Preface  

This is the first edition of CSA N292.4, Storage of radioactive waste and irradiated fuel . This Standard is part of the CSA N292 series of Standards on radioactive waste management.  This Standard is a consolidation of and replaces CSA N292.1, Wet storage of irradiated fuel and other radioactive materials, and CSA N292.2, Interim dry storage of irradiated fuel. In addition to the contents of those two Standards, this Standard draws on clauses developed for CSA N292.7, Deep geological disposal of radioactive waste and irradiated fuel, where relevant, to ensure that the entire lifecycle of facilities that include storage of radioactive waste or irradiated fuel is covered in this Standard. This includes, but is not limited to, adding requirements and guidance on engagement, site evaluation, monitoring and surveillance, site preparation, construction, and commissioning.  This Standard works in concert with CSA N292.0, General principles for the management of radioactive waste and irradiated fuel, 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 Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.  This Standard draws on the experience both in Canada and internationally in storage of radioactive waste, irradiated fuel, or other radioactive materials and reflects current best practices.  Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its supporting Regulations.  This Standard was prepared by the Subcommittee on Storage of Radioactive Waste and Irradiated Fuel, 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 Storage facilities and storage areas  

1.1.1 Storage of radioactive waste or irradiated fuel  

This Standard specifies requirements for standalone storage facilities and areas within other facilities dedicated to storage of  a) radioactive waste; or  b) irradiated fuel.  Notes:  1) This includes waste management facilities built within or adjacent to nuclear power plant (NPP) sites, research reactors, and portions thereof that are dedicated to storage of radioactive waste or irradiated fuel.  2) This Standard may be used as guidance for other facilities that house areas for storage of radioactive waste or irradiated fuel, such as research facilities, medical facilities, isotope production facilities, manufacturing facilities, processing facilities, laboratories, or industrial facilities.  3) Storage occurs either in a dry medium, such as in dry storage containers or storage buildings, or in a wet medium, such as in wet storage bays.  4) In this Standard, a) the term “storage system” refers to both standalone storage facilities and storage areas within other types of facilities; and  b) the term “storage facility” refers to standalone facilities for storage of radioactive waste or irradiated fuel, but can generally be considered synonymous with “storage system”.  

1.1.2 Wet storage of other radioactive materials  

The requirements in this Standard also pertain to wet storage of other radioactive materials requiring shielding or decay heat dissipation.  Notes:  1) In this Standard, the term “other radioactive materials” refers to radioactive materials other than irradiated fuel (e.g., sealed sources).  2) Unless specified, the clauses in this Standard apply to radioactive waste, irradiated fuel, and other radioactive materials.  

1.1.3 Storage of damaged or defective irradiated fuel  

This Standard includes requirements for storage of damaged or defective irradiated fuel.  Note: For dry storage of damaged or defective fuel, there can be additional processing and packaging requirements that are not detailed in this Standard.  

1.1.4 On-site transfer  

This Standard includes requirements for on-site transfer of radioactive waste, irradiated fuel, or other radioactive materials  a) from wet storage to dry storage; and b) within a storage system.  

1.2 Lifecycle activities  

This Standard specifies the requirements for the following activities that occur during the lifecycle of a storage facility:  a) Indigenous, public, and stakeholder engagement (see Clause 5);  b) site evaluation (see Clause 6);  c) design (see Clause 7);  d) monitoring and surveillance (see Clause 8);  e) safety assessment (see Clause 9);  f) site preparation (see Clause 10);  g) construction (see Clause 11);  h) commissioning (see Clause 12);  i) operation (see Clause 13); and  j) decommissioning (see Clause 14).  Note: Decommissioning of storage facilities and other facilities containing nuclear substances is subject to the requirements in CSA N294.  

1.3 Exclusions  

This Standard excludes requirements for  a) siting of a storage facility, apart from siting-related aspects during the lifecycle activities of Indigenous, public, and stakeholder engagement; site evaluation; design; and safety assessment;  b) other items that might be stored within the storage system;  Note: Examples of such items include tools.  c) wet source storage gamma irradiators;  Note: Wet source storage gamma irradiators are designed and licensed in accordance with ANSI/HPS N43.10 and IAEA Specific Safety Guide No. SSG-8.  d) off-site transport of radioactive waste, irradiated fuel, or other radioactive materials, including storage during transport, to or from a storage system;  Note: For the off-site transportation of radioactive materials, see the Packaging and Transport of Nuclear Substances Regulations.  e) site evaluation during decommissioning; and  f) uranium mine and mill tailings.  

1.4 CSA N292.0  

This Standard is used in conjunction with CSA N292.0.  

1.5 Users  

This Standard applies to waste organizations or facilities associated with storage of radioactive waste, irradiated fuel, or other radioactive materials, as defined in Clause 1.1.  Note: Waste organizations can refer to waste generators, waste brokers, waste receivers, waste processors, and the operating organizations of waste management facilities.  

1.6 Terminology  

In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; “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 Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.  Notes to tables and figures are considered part of the table or figure and may be written as requirements.  Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application.