuth-210 and polonium-210) - Aqueous | drinking water, other | requirement | 1 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P006 | radiological | health | guideline | Thorium-232 Series (all progeny) - Aqueous | drinking water, other | requirement | 1 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P007 | radiological | health | guideline | Thorium-232 - Aqueous | drinking water, other | requirement | 1 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P008 | radiological | health | guideline | Radium-228 (in equilibrium with Ac-228) - Aqueous | drinking water, other | requirement | 5 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P009 | radiological | health | guideline | Thorium-228 (in equilibrium with all its progeny) - Aqueous | drinking water, other | requirement | 1 Bq/L | Unconditional Derived Release Limits - Diffuse NORM Sources | Aqueous Release limits ~10x Guidelines for Canadian Drinking Water Quality. | high |
| #P010 | radiological | health | guideline | Dose Constraint | other | requirement | 0.3 mSv/a | Investigation Threshold and Dose constraint for members of the public or incidentally exposed workers | An incremental dose of 0.3 mSv/a is adopted as the NORM Investigation Threshold. | high |
| #P011 | radiological | health | guideline | Occupationally Exposed Workers - Annual Effective Dose Limit | other | requirement | 20 mSv | Radiation dose limits foundation for all radiation protection program recommendations | Maximum dose of 50 mSv in one year is allowed, provided that the total effective dose of 100 mSv over a five-year period is maintained. | high |
| #P012 | radiological | health | guideline | Incidentally Exposed Workers and Members of the Public - Annual Effective Dose Limit | other | requirement | 1 mSv | Radiation dose limits foundation for all radiation protection program recommendations | Cumulative dose limit of 5 mSv over five years. | high |
| #P013 | radiological | health | guideline | Dose Management Threshold | other | requirement | 1 mSv/a | Threshold for initiating Dose Management program for workers | Assessed incremental dose to a worker. | high |
| #P014 | radiological | health | guideline | Radiation Protection Management Threshold | other | requirement | 5 mSv/a | Threshold for initiating formal Radiation Protection Management program | Assessed or measured incremental worker dose. | high |
| #P015 | radiological | health | guideline | Gamma Radiation Investigation Threshold | other | requirement | 0.15 µSv/h | Derived Working Limit (DWL) for gamma radiation | Incremental dose-rate above off-site background. | high |
| #P016 | radiological | health | guideline | Gamma Radiation Dose Management Threshold | other | requirement | 0.5 µSv/h | Derived Working Limit (DWL) for gamma radiation | Incremental dose-rate. | high |
| #P017 | radiological | health | recommended | Radon Investigation Derived Working Limit | other | requirement | 200 Bq/m³ | Screening level for workplaces to be assessed for potential elevated levels | Average radon concentration. Unrestricted Classification applies below this level. | high |
| #P018 | radiological | health | guideline | Radon Radiation Protection Management Threshold | other | requirement | 800 Bq/m³ | Threshold for initiating formal Radiation Protection Management program due to radon | Average annual radon concentration. | high |
| #P019 | radiological | health | guideline | Surface Contamination Dose Rate Limit | other | requirement | 0.5 µSv/h | Surface Contamination Unconditional Derived Release Limits - Discrete NORM Sources | Measured at 50 cm distance. | high |
| #P020 | radiological | health | guideline | Surface Contamination Activity Limit | other | requirement | 1 Bq/cm² | Surface Contamination Unconditional Derived Release Limits - Discrete NORM Sources | Averaged over a 100 cm² area. | high |
| #P021 | radiological | health | guideline | Occupationally Exposed Workers - Five Year Cumulative Dose Limit | other | requirement | 100 mSv | Radiation dose limits for five year cumulative periods | Total effective dose over a five-year period. | high |
| #P022 | radiological | health | guideline | Incidentally Exposed Workers and Members of the Public - Five Year Cumulative Dose Limit | other | requirement | 5 mSv | Radiation dose limits for five year cumulative periods | Total effective dose over a five-year period. | high |
| #P023 | radiological | health | mandatory | Pregnant Occupationally Exposed Worker - Effective Dose Limit | other | requirement | 4 mSv | Dose limit for the balance of a known pregnancy | Applies for the duration of the pregnancy once known to the employer. | high |
| #P024 | radiological | reporting | recommended | Radiation Warning Sign Posting Threshold | other | requirement | > 25 µSv/h | Requirement for posting durable and legible radiation warning signs | Reasonable probability that a person in the area will be exposed to this rate. | high |
| #P025 | radiological | operational | mandatory | SCO Non-fixed Contamination Limit - Beta/Gamma/Low Toxicity Alpha | other | requirement | < 0.4 Bq/cm² | Exemption criteria from PTNSR for Surface Contaminated Objects (SCO) | Averaged over each 300 cm² of all surfaces. | high |
| #P026 | radiological | operational | mandatory | SCO Non-fixed Contamination Limit - Other Alpha Emitters | other | requirement | < 0.04 Bq/cm² | Exemption criteria from PTNSR for Surface Contaminated Objects (SCO) | Averaged over each 300 cm² of all surfaces. | high |
| #P027 | radiological | health | guideline | Uranium-238 Series (all progeny) - Solid Diffuse NORM | other | requirement | 300 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration. | high |
| #P028 | radiological | health | guideline | Uranium-238 Series (all progeny) - Airborne Diffuse NORM | other | requirement | 0.003 Bq/m³ | Unconditional Derived Release Limits - Diffuse NORM Sources | Air concentration. | high |
| #P029 | radiological | health | guideline | Uranium Ore - Discrete NORM Source | other | requirement | 1000 Bq | Unconditional Derived Release Limits for discrete sources | Uranium ore in equilibrium with all progeny. | high |
| #P030 | radiological | health | guideline | Radon Radiation Protection Management Upper Limit | other | requirement | 3000 Bq/m³ | Upper boundary of Radiation Protection Management for radon based on occupational dose limit (5 year average) | Assumes 2000 hours per year occupational exposure and equilibrium factor of 0.4 | high |
| #P031 | radiological | health | guideline | Uranium-238 (partitioned) - Solid Diffuse NORM | other | requirement | 10000 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration for partitioned U-238 (U-238, Th-234, Pa-234m, U-234) | high |
| #P032 | radiological | health | guideline | Thorium-230 - Solid Diffuse NORM | other | requirement | 10000 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration | high |
| #P033 | radiological | health | guideline | Radium-226 (in equilibrium) - Solid Diffuse NORM | other | requirement | 300 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration | high |
| #P034 | radiological | health | guideline | Radium-226 (in equilibrium) - Discrete NORM Source | other | requirement | 10000 Bq | Unconditional Derived Release Limits for discrete sources | Total activity of Radium-226 in equilibrium with its progeny | high |
| #P035 | radiological | health | guideline | Thorium-232 (in equilibrium) - Discrete NORM Source | other | requirement | 1000 Bq | Unconditional Derived Release Limits for discrete sources | Total activity of Thorium-232 in equilibrium with all progeny | high |
| #P036 | radiological | health | guideline | Lead-210 Occupational ALI - Inhalation | other | requirement | 18000 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on 5 µm AMAD and absorption type F | high |
| #P037 | radiological | health | guideline | Radium-226 Occupational ALI - Ingestion | other | requirement | 71000 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on fraction f1 = 0.2 | high |
| #P038 | radiological | health | guideline | Occupationally Exposed Workers - Maximum Single Year Effective Dose | other | requirement | 50 mSv | Annual limit for occupationally exposed workers in any single year | Total effective dose of 100 mSv over a five-year period must be maintained. | high |
| #P039 | radiological | health | guideline | Potassium-40 - Solid Diffuse NORM | other | requirement | 17000 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Based on natural abundance of Potassium 40 in potassium chloride. | high |
| #P040 | radiological | health | guidance | Radon-222 Progeny Dose Conversion Factor | other | requirement | 5 mSv/WLM | Conversion factor from Working Level Months to millisieverts for workers | Specific to Radon-222 progeny; Radon-220 progeny must be treated separately. | high |
| #P041 | radiological | operational | mandatory | Activity Concentration for Exempt Material - U-(nat) | other | requirement | 1 Bq/g | Basic NORM Radionuclide Values for transport exemption | Shipments are subject to federal regulations if activity concentration exceeds 10 times this value. | high |
| #P042 | radiological | health | guideline | Lead-210 Occupational ALI - Ingestion | other | requirement | 29000 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on fraction f1 = 0.2 | high |
| #P043 | radiological | health | guideline | Thorium-228 Occupational ALI - Inhalation (Type S) | other | requirement | 600 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on 5 µm AMAD and absorption type S (Slow) | high |
| #P044 | radiological | health | guideline | Uranium (all progeny) Occupational ALI - Inhalation | other | requirement | 2800 Bq | Annual Limit on Intake for Occupationally Exposed Workers from AECB 1995 | Mixed lung absorption types assumed | high |
| #P045 | radiological | health | guideline | Thorium-232 - Solid Diffuse NORM | other | requirement | 10000 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration for Thorium-232 | high |
| #P046 | radiological | health | guideline | Potassium-40 - Discrete NORM Source | other | requirement | 1000000 Bq | Unconditional Derived Release Limits for discrete sources | Total activity of Potassium-40 | high |
| #P047 | operational | treatment | recommended | Inhalation Engineering Control Threshold | other | requirement | > 0.05 ALI | Threshold for implementing engineering controls for airborne NORM | When annual intakes exceed 1/20 of the ALI | high |
| #P048 | operational | health | guidance | Respiratory Protection Threshold | other | requirement | > 5 mSv/a | Threshold for considering respiratory protection programs | If intakes exceed 25% of the ALI after engineering controls are applied | high |
| #P049 | radiological | reporting | recommended | Radiation Warning Sign Posting Quantity Threshold | other | requirement | > 100 multiplier | Threshold for posting radiation warning signs based on material activity | Radioactive material present in an activity greater than 100 times Table 5.1 values | high |
| #P050 | radiological | health | guideline | Thorium-232 Series (all progeny) - Solid Diffuse NORM | other | requirement | 300 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration for the entire Thorium-232 decay series in equilibrium. | high |
| #P051 | radiological | health | guideline | Thorium-232 Series (all progeny) - Airborne Diffuse NORM | other | requirement | 0.002 Bq/m³ | Unconditional Derived Release Limits - Diffuse NORM Sources | Air concentration for the entire Thorium-232 decay series in equilibrium. | high |
| #P052 | radiological | health | guideline | Radium-228 (in equilibrium with Ac-228) - Solid Diffuse NORM | other | requirement | 300 Bq/kg | Unconditional Derived Release Limits - Diffuse NORM Sources | Solid material concentration. | high |
| #P053 | radiological | health | guideline | Radium-228 (in equilibrium with Ac-228) - Airborne Diffuse NORM | other | requirement | 0.005 Bq/m³ | Unconditional Derived Release Limits - Diffuse NORM Sources | Air concentration. | high |
| #P054 | radiological | health | guideline | Lead-210 (in equilibrium) - Discrete NORM Source | other | requirement | 10000 Bq | Unconditional Derived Release Limits for discrete NORM sources | In equilibrium with bismuth-210 and polonium-210. | high |
| #P055 | radiological | health | guideline | Radium-228 (in equilibrium) - Discrete NORM Source | other | requirement | 100000 Bq | Unconditional Derived Release Limits for discrete NORM sources | In equilibrium with actinium-228. | high |
| #P056 | radiological | health | guideline | Polonium-210 Occupational ALI - Ingestion | other | requirement | 83000 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on fraction f1 = 0.1 | high |
| #P057 | radiological | health | guideline | Thorium-232 Occupational ALI - Inhalation (Type M) | other | requirement | 700 Bq | Annual Limit on Intake for Occupationally Exposed Workers | Based on 5 µm AMAD and absorption type M (Moderate). | high |
| Req ID | Category | Name | Context | Confidence |
|---|---|---|---|---|
| #D001 | ALARA | An acronym for "As Low As Reasonably Achievable", social and economic factors being taken into account. ALARA is a guiding principle in radiation protection, and encourages managers to reduce dose levels as much as possible, even if they are already meeting allowable levels. | high | |
| #D002 | ALI | Annual Limit on Intake | high | |
| #D003 | BEIR | (United States National Academy of Science Committee on the) Biological Effects of Ionizing Radiation | high | |
| #D004 | CNSC | Canadian Nuclear Safety Commission is the federal agency that licenses and regulates nuclear facilities and materials. The CNSC is the successor to the Atomic Energy Control Board (AECB). | high | |
| #D005 | DC | Dose Coefficient | high | |
| #D006 | DRL | Derived Release Limit | high | |
| #D007 | DWL | Derived Working Limit | high | |
| #D008 | IAEA | International Atomic Energy Agency | high | |
| #D009 | ICRP | International Commission on Radiological Protection | high | |
| #D010 | NCRP | National Council on Radiation Protection and Measurements | high | |
| #D011 | NDR | National Dosimetry Registry | high | |
| #D012 | NORM | Naturally Occurring Radioactive Material | high | |
| #D013 | PTNSR | Packing and Transport of Nuclear Substances Regulations | high | |
| #D014 | SCO | Surface Contaminated Object | high | |
| #D015 | TDGR | Transportation of Dangerous Goods Regulations | high | |
| #D016 | TENORM | Technologically Enhanced Naturally Occurring Radioactive Material | high | |
| #D017 | UDRL | Unconditional Derived Release Limit | high | |
| #D018 | UNSCEAR | United Nations Scientific Committee on the Effects of Atomic Radiation | high | |
| #D019 | NORM | NORM is an acronym for naturally occurring radioactive materials, which include radioactive elements found in the environment. | high | |
| #D020 | Effective Dose | The ICRP defines the effective dose as the sum of all tissue equivalent doses multiplied by the appropriate tissue weighting factors associated with each respective tissue. | high | |
| #D021 | Occupationally Exposed Workers | Occupationally Exposed Workers are employees who are exposed to NORM sources of radiation as a result of their regular duties. | high | |
| #D022 | Incidentally Exposed Workers | Incidentally Exposed Workers are employees whose regular duties do not include exposure to NORM sources of radiation. | high | |
| #D023 | Members of the Public | Members of the Public are persons who have no occupational exposure to NORM. | high | |
| #D024 | Surface contaminated object (SCO) | A surface contaminated object (SCO) is a solid object which is not itself radioactive but which has radioactive material distributed on its surface. | high | |
| #D025 | Low toxicity alpha emitters | Low toxicity alpha emitters are: natural uranium, depleted uranium, uranium-235 or uranium-238, thorium 232, thorium -228 and thorium-230 when contained in ores or physical and chemical concentrates, or alpha emitters with a half life less than 10 days. | high | |
| #D026 | Absorbed Dose | The mean energy deposited by ionizing radiation per unit mass of the body or organ or tissue of the body. Unit: gray (Gy), 1 Gy = 1 joule per kilogram. | high | |
| #D027 | Activity (Radioactivity) | The number of nuclear transformations that occur in a quantity of material per unit of time. Unit: becquerel (Bq), 1 Bq = 1 disintegration per second. | high | |
| #D028 | Alpha Radiation (Alpha Decay) | A high-energy positively charged particle ejected from the nucleus of an unstable (radioactive) atom, consisting of two protons and two neutrons. An alpha particle is a helium nucleus. | high | |
| #D029 | Annual Limit on Intake (ALI) | The intake by inhalation, ingestion or through the skin of a given radionuclide in a year by a reference man which would result in a committed dose equal to the relevant dose limit. The ALI is expressed in units of activity. | high | |
| #D030 | Background Radiation | The radiation to which an individual is exposed arising from natural radiation sources such as terrestrial radiation from radionuclides in the soil, cosmic radiation from space, and naturally occurring radionuclides deposited in the body from foods, etc. | high | |
| #D031 | Becquerel (Bq) | An SI unit of radioactivity, equivalent to 1 nuclear transformation per second. Used as a measurement of the quantity of a radionuclide since the number of radioactive transformations (disintegrations) is directly proportional to the number of atoms of the radionuclide present. Replaces an earlier unit, the curie (Ci). | high | |
| #D032 | Beta Radiation (Beta Decay) | The ejection of a high-energy negatively charged subatomic particle from the nucleus of an unstable atom. A beta particle is identical in mass and charge to an electron. | high | |
| #D033 | Contamination (Radioactive Contamination) | Radioactive material present in excess of natural background quantities in a place it is not wanted. | high | |
| #D034 | Committed Dose | The total dose received from a radioactive substance in the body during the remainder of a person's life (assumed as 50 years for adults, 70 years for children) following the intake of the radionuclide. | high | |
| #D035 | Curie (Ci) | A unit of activity equivalent to 3.7 x 10 10 disintegrations per second. Replaced in international usage by the becquerel. | high | |
| #D036 | Decay (Radioactive Decay) | A process followed by an unstable nucleus to gain stability by the release of energy in the form of particles and/or electromagnetic radiation. NORM materials decay with the release of alpha particles, beta particles and/or gamma photons. | high | |
| #D037 | Derived Working Limit (DWL) | A practical working limit derived from regulatory limits. Derived Working Limits can be compared to measured values at the work site to assess compliance with regulatory limits. | high | |
| #D038 | Diffuse NORM | NORM-contaminated material in which the radioactive concentration is uniformly dispersed. It is generally low in radioactive concentration, and relatively large in volume. | high | |
| #D039 | Discrete NORM | NORM-contaminated material in which radioactive substances are concentrated, or not uniformly dispersed throughout the material. It generally has much higher levels of radioactive concentration in a localized volume than diffuse NORM. | high | |
| #D040 | Dose Constraint | An upper bound on the annual dose that members of the public or incidentally exposed workers should receive from a planned operation or single source. | high | |
| #D041 | Dosimeter | A device for measuring a dose of radiation that is worn or carried by an individual. | high | |
| #D042 | Equilibrium (Radioactive) | In a radioactive decay series, the state that prevails when the rate at which progeny are produced is equal to the rate at which they are decaying. This form of equilibrium may be attained only if the precursor is very long-lived relative to any member of the decay chain. All members of a NORM radioactive decay series in equilibrium have the same radioactivity. | high | |
| #D043 | Equivalent Dose | The absorbed dose multiplied by a "radiation weighting factor", (w R), which accounts for the different potential for adverse effects of the different types of radiation. Unit: sievert (Sv). | high | |
| #D044 | Gamma Radiation (Gamma Rays or Gamma Photons) | Electromagnetic radiation or photon energy emitted from an unstable nucleus in the process of ridding itself of excess energy. Highly penetrating, gamma rays lose energy as they pass through atoms of matter. | high | |
| #D045 | Gray (Gy) | Radiation damage is dependent on the absorption of radiation energy and is approximately proportional to the concentration of absorbed energy in tissue. The gray is the SI unit of absorbed radiation dose corresponding to the absorption of 1 joule of radiation energy per kilogram of material. For gamma and beta radiations, the gray is numerically equal to the sievert. | high | |
| #D046 | Groundshine | Radiation detectable on the earth's surface from radioactive substances on or beneath the surface. | high | |
| #D047 | Half-life, Biological | The time required for the body to eliminate half the quantity of a substance taken into the body. A major factor in determining a radionuclide's Dose Coefficient. | high | |
| #D048 | Half-life, Radioactive | The time required for a radioactive material to lose half of its activity through radioactive decay. | high | |
| #D049 | Incremental Dose | Radiation dose found in excess of the local background radiation dose. | high | |
| #D050 | Personal Dosimetry Threshold | The annual effective dose above which radiation dosimetry of individual workers is required. | high | |
| #D051 | Phosphogypsum Stack | Phosphogypsum stack refers to the storing of phosphogypsum, a byproduct of fertilizer production, in large outdoor stockpiles. | high | |
| #D052 | Rad | A historical radiation unit for measuring radiation energy absorption (dose), equivalent to 100 ergs per gram in any medium. RAD is an acronym for Radiation Absorbed Dose. Now replaced in international system of units by the "gray" (Gy). | high | |
| #D053 | Radiation Weighting Factor (w R) | A value recommended by the International Commission on Radiological Protection, and usually adopted by national regulatory agencies, to convert absorbed dose from various types of ionizing radiation into its dose equivalent in terms of biological harm from alpha, beta or gamma radiation. For gamma rays and beta particles, w R = 1. For alpha particles and fast neutrons, w R = 20. | high | |
| #D054 | Radiochemical Analysis | Analysis of the radioactive content of a NORM sample. Radiochemical analysis will identify and quantify the concentration of various radionuclides in the NORM sample. | high | |
| #D055 | Radionuclide or Radioisotope | A particular form of an element, characterized by a specific atomic mass and atomic number, whose atomic nucleus is unstable and decays or disintegrates with a statistical probability characterized by its physical half-life. | high | |
| #D056 | Radon | The only radioactive gas generated during natural radioactive decay processes. Two radioisotopes of radon are present - radon and thoron - each a decay product of radium. Radon (Rn-222) is found in the uranium decay series while thoron (Rn-220) is found in the thorium decay series. | high | |
| #D057 | Rem | A historical unit of human dose equivalent. Rem is an acronym for roentgen equivalent man and was replaced in 1977 by the sievert in the international system of units. | high | |
| #D058 | Roentgen (R) | The classical unit of radiation ionization in air, frequently misapplied as a unit of exposure in humans. Replaced in international system of units by the "coulomb per kg in air". | high | |
| #D059 | Shielding | The reduction of radiation beam intensity by interposing, between the source and an object or person that might be exposed, a substance that absorbs radiation energy, either by collision, in the case of particulate radiation, or by absorption of waveform energy, in the case of gamma photons. | high | |
| #D060 | SI (Systeme Internationale) | The "metric" system of units generally based on the metre/kilogram/second units. Special quantities for radiation include the becquerel, gray and sievert. | high | |
| #D061 | Sievert (Sv) | The sievert is the unit of radiation equivalent dose, H, that is used for radiation protection purposes, for engineering design criteria and for legal and administrative purposes. The sievert is the SI unit of absorbed radiation dose in living organisms modified by radiation type and tissue weighting factors. The unit of dose for the terms "equivalent dose" and "effective dose". It replaces the classical radiation unit the rem. Multiples of sieverts (Sv) used in the Guidelines include millisieverts (mSv) and microsieverts (µSv). | high | |
| #D062 | Specific Activity (Radioactive Concentration) | The number of becquerels per unit of mass of a material. Units: Bq/g and kBq/kg | high | |
| #D063 | Tissue Weighting Factor (w T) | A weighting factor developed by the ICRP that assigns a relative share of total radiation dose detriment to specific organs and tissues. Risks from localized radiation exposures to specific organs and tissues can be quantified. | high | |
| #D064 | Unconditional Derived Release Limits (UDRL) | Within the Unrestricted classification, the radioactive activity of NORM below which NORM can be released into the public domain without restrictions. | high | |
| #D065 | Working Level (WL) | A unit for potential alpha energy concentration, (PAEC), resulting from the presence of radon progeny equal to the emission of 1.3 x 10 5 MeV of alpha energy per litre of air. In SI units the WL corresponds to 2.08 x 10 -5 joules per cubic metre (J/m³). | high | |
| #D066 | Working Level Month (WLM) | A measure of the cumulative exposure to radon progeny in air. One Working Level Month is defined as the exposure received by an individual inhaling air containing a radon progeny concentration of one WL for a period of 170 hours, the assumed number of hours in a working month. One working level month is equivalent to 3.54 mJ h m -3. | high | |
| #D067 | Atomic Number | The number of protons contained in the nucleus of an atom. This number gives each atom its distinct chemical identity. | high | |
| #D068 | Atomic Mass (Mass Number) | The total mass of protons and neutrons contained in the nucleus of an atom. | high | |
| #D069 | Balance of Pregnancy | The period from the moment an employer is informed of the pregnancy to the end of the pregnancy. | high | |
| #D070 | Decay Series (Radioactive Decay Series) | A succession of radionuclides, each member of which transforms by radioactive decay into the next member until a stable nuclide results. The first member is called the "parent", the intermediate members are called "progeny" and the final stable member is called the "end product". In the two NORM decay series; uranium-238 and thorium-232 are the "parents," and lead-206 and lead-208 are the "end products". | high | |
| #D071 | Five Year Dosimetry Period | The period of five calendar years beginning on January 1 of the year following the year in which the Radiation Protection Management Program is started, and every period of five calendar years thereafter. | high | |
| #D072 | One-year Dosimetry Period | The period of one calendar year beginning on January 1 of the year following the year in which the Radiation Protection Management Program is started, and every period of one calendar year thereafter. | high | |
| #D073 | Radon Progeny | The products of radon (radon-222) or thoron (radon-220) decay with short half-lives. Radon decay products include; Polonium-218 (RaA), Lead-214 (RaB), Bismuth-214 (RaC), and Polonium-214 (RaC'). Thoron decay products include; Polonium-216 (ThA), Lead-212 (ThB), Bismuth-212 (ThC), Polonium-212 (ThC'), and Thallium-208 (ThC") | high | |
| #D074 | Isotopes | Atoms of an element that have different numbers of neutrons are called isotopes of that element, though they all behave chemically the same way. | high | |
| #D075 | Nuclear Disintegration | In isotopes of some elements, however, the balance of protons and neutrons in the atom makes the atom unstable, so it ejects one or more particles and excess energy from the nucleus to become more stable. This process is called nuclear disintegration. | high | |
| #D076 | Ionizing Radiation | The particles or high-energy rays are called "ionizing radiation" because they ionize, or change the physical and chemical structure of, other atoms of matter they pass through. | high | |
| #D077 | Radioactive | Elements that emit ionizing radiation are called radioactive; in some cases, one or more isotopes of an element are radioactive, and are called radioisotopes, or radionuclides. | high | |
| #D078 | Half-life | The half-life is the length of time it takes for half of a substance's atoms to 'decay' to a more stable form, or to reduce the radioactivity by half. | high | |
| #D079 | DC | A factor that relates the amount of radiation dose (Sv) delivered to the body per unit of activity (becquerel) taken into the body. Unit: (Sv/Bq). | high | |
| #D080 | Becquerel | The becquerel (Bq) measures the quantity of radioactivity present without consideration for what kind of radiation is emitted. 1 Bq = 1 nuclear transformation (disintegration) per second. | high | |
| #D081 | Sievert | The sievert (Sv) is the unit of Effective Dose of radiation, and accounts for the total effect of different types of radiation on different parts of the body. | high | |
| #D082 | Justification | No activity involving ionizing radiation for any purpose can be justified unless it is possible to demonstrate that it will lead to a positive net benefit. | high | |
| #D083 | Optimization | All exposures shall be kept as low as reasonably achievable, economic and social factors being taken into consideration (the ALARA principle). | high | |
| #D084 | Limitation | The maximum acceptable occupational exposure of any individual must not involve a radiation risk to that individual greater than the risk that arises in working in what is generally regarded as a "safe" industry. | high | |
| #D085 | Investigation Threshold | An incremental dose of 0.3 mSv/a, the dose constraint value set in section 2.4.3, is adopted as the NORM Investigation Threshold. | high | |
| #D086 | NORM Management Threshold | An assessed incremental dose to the public or workers of greater than 0.3 mSv/a, the dose constraint value set in section 2.4.3 and the Investigation Threshold, is adopted as the NORM Management Threshold. | high | |
| #D087 | Dose Management Threshold | An assessed incremental dose of 1 mSv/a to a worker is adopted as the Dose Management Threshold. | high | |
| #D088 | Radiation Protection Management Threshold | An assessed or measured incremental worker dose of 5 mSv/a is adopted as the Radiation Protection Management Threshold. | high |