N290.18-17

Preface
0 Introduction
1 Scope
2 Reference publications
3 Definitions and abbreviations
4 Overview of a PSR
5 The PSR basis document
6 Review against modern requirements documents and practices
7 Safety factor reports
8 Global assessment
9 IIP
Annex A (informative) - Sample methodology for safety factor
        reviews
Annex B (informative) - Guidance on review against modern
        requirements documents and practices

Specifies requirements and guidance related to the performance of periodic safety reviews (PSRs) for nuclear power plants (NPPs).

Preface This is the first edition of CSA N290.18, Periodic safety review for nuclear power plants. This Standard provides requirements regarding the conduct of a periodic safety review in accordance with CNSC regulatory document REGDOC-2.3.3, Periodic Safety Reviews. This Standard is consistent with the IAEA\'s Specific Safety Guide No. SSG-25, Periodic Safety Review for Nuclear Power Plants. 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. The CSA N286 Standard 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. Scope 1.1 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 This Standard provides specific requirements and guidance related to the PSR for a) development of the basis document; b) conducting reviews of modern requirements documents and practices; c) conducting safety factor reviews, including identification of safety factor findings; d) analysis 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) preparation of the integrated implementation plan (IIP) where the developed global issues are resolved into actions. 1.3 This Standard identifies required deliverables that will help facilitate achieving the objectives of the PSR process. 1.4 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 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.