CSA N290.0:26/CSA N290.2:26 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 N290.2:26 - Requirements for emergency core cooling systems of nuclear power plants Preface This is the third edition of CSA N290.2, Requirements for emergency core cooling 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) guidance has been provided for addressing the poised state of ECC following an initiation in an adjacent unit; 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 emergency core cooling (ECC) system for new and existing water-cooled nuclear power plants. 1.2 Inclusions This Standard also applies to all support systems required to ensure that the ECC system is able to maintain adequate heat transfer for as long as necessary to maintain the release of radioactive material within reference dose limits by limiting fuel failure. This Standard includes requirements for the layout of plant structures to provide a recovery flow path to the ECC pumps. 1.3 Companion standard This Standard outlines the specific requirements for ECC system, and is used in concert with CSA N290.0, which outlines general requirements for safety systems. 1.4 Use of the ECC system This Standard uses the term "ECC system" to refer to either a single system or multiple systems depending on the plant design. 1.5 Exclusions This Standard does not address the assessment of plant or system operation following beyond design basis accident (BDBA). Requirements and guidance regarding BDBA are provided in CSA N290.16. 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.