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.
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
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.
