CSA N287.8:15 (R2020)

Preface This is the first edition of CSA N287.8, Aging management for concrete containment structures for nuclear power plants. The purpose of this Standard is to provide aging management requirements to ensure that concrete containment structures satisfy their functional and performance requirements in all different phases of their life cycle and to ensure that for new concrete containment structures, aging is addressed during design and construction phases. Note: The functional and performance requirements of concrete containment structures might be different in different phases of the life cycle. In Canada, CNSC REGDOC 2.6.3 provides the regulatory requirements for managing the aging of structures, systems and components of a nuclear power plant (NPP). The Standards in the CSA N287 Series of 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 N287.1-14, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, and commissioning of concrete containment structures for nuclear power plants designated as class containment and is directed to the owners, designers, manufacturers, fabricators, and constructors of the concrete components and parts; b) CSA N287.2-08, Material requirements for concrete containment structures for CANDU nuclear power plants, specifies requirements for materials used in concrete containment structures; c) CSA N287.3-14, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; d) CSA N287.4-09, Construction, fabrication, and installation requirements for concrete containment structures for CANDU nuclear power plants, specifies construction, fabrication, and installation requirements that apply to concrete containment structures of a containment system designated as class containment components, parts, and appurtenances for CANDU nuclear power plants; e) CSA N287.5-11, 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 parts or components of concrete containment structures for nuclear power plants; f) CSA N287.6-11, 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 N287.7-08, In-service examination and testing requirements for concrete containment structures for CANDU 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 and their components for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors. In the preparation of these Standards, it was the decision of the Committee to make use of existing standards, codes, and other reference material wherever possible. 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. Thus, requirements additional to those specified in this Standard may be imposed by the Canadian Nuclear Safety Commission. 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 its generic requirements; however, it may provide more specific direction for those requirements. Scope 1.1 This Standard provides aging management requirements for concrete containment structures and their components for nuclear power plants and is directed to owners/operators, designers, manufacturers, fabricators, and constructors. Note: This Standard may provide guidance for aging management of other concrete structures where applicable. 1.2 This Standard provides requirements for aging management of existing concrete containment structures to address emerging challenges and ensure that existing concrete containment structures and their components satisfy their functional and performance requirements in all different phases of their life cycle. 1.3 This Standard provides requirements for aging management of new concrete containment structures to ensure that a) aging is addressed during design and construction phases; and b) containment structures and their components satisfy their functional and performance requirements in all different phases of their life cycle. 1.4 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.

Preface This is the first edition of CSA N287.8, Aging management for concrete containment structures for nuclear power plants. The purpose of this Standard is to provide aging management requirements to ensure that concrete containment structures satisfy their functional and performance requirements in all different phases of their life cycle and to ensure that for new concrete containment structures, aging is addressed during design and construction phases. Note: The functional and performance requirements of concrete containment structures might be different in different phases of the life cycle. In Canada, CNSC REGDOC 2.6.3 provides the regulatory requirements for managing the aging of structures, systems and components of a nuclear power plant (NPP). The Standards in the CSA N287 Series of 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 N287.1-14, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, and commissioning of concrete containment structures for nuclear power plants designated as class containment and is directed to the owners, designers, manufacturers, fabricators, and constructors of the concrete components and parts; b) CSA N287.2-08, Material requirements for concrete containment structures for CANDU nuclear power plants, specifies requirements for materials used in concrete containment structures; c) CSA N287.3-14, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; d) CSA N287.4-09, Construction, fabrication, and installation requirements for concrete containment structures for CANDU nuclear power plants, specifies construction, fabrication, and installation requirements that apply to concrete containment structures of a containment system designated as class containment components, parts, and appurtenances for CANDU nuclear power plants; e) CSA N287.5-11, 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 parts or components of concrete containment structures for nuclear power plants; f) CSA N287.6-11, 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 N287.7-08, In-service examination and testing requirements for concrete containment structures for CANDU 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 and their components for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors. In the preparation of these Standards, it was the decision of the Committee to make use of existing standards, codes, and other reference material wherever possible. 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. Thus, requirements additional to those specified in this Standard may be imposed by the Canadian Nuclear Safety Commission. 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 its generic requirements; however, it may provide more specific direction for those requirements. Scope 1.1 This Standard provides aging management requirements for concrete containment structures and their components for nuclear power plants and is directed to owners/operators, designers, manufacturers, fabricators, and constructors. Note: This Standard may provide guidance for aging management of other concrete structures where applicable. 1.2 This Standard provides requirements for aging management of existing concrete containment structures to address emerging challenges and ensure that existing concrete containment structures and their components satisfy their functional and performance requirements in all different phases of their life cycle. 1.3 This Standard provides requirements for aging management of new concrete containment structures to ensure that a) aging is addressed during design and construction phases; and b) containment structures and their components satisfy their functional and performance requirements in all different phases of their life cycle. 1.4 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.