前言:这是CSA N287的第一版。8、核电站混凝土安全壳结构的老化管理。本标准的目的是提供老化管理要求，以确保混凝土安全壳结构在其生命周期的所有不同阶段满足其功能和性能要求，并确保新的混凝土安全壳结构在设计和施工阶段解决老化问题。注:在生命周期的不同阶段，混凝土安全壳结构的功能和性能要求可能不同。 在加拿大，CNSC REGDOC 2.6.3提供了管理核电站（NPP）结构、系统和组件老化的监管要求。CSA N287系列标准中的标准是针对加拿大与核电厂结构相关的公用事业和行业认识到，核电厂混凝土安全壳结构的设计、施工和测试需要一致的标准而制定的。CSA N287系列标准由八个标准组成。每项标准的目标总结如下: a） CSA N287。1-14，核电厂混凝土安全壳结构的一般要求，规定了指定为安全壳类的核电厂混凝土安全壳结构的设计、施工、测试和调试的一般要求，并针对混凝土组件和部件的所有者、设计师、制造商、制造商和施工人员；b） CSA N287。2-08，CANDU核电厂混凝土安全壳结构的材料要求，规定了混凝土安全壳结构所用材料的要求； c） CSA N287。3-14，《核电厂混凝土安全壳结构设计要求》规定了混凝土安全壳结构的设计要求；d） CSA N287。4-09，CANDU核电厂混凝土安全壳结构的施工、制造和安装要求，规定了适用于指定为CANDU核电厂安全壳部件、零件和附件的安全壳系统混凝土安全壳结构的施工、制造和安装要求；e） CSA N287。5-11《核电厂混凝土安全壳结构的检查和试验要求》规定了适用于参与核电厂混凝土安全壳结构零件或组件施工、制造或安装的任何组织的检查和试验要求； f） CSA N287。6-11《核电厂混凝土安全壳结构的运行前验证和泄漏率测试要求》规定了在首次临界之前，通过演示证明混凝土安全壳结构的设计和施工在质量和性能方面符合CSA N287规定要求的要求。6包括调试泄漏率目标；g） CSA N287。7-08《CANDU核电厂混凝土安全壳结构在役检查和试验要求》规定了统一要求，通过系统和定期检查，结构和泄漏- 通过达到CSA N287的规定要求，可以评估混凝土安全壳结构的紧密完整性。7包括运行泄漏率目标；和h）CSA N287。8，《核电厂混凝土安全壳结构的老化管理》，为核电厂混凝土安全壳结构及其组件提供老化管理要求，并针对业主/运营商、设计师、制造商、制造商和施工人员。在编制这些标准时，委员会决定尽可能使用现有标准、规范和其他参考资料。 本标准的使用者应注意，加拿大核设施的设计、制造、施工、调试、运行和退役应遵守《核安全与控制法》及其配套法规的规定。因此，除本标准中规定的要求外，加拿大核安全委员会可能会提出其他要求。CSA N系列标准为核设施和活动的管理提供了一套相互关联的要求。CSA N286为管理层提供全面指导，以制定和实施健全的管理实践和控制措施，而其他CSA核标准则提供支持管理体系的技术要求和指导。 本标准与CSA N286一致，不重复其一般要求；然而，它可能会为这些要求提供更具体的指导。范围:1.1本标准规定了核电厂混凝土安全壳结构及其部件的老化管理要求，适用于业主/运营商、设计师、制造商、制造商和施工人员。注:适用时，本标准可为其他混凝土结构的老化管理提供指导。1.2本标准规定了现有混凝土安全壳结构的老化管理要求，以应对新出现的挑战，并确保现有混凝土安全壳结构及其组件在其生命周期的所有不同阶段满足其功能和性能要求。 1.3本标准规定了新混凝土安全壳结构的老化管理要求，以确保a）在设计和施工阶段解决老化问题；安全壳结构及其部件在其生命周期的所有不同阶段都满足其功能和性能要求。1.4在本标准中，“应”用于表示要求，即用户为遵守本标准而有义务满足的规定；“应该”用于表示建议或建议但不需要的建议；“可”用于表示一个选项或在标准范围内允许的选项。 注释随附条款不包括要求或替代要求；随附条款的注释的目的是将解释性或信息性材料与文本分开。表和图的注释被视为表或图的一部分，可以作为要求编写。附件被指定为规范性（强制性）或信息性（非强制性）以定义其应用。

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; andh) 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 theNuclear 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:1.1This 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.1.2This 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.1.3This Standard provides requirements for aging management of new concrete containment structures to ensure thata) aging is addressed during design and construction phases; andb) containment structures and their components satisfy their functional and performance requirements in all different phases of their life cycle.1.4In 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.