CSA N287.3:25

Preface This is the fifth edition of CSA N287.3, Design requirements for concrete containment structures for nuclear power plants. It supersedes the previous editions, published in 2014, 1993, 1982, and 1978. This Standard reflects Canadian regulatory requirements, the operating experience of the Canadian nuclear industry, and international practices. The Standard was originally written for CANDU® reactors but can be used for other concrete containment structures as applicable. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). The major changes to this edition include the following: a) updates to definitions for consistency with other CSA standards; b) addition of Clause 1.2 for applicability of standard; c) addition of Clause 4.6 for monitoring instrumentation; d) addition of Clause 4.7 on aging management; e) clarifications regarding what is the responsibility of "designer" versus the responsibility of "owner/ operating organization"; f) updates to requirements to include SOE considerations; g) improved alignment with CSA N290.3 and CSA N290.16; h) improved alignment with CNSC REGDOC-2.5.2; i) improved alignment with CSA A23.3; j) clarification in Clause 8.2.2 related to application of strength reduction factors; k) update to Clause 14.3.3 related to the design of shear lugs; l) update to Annex E related to loads, load combinations, acceptance criteria, and structural integrity margin assessment for design extension conditions; and m) accessibility was improved. This Standard specifies requirements for the design of concrete containment structures and addresses their beyond design basis assessment. The CSA N-series of 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 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 is part of the CSA N287 series of Standards, which provides the requirements for concrete containment structures for nuclear power plants. These Standards were initiated in response to a recognition by the utilities and industries concerned with nuclear power plant structures in Canada of a need for consistent standards for the design, construction, and testing of concrete containment structures for nuclear power plants. The CSA N287 series of Standards consists of eight Standards. The objectives of each Standard are summarized as follows: a) CSA N287.1, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, commissioning, and in-service examination and testing of concrete containment structures for nuclear power plants and is directed to the owners/operating organizations, designers, manufacturers, fabricators, and constructors; b) CSA N287.2, Material requirements for concrete containment structures nuclear power plants, specifies requirements for materials used for concrete containment structures; c) CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; d) CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants; e) CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures for nuclear power plants; f) CSA N287.6, Pre-operational proof and leakage rate testing requirements for concrete containment structures for nuclear power plants, specifies requirements for proof by demonstration, before first criticality, that the design and construction of a concrete containment structure are satisfactory with respect to quality and performance as demonstrated by achieving the specified requirements of CSA N287.6, including commissioning leakage rate target; g) CSA N287.7, In-service examination and testing requirements for concrete containment structures nuclear power plants, specifies uniform requirements whereby, through systematic and periodic examination, the structural and leak-tight integrity of concrete containment structures can be assessed as demonstrated by achieving the specified requirements of CSA N287.7, including the operational leakage rate target; and h) CSA N287.8, Aging management for concrete containment structures for nuclear power plants, provides aging management requirements for concrete containment structures for nuclear power plants and is directed to the owners/operating organizations, designers, manufacturers, fabricators, and constructors. In general, the design of concrete containment structures is governed by the applicable requirements of CSA A23.3, Design of concrete structures. CSA N287.3 gives the additional or modified requirements that are specific to concrete containment structures. 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 Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard. This Standard was prepared by the Subcommittee on Design Requirements for Concrete Containment Structures for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Concrete Containment and Safety-Related Structures and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 General This Standard specifies requirements for the design of concrete containment structures, and addresses their beyond design basis assessment. Concrete containment structures include the following structural and non-structural elements: a) concrete; b) reinforcement (pre-stressed and non-pre-stressed); c) steel (e.g., liner, embedded parts, anchors); d) nonmetallic liners and coating systems; e) joint sealants and water stops; and f) elements necessary to support the containment structure (e.g., foundations). 1.2 Application This Standard is used in concert with the other standards of the CSA N287 series of Standards. This Standard is applicable to new nuclear power plants’ concrete containment structures in Canada, subject to approval by the authority having jurisdiction (AHJ). The application of the Standard to existing or operating nuclear power plants is as agreed upon by the owner/operating organization and the AHJ. 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 (nonmandatory) to define their application.