前言:这是CSA N289的第三版。2、核电站抗震鉴定的地震动测定。它取代了2010年和1981年出版的前两个版本。该版本的主要变化包括:第4条已修订，以解决微震监测和诱发地震活动。对第5条进行了修订和重组，以提供更多关于震源特征描述和地震动模型（GMM）的细节，并对两者进行区分，并解决与两者相关的权重问题。对第6条进行了修订，以解决近断层场地的地震危险性结果，同时考虑地震的潜在损害，以及情景地震的发展。引入了一项新的第7条，即考虑当地现场条件的地震危险评估，以提供一种程序来解释当地条件和各种不确定性来源。 引入了新的第8条，即独立同行审查，以提高地震危险性评估和评估的可信度。新的资料性附录（附录B）用于处理厂址记录的地震运动。另一个新的信息性附录（附录C）是参考书目，包括与本标准范围相关的最新参考文献和出版物。本标准与最近发布的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）或相关监管机构（加拿大以外的国家）采用本标准时，本标准才具有法律效力。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》提供了基于核安全考虑确定需要抗震鉴定的结构和系统的指南；b） CSA N289。2:21，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。3:20，《核电厂抗震鉴定设计程序》提供了确定设计反应谱和地震动时间的设计要求、标准和分析方法- 分析中使用的历史记录；ii）为SSC和需要抗震鉴定的支架制定设计标准；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》提供了通过试验方法对特定部件和系统进行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》规定了地震仪器的要求，以及地震事件前后结构和系统的地震相关检查的要求。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，它可以为这些需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本标准描述了获取必要的地震学和地质信息所需的调查，以确定地震地面运动，该地震地面运动将用于安全相关核电厂结构、系统和部件（SSC）的地震鉴定，以及二次地震影响的可能性（例如:。 g、 ，海啸、地震、火山作用、边坡失稳、地表断层、地表失稳和大坝溃决），可能对电厂安全或运行产生直接或间接影响。注:1）本标准为一系列地震危险性结果奠定了基础，这些结果可用作CSA N289系列标准的输入。本标准未规定设计中使用的地震动参数；b） 概率水平；（orc）要达到的信心程度。2） 本标准中规定的调查应定期更新，以反映获得的知识和现代要求。调查可以独立进行，也可以作为定期安全审查的一部分进行（参考REGDOC-2.3.3、CSA N289.1和CSA N290.18）。1.2本标准用于确定北美东部低至中度地震危险地区的地震动，与加拿大现有核电厂附近的水平相当。 在地震危险性较高的地区，由于近断层和其他超出本标准范围的影响，强震震动的评估可能更加复杂。因此，虽然本标准的规定可适用于任何核电站现场，但对于高地震危险现场，可能需要额外的规定。注:关于高地震危险场所附加规定的指南可从IAEA特定安全指南SSG-9和其他国家的相关规范中获得。1.3本标准适用于《加拿大政府安全与控制法案》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 N289.2,Ground motion determination for seismic qualification of nuclear power plants.It supersedes the previous editions, published in 2010 and 1981.The major changes to this edition include the following:Clause 4 has been revised to address microearthquake monitoring and induced seismicity.Clause 5 has been revised and restructured to provide more details on and differentiate between seismic source characterization and ground motion models (GMMs), and to address the weights associated with both.Clause 6 has been revised to address seismic hazard results for near-fault sites, while considering damage potential of earthquakes, and the development of scenario earthquakes.A new Clause 7, on evaluation of seismic hazards considering local site conditions, has been introduced to provide a procedure to account for local conditions and for various sources of uncertainty.A new Clause 8, an independent peer review, has been introduced to enhance the confidence level of seismic hazard assessment and evaluations.A new informative annex (Annex B) has been introduced for processing earthquake motions recorded at the plant site.Another new informative annex (Annex C), a bibliography, has been introduced to include recent references and publications associated with the scope of this Standard.This 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 regulatory body (in countries other than Canada).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, provides guidelines for identifying structures and systems requiring seismic qualification based on nuclear safety considerations;b) CSA N289.2:21,Ground motion determination for seismic qualification of nuclear power plants, determines the appropriate seismic ground motion parameters for a particular site;c) CSA N289.3:20,Design procedures for seismic qualification of nuclear power plants, provides 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 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 structures, systems and components, provides 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, establishes 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 can 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.Scope:1.1This Standard describes the investigations required to obtain the seismological and geological information necessary to determine the seismic ground motion that will be used in seismic qualification of safety-related nuclear power plant structures, systems, and components (SSCs), and the potential for secondary earthquake effects (e.g., tsunami, seiche, volcanism, slope instability, surface faults, surface instability, and dam failures) that can have a direct or indirect effect on plant safety or operation.Notes:1) This Standard establishes the basis for a family of seismic hazard results that can be used as input to CSA N289 Series of Standards. This Standard does not specifya) ground motion parameters to be used in design;b) probability level; orc) degree of confidence to be achieved.2) The investigations specified in this Standard should be updated periodically to reflect gained knowledge and modern requirements. The investigations may be conducted independently or as part of the periodic safety review (refer to REGDOC-2.3.3, CSA N289.1, and CSA N290.18).1.2This Standard was developed for the determination of ground motions for Eastern North American regions of low to moderate seismic hazard, comparable to the levels near Canada's existing nuclear power plants. In regions of higher seismic hazard, the assessment of strong earthquake shaking can be more complex due to near-fault and other effects that are beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any nuclear power plant site, additional provisions might be required for high seismic hazard sites.Note:Guidance regarding additional provisions for high seismic hazard sites may be obtained from IAEA Specific Safety Guide SSG-9, and relevant codes of other countries.1.3This Standard may be applied, as appropriate, to other nuclear facilities under the jurisdiction of the Government of Canada'sNuclear 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.