CSA N287.1:24 PDF

CSA N287.1:24 PDF

Preface

This is the fifth edition of CSA N287.1, General requirements for concrete containment structures for nuclear power plants . It supersedes the previous editions, published in 2014, 1993, 1982, and 1977. The major changes to this edition include the following: • terminologies have been clarified by modifying the definitions to align with other CSA nuclear standards; • alignment with other CSA nuclear standards has been improved; • personnel qualification requirements have been clarified; • further guidance on trending has been added; • documentation requirements have been clarified; • interface with CSA N286, which expanded from quality assurance to management of all business objectives including quality, has been improved; and • accessibility has been improved. This Standard provides general requirements to ensure that the design, construction, and testing of concrete containment structures will meet a quality and standard commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy. 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 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 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 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: • 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; • CSA N287.2, Material requirements for concrete containment structures for nuclear power plants, specifies requirements for materials used for concrete containment structures; • CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; • CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for nuclear power plants; • 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; • 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; • CSA N287.7, In-service examination and testing requirements for concrete containment structures for 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 • 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. 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 General Requirements for Concrete Containment Structures for Nuclear Power Plants, under the jurisdiction of the Technical Committee on Concrete Containment and Safety Related Structures for Nuclear Power Plants and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.

Scope

1.1 General

This Standard provides general requirements for the design, fabrication, construction, installation, examination, and commissioning as well as the in-service examination, testing, and aging management of concrete containment structures for nuclear power plants. It is directed to the owners/operating organizations, designers, manufacturers, fabricators, and constructors of the concrete containment structures and their elements. 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). This Standard does not address requirements for containment components. Note: The requirements for containment components are addressed in CSA N285.0/N285.6 Series. Notes: 1) This Standard is applicable to new nuclear power plants’ concrete containment structures to be built in Canada. Application of the Standard to concrete containment structures to be built outside Canada is subject to approval of 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. 2) The requirements of the CSA N287 series of Standards generally exceed the requirements of the National Building Code of Canada. 3) In Canada, CNSC REGDOC-2.5.2 provides the regulatory requirements for the design of new containment structures.

1.2 Responsibilities

This Standard defines the responsibilities of organizations and individuals with respect to the functions mentioned in Clause 1.1 together with the pertinent documentation required as a statement of quality assurance. Note: A basic interaction organizational chart and basic interaction chart for documentation are provided in Annex A.

1.3 Interface

This Standard is used in concert with other standards in the CSA N287 series of Standards.

1.4 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.