CSA N290.0:26/CSA N290.1:24 PACKAGE

Abstract

CSA N290.0:26 - General requirements for safety systems of nuclear power plants Preface This is the third edition of CSA N290.0, General requirements for safety systems of nuclear power plants . It supersedes the previous editions published in 2017 and 2011. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants. The following are the major changes to this edition: a) clause titles have been added at all levels; b) definitions have been updated to further align with CSA program and CNSC REGDOC-3.6 terminology; c) Annex A, Guidance on plant life maintenance, has been removed and pointers to CSA N290.9 and CSA N290.20 have been added, as applicable; and d) content has been updated to reflect changes to referenced CSA and external standards. 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 reflects the operating experience of the Canadian nuclear power industry. 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 Requirements for Emergency Core Cooling Systems of Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation for Nuclear Power Plants, and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 Application This Standard applies to the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for new and existing water-cooled nuclear power plants. Note: This Standard also applies to safety support systems as they relate to the safety systems covered by this Standard. 1.2 Companion documents This Standard provides the general requirements for safety systems. This Standard is a companion document used in concert with CSA N290.1, CSA N290.2, and CSA N290.3, which outline system-specific requirements. 1.3 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. -------------------------------------------------------------------------------------------------------------------------------- CSA N290.1:24 - Requirements for the shutdown systems of nuclear power plants Preface This is the third edition of CSA N290.1, Requirements for the shutdown systems of nuclear power plants . It supersedes the previous editions published in 2013 and 1980. Changes to this edition include the following: a) alignment with new publications including CNSC REGDOC-2.5.2, CNSC REGDOC-2.6.1, and the CSA N290A series of Standards; b) alignment with the latest CSA nuclear program common definitions and alignment of terminology used throughout this Standard; c) incorporation of overpressure protection requirements from CSA N285.0 into a new informative Annex A; d) removal of duplications between this Standard and the companion CSA N290.0 (e.g., removal of the informative Annex on failure mode considerations, equipment sharing requirements, and cyber security requirements); and e) addition of clause titles and the restructuring of the Standard to improve application and usability. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants. CSA N290.0 provides the general requirements for safety systems. CSA N290.0 is a companion document that outlines system-specific requirements and is used in concert with CSA N290.2, CSA N290.3, and this Standard. The CSA N-Series Standards provides 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. 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. This Standard was prepared by the Subcommittee on Requirements for the Shutdown Systems of Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, Instrumentation for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 Application This Standard applies to the design, procurement, installation, commissioning, operation, testing, and maintenance requirements of reactor shutdown systems (SDSs), based on insertion of a neutron-absorbent material in the core, for existing and new water-cooled nuclear power plants (NPPs). Notes: 1) "Existing nuclear power plants" refers to NPPs in service prior to 2024. 2) The requirements for new plants and existing plants might differ. Where requirements differ for new plants and existing plants, the differences are explicitly stated. 1.2 Companion standard This Standard is written as a companion document to CSA N290.0, which provides general requirements for the NPP safety systems, including the reactor SDS. This Standard and its companion CSA N290.0 provide the requirements for the reactor SDS. 1.3 Inclusions This Standard uses the term SDS, which includes the following functions: detection, trip, actuation, and means of shutdown (MSD). 1.4 Exclusions This Standard does not apply to a) small modular reactors (SMRs); and Note: SMRs are fission reactors with a power level less than approximately 300 MWe per module. b) non-water-cooled reactors. 1.5 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.