Draft Details

Designation:CSA N292.5
Source:CSA
Contact name:Samuel Pahad
Review start date:Jul 19, 2024
Review end date:Sep 17, 2024
Categories:Energy
Contact email:thuy.ton(at)csagroup.org
Draft Scope/Description:

1.1 Application of exemption quantities or clearance levels

This Guideline addresses the application of exemption quantities or clearance levels for the release of waste and other materials containing, or potentially containing, nuclear substances. In this Guideline, such materials are referred to as “impacted materials”.

In this Guideline, “nuclear substances” encompasses those defined by the Nuclear Safety and Control Act, with the exception of Deuterium.

This Guideline has been developed to address the application of the Nuclear Substances and Radiation Devices Regulations (NSRDR), but it may also be used for guidance on the application of other exemption quantities or clearance levels.

Notes:

For the purposes of this Guideline, in Canada, the federal AHJ is the CNSC

Examples of other exemption quantities or clearance levels include specific criteria set by the authority having jurisdiction (AHJ) and the criteria provided in IAEA No. GSR Part 3

 

1.2 Strategies and methodologies for the exemption or clearance process

This Guideline includes strategies and methodologies to optimize efforts and confidence levels of the exemption or clearance process, including

a) determining appropriate exemption quantities, conditional clearance levels, or unconditional clearance levels;

b) providing sampling and analysis techniques for assessing the radiological status of materials identified for exemption or clearance; and

c) applying decision techniques for evaluating sampling and analysis results against the exemption quantities or clearance levels.

1.3 Types of materials

This Guideline addresses exemption or clearance of

a) moderate and bulk quantities of solids, including

i) materials and equipment;

ii) building structures (in-situ) and building materials from demolition activities; and

iii) lands (in-situ) and excavated soils; and

 

b) non-effluent liquids.

Notes:

This Guideline addresses the radiological properties of materials intended for exemption or clearance.

This Guideline also covers radiological aspects of impacted materials with mixed contaminants; that is, materials that contain, or might contain, both nuclear substances and hazardous, chemical, or biological components

 

1.4 Exclusions

This Guideline does not address:

Exemption or clearance of the following types of materials:

Category I, II, or III material as defined in the Nuclear Security Regulations;

liquid or gaseous effluents from nuclear facilities;

For requirements and guidance on effluents from nuclear facilities, see the CSA N288 Series of Standards.

naturally occurring radioactive material (NORM) or technologically enhanced naturally occurring radioactive material (TENORM) other than NORM or TENORM that is or has been associated with the development, production, or use of nuclear energy;

Notes:

In Canada, NORM and TENORM are addressed by Health Canada in Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM) and are regulated by Provincial and Territorial governments.

While this Guideline is not applicable to the management NORM or TENORM, the principles in this Guideline can be useful for their management.

effluents directly resulting from patients who have received medically administered nuclear substances; and

remains of deceased nuclear medicine patients from medical facilities.

aspects related to safeguards;

non-radiological aspects of materials with mixed contaminants; and

application of the concept of exclusion, as defined by the AHJ.

1.5 CSA N292.0

This Guideline is used in conjunction with CSA N292.0, as applicable.

1.6 Users

This Guideline applies to organizations or facilities of all sizes that generate, handle, process, transport, store, and dispose of nuclear substances.

Note: Examples of facilities include, but are not limited to, nuclear reactors, waste management facilities, research institutes, medical facilities, manufacturing facilities, laboratories, and industrial facilities.

1.7 Terminology

In this Guideline, “should” is used to express a recommendation or that which is advised but not required, and “may” is used to express an option or that which is permissible within the limits of the Guideline.

You may comment on any section of this document by clicking the “Submit Comment” link at the bottom of the relevant section.