前言:这是CSA N289的第三版。3、核电站抗震鉴定设计程序。它取代了2010年以同一标题出版的前一版，以及1981年以CANDU核电厂抗震鉴定设计程序为题出版的前一版。标题已经更改，以反映范围的变化，从只涉及CANDU®反应堆到包括任何核电站。注:CANDU（加拿大氘铀）是加拿大原子能有限公司（AECL）的注册商标。在CSA N289的整个版本中有许多变化。3.最重要的变化如下:根据概率地震危险性评估（PSHA）结果建立设计地面反应谱的过程，包括现场反应分析，已以更简洁的格式阐明，并与当前的良好实践保持一致。 对第7条“抗震设计标准”进行了修订和重组，以允许对核电厂（NPP）设计中需要解决的所有情况和所有结构、系统和部件（SSC）（包括“核”和“非核”SSC）提出一整套要求。标准中引入了关于土-结构相互作用（SSI）的新附录B（资料性附录），以及SSI分析的现行惯例。本标准正文与附录一致。该标准与最近发布的CSA集团标准、CNSC监管文件和行业文件保持一致。CSA N289系列标准中的标准是为了响应加拿大核设施相关公用事业和行业对适用于核电厂核结构、系统和部件（SSC）抗震设计和鉴定的标准文件的需求而制定的。 本标准的使用者应认识到，只有在加拿大核安全委员会（CNSC）或具有管辖权的适当机构（加拿大以外的国家）采用本标准时，本标准才具有法律效力。本标准的目的是提供要求，确保核SSC的设计和抗震鉴定采用符合质量和标准的分析技术，符合符合加拿大核安全理念所需的安全原则。CSA N289系列标准由五个标准组成。每个标准的一些目标总结如下:a）CSA N289。1-18，核电厂抗震设计和鉴定的一般要求——为基于核安全考虑确定需要抗震鉴定的结构和系统提供指南； b） CSA N289。2-10，核电厂抗震鉴定的地震动测定——确定特定场地的适当地震动参数；c） CSA N289。3-10，核电厂抗震鉴定设计程序——提供设计要求、标准和分析方法，以确定分析中使用的设计反应谱和地震动时程；ii）为需要抗震鉴定的结构、系统和组件（SSC）以及支架制定设计标准；Andii）进行地震分析，包括土壤-结构相互作用的影响。d） CSA N289。4-12，核电厂结构、系统和部件抗震鉴定试验程序——通过试验方法提供特定部件和系统抗震鉴定的设计要求和方法； ande）CSA N289。5-12，核电厂和核设施的地震仪器要求——制定地震仪器要求，以及地震事件前后结构和系统的地震相关检查要求。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CSA集团的其他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CSA N286的一般要求；然而，它可能会为这些要求提供更具体的指导。 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》及其法规的规定。因此，加拿大核安全委员会（CNSC）可以对本标准中规定的要求施加附加要求。范围1。1本标准规定了试验的要求、标准、分析方法和设计程序 a） 确定分析中使用的设计反应谱和地震动时程；b） 为需要抗震鉴定的结构、系统和组件（SSC）以及支架制定设计标准；进行地震分析，包括土-结构相互作用的影响。 1.2本标准适用于需要通过分析方法进行抗震鉴定的核电厂SSC（见CSA N289.1）。本标准也可适用于运行机构或有管辖权的机构（AHJ）认为适当时可能不需要明确抗震鉴定的SSC。1.3本标准可适用于《核安全与控制法》管辖下的其他核设施。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 third edition of CSA N289.3,Design procedures for seismic qualification of nuclear power plants. It supersedes the previous edition, published in 2010 under the same title, and 1981 under the titleDesign Procedures for Seismic Qualification of CANDU Nuclear Power Plants. The title has been changed to reflect a scope change, from addressing only CANDU® reactors to including any nuclear power plant.Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).There have been many changes throughout this edition of CSA N289.3; the most significant changes are as follows:The process for establishing design ground response spectra from probabilistic seismic hazard assessment (PSHA) results, including site response analysis, has been articulated in a more concise format and aligned with current good practices.Clause 7, Seismic design criteria, has been revised and re-structured to allow for a complete set of requirements for all cases and all structures, systems, and components (SSCs) that need to be addressed in nuclear power plant (NPP) design (including both "nuclear" and "non-nuclear" SSCs).A new Annex B (informative) on soil structure interaction (SSI) has been introduced in the Standard with the current established practices for SSI analysis. The body of this Standard is aligned with the Annex.The Standard has been aligned with recently published CSA Group standards, CNSC Regulatory Documents, and industry documents.Standards in the CSA N289 series of Standards are developed in response to a recognition by the utilities and industries concerned with nuclear facilities in Canada of a need for the documentation of standards applicable to the seismic design and qualification of nuclear structures, systems, and components (SSCs) of nuclear power plants. Users of this Standard should recognize that it has the force of law only when adopted by the Canadian Nuclear Safety Commission (CNSC) or the appropriate authority having jurisdiction (in countries other than Canada).The purpose of this Standard is to provide requirements that ensure that the nuclear SSCs are designed and seismically qualified in a manner using analytical techniques that meet a quality and standard commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.The CSA N289 series of Standards consists of five Standards. Some of the objectives of each Standard are summarized as follows:a) CSA N289.1-18,General requirements for seismic design and qualification of nuclear power plants— to provide guidelines for identifying structures and systems requiring seismic qualification based on nuclear safety considerations;b) CSA N289.2-10,Ground motion determination for seismic qualification of nuclear power plants— to determine the appropriate seismic ground motion parameters for a particular site;c) CSA N289.3-10,Design procedures for seismic qualification of nuclear power plants— to provide design requirements, criteria, and methods of analysis fori) determining the design response spectra and ground motion time-histories to be used in the analysis;ii) establishing design criteria for structures, systems and components (SSCs), and supports that require seismic qualification; andiii) performing seismic analyses, including the effects of the soil-structure-interaction.d) CSA N289.4-12,Testing procedures for seismic qualification of nuclear power plant structure, systems, and components— to provide design requirements and methods for seismic qualification of specific components and systems by testing methods; ande) CSA N289.5-12,Seismic instrumentation requirements for nuclear power plants and nuclear facilities— to establish the requirements for seismic instrumentation and for seismic-related inspection of structures and systems before and after a seismic event.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.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 Regulations. The Canadian Nuclear Safety Commission (CNSC) can therefore impose additional requirements to those specified in this Standard.Scope1.1This Standard specifies the requirements, criteria, methods of analysis, and design procedures for a) determining the design response spectra and ground motion time-histories to be used in the analysis;b) establishing design criteria for structures, systems and components (SSCs), and supports that require seismic qualification; andc) performing seismic analyses, including the effects of the soil-structure-interaction.1.2This Standard applies to SSCs in nuclear power plants that require seismic qualification by analytical methods (see CSA N289.1). This Standard may also be applied to SSCs that might not require explicit seismic qualification as deemed appropriate by the operating organization or by authorities having jurisdiction (AHJ).1.3This Standard may be applied, as appropriate, to other nuclear facilities under the jurisdiction of the Nuclear Safety and Control Act.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.