N290.0-17 - General requirements for safety systems of nuclear power plants
Preface
This is the second edition of CSA N290.0, General requirements for safety systems of nuclear power plants. It supersedes the previous edition published in 2011. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.
Changes to this edition include the following:
a) New requirements, guidance, and recommendations have been added to address lessons learned in response to the Fukushima Daiichi event. This edition has been updated for alignment with CNSC REGDOC-2.5.2.
b) Consistent with industry initiatives to further classify and subdivide the beyond design basis accident regime, this Standard has been updated to address design extension conditions to the extent they are applicable to safety systems. Other requirements for beyond design basis accidents are addressed in CSA N290.16.
c) The informative Annex A from CSA N290.1 has been moved to Annex B in this edition, as it is more generally applicable to safety systems.
d) In addition to CSA N290.2 and CSA N290.3, the new edition of this Standard is also a companion document to CSA N290.1. This edition provides improved clarity regarding the link between CSA N290.0 and these Standards. Clarification has also been provided to distinguish between a safety system from a system that is important to safety.
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 may provide more specific direction for those requirements.
Scope
1.1
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
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
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.
1.4
In this Standard, shall be considered or shall consider means that the user evaluates the impact and documents any decisions.
Note: Examples can include no action, operating procedures, and design features.
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CSA N290.3:22 - Requirements for the containment system of nuclear power plants
Preface
This is the third edition of CSA N290.3, Requirements for the containment system of nuclear power plants. It supersedes the previous editions published in 2016 and 2011.
Changes to this edition include the following:
a) update of requirements to ensure alignment with other recently issued CSA standards, specifically the CSA N290.0 companion Standard and CSA N285.0/N285.6;
b) update of requirements to ensure alignment with IAEA SSG-53;
c) update of definitions for alignment with CSA common definitions;
d) new informative annexes (Annexes C and D) have been added. Annex C captures information on multi-unit CANDU negative pressure containment (NPC) system, and Annex D identifies additional documents that may be consulted for further information on requirements for the containment system of CANDU;
e) normative Annex A figures and associated text have been updated to improve clarity and alignment with current practice;
f) informative Annex B figures and associated text have been updated to improve clarity; and
g) clause titles have been added, and the Standard has been restructured to improve application and usability.
CSA N290.0 provides the general requirements for safety systems. CSA N290.0 is a companion document which outlines system-specific requirements and is used in concert with CSA N290.1, CSA N290.2, and this Standard.
This Standard has been written as a general standard for the containment system of nuclear power plants, and establishes the nuclear safety design, qualification, installation, operation, maintenance, inspection, and documentation.
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.
This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.
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 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 Requirements for the Containment System of Nuclear Power Plants, under the jurisdiction of the Technical Committee on Reactor Control Systems, Safety Systems, and Instrumentation of Nuclear Power Plants, and the Standards Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.
Scope
1.1 Application
This Standard applies to the containment system of existing and new water-cooled nuclear power plants.
Notes:
1) Existing nuclear power plants refers to those licensed for initial operation prior to 2011.
2) The requirements for new builds and existing plants might differ. Where requirements differ for new builds and existing plants, the difference is explicitly stated.
3) For supplementary information on multi-unit CANDU NPC systems, refer to Annex C.
1.2 Companion document
This Standard was written as a companion document to CSA N290.0, which outlines general requirements for safety systems.
This Standard, with its companion document, specifies requirements for the design, qualification, installation, operation, maintenance, inspection, and documentation of a containment system.
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.
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