CSA N290.18:26

Preface This is the second edition of CSA N290.18, Periodic safety review for nuclear power plants . It supersedes the previous edition published in 2017. The following are the major changes to this edition, which address the operating experience from the periodic safety reviews of Canadian nuclear power plants: a) additional guidance for existing requirements; b) addition of a new informative Annex C; c) streamlined clauses to improve overall clarity; and d) addition of clause titles and descriptive text to figures to improve accessibility. This Standard provides requirements regarding the conduct of a periodic safety review (PSR) in accordance with CNSC REGDOC-2.3.3. This Standard is consistent with IAEA SSG-25. Users of this Standard 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 Standard. 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 was prepared by the Subcommittee on Periodic Safety Review for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Safety and Risk Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 General This Standard provides requirements and guidance related to the performance of periodic safety reviews (PSRs) for nuclear power plants (NPPs). Note: This Standard may be used to provide guidance for nuclear facilities other than NPPs using a graded approach. 1.2 Requirements and guidance This Standard provides requirements and guidance related to the PSR for a) developing the basis document; b) conducting reviews of modern requirements documents and practices; c) conducting safety factor reviews to identify findings; d) performing analyses of safety factor findings, including consolidation of identified gaps and strengths, development of global issues, and preparation of a global assessment report (GAR); and e) preparing the integrated implementation plan (IIP) where the developed global issues are resolved into actions. 1.3 Deliverables This Standard identifies required deliverables that facilitate achieving the objectives of the PSR process. 1.4 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. 1.5 Additional terminology In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions. Note: Decisions could include no action.