CSA N292.5:25

Description

Preface This is the second edition of CSA N292.5, Guideline for exemption or clearance of materials that contain, or potentially contain, nuclear substances. It supersedes the previous edition, published in 2011 under the title Guideline for the exemption or clearance from regulatory control of materials that contain, or potentially contain, nuclear substances. This Guideline was developed in response to a need for guidance on approaches to exemption and clearance of materials consistent with Canadian and international recommendations. Changes to this edition include the following: a) updated for harmonization and consistency with the umbrella Standard, CSA N292.0, including alignment with defined terms in N292.0, and clause cross-references; b) clarified the differences in application of the MARSSIM Unity Rule for mixtures versus the equations derived from the Nuclear Substances and Radiation Devices Regulations (NSRDR) requirements; c) included best practices and guidance from IAEA SRS 67, GSG-17 and GSG-18; d) improved the consistency of terminology (e.g., consistent use of impacted material); and e) modified and removed administrative provisions and terminology as applicable (e.g., reference to “licence”). This Guideline works in concert with CSA N292.0, which specifies common requirements for the management of radioactive waste or irradiated fuel. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group Nuclear Standards provide technical requirements and guidance that support the management system. This Guideline works in harmony with CSA N286; however, it might provide more specific direction for those requirements. Users of this Guideline are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Guideline. This Guideline was prepared by the Subcommittee on Application of Unconditional Clearance of Materials from Nuclear Facilities, under the jurisdiction of the Technical Committee on Radioactive Waste Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 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: 1) For the purposes of this Guideline, in Canada, the federal authority having jurisdiction (AHJ) is the Canadian Nuclear Safety Commission (CNSC). 2) Examples of other exemption quantities or clearance levels include specific criteria set by the 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: 1) This Guideline addresses the radiological properties of materials intended for exemption or clearance. 2) 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 a) exemption or clearance of the following types of materials: i) Category I, II, or III material as defined in the Nuclear Security Regulations; ii) liquid or gaseous effluents from nuclear facilities; Note: For requirements and guidance on effluents from nuclear facilities, see the CSA N288 series of Standards. iii) 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: 1) In Canada, NORM and TENORM are addressed by Health Canada in the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM) and are regulated by provincial and territorial governments. 2) While this Guideline is not applicable to the management of NORM or TENORM, the principles in this Guideline can be useful for their management. iv) effluents directly resulting from patients who have received medically administered nuclear substances; and v) remains of deceased nuclear medicine patients from medical facilities; b) aspects related to safeguards; c) non-radiological aspects of materials with mixed contaminants; and d) 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.