N290。0-17-核电厂安全系统的一般要求本标准为CSA N290的第二版。0，核电厂安全系统的一般要求。它取代了2011年出版的前一版。本标准是关于核电厂反应堆控制系统、安全系统和仪表的一系列标准之一。本版本的变化包括以下内容:a）增加了新的要求、指南和建议，以解决在应对福岛第一核电站事件中吸取的经验教训。本版本已更新，以与CNSC REGDOC保持一致- 2.5.2. b） 与行业进一步分类和细分超设计基准事故制度的倡议一致，本标准已更新，以解决适用于安全系统的设计扩展条件。超出设计基准事故的其他要求见CSA N290。16.c）CSA N290的资料性附录A。1已移至本版附录B，因为它更普遍地适用于安全系统。d） 除了CSA N290。2和CSA N290。3.本标准的新版也是CSA N290的配套文件。1.本版本提高了CSA N290之间联系的清晰度。 0和这些标准。还对安全系统和对安全重要的系统进行了说明。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。范围1。1本标准适用于新建和现有水冷核电厂安全系统的设计、鉴定、安装、运行、维护、检查和文件编制。注:本标准也适用于与本标准涵盖的安全系统相关的安全支持系统。1.2本标准规定了安全系统的一般要求。本标准是与CSA N290配合使用的配套文件。1，CSA N290。2和CSA N290。3，概述了系统的具体要求。 1.3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。1.4在本标准中，“应考虑”或“应考虑”是指用户评估影响并记录任何决定。注:示例可能包括无操作、操作程序和设计特征--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------N290。2-17-核电厂应急堆芯冷却系统的要求本标准为CSA N290的第二版。 2、核电厂应急堆芯冷却系统的要求。它取代了2011年出版的前一版。本标准是关于核电厂反应堆控制系统、安全系统和仪表的一系列标准之一。本版本的变化包括以下内容:a）增加了新的要求、指南和建议，以解决在应对福岛第一核电站事件中吸取的经验教训。本版本已更新，以使标准与CNSC REGDOC-2.5.2保持一致。b） 本标准前一版的第5.14条被重新定位到本版的信息性附录中，以在不限制未来设计选项的情况下为碎片拦截器的设计提供指导。 根据运行经验，本版本中包含了关于解决水锤问题的设计考虑的进一步指南。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。范围1。1本标准适用于新建和现有水冷核电厂应急堆芯冷却（ECC）系统的设计、鉴定、安装、运行、维护、检查和文件编制。1.2本标准还适用于所有必要的支持系统，以确保ECC系统能够在必要的时间内保持足够的热传递，从而通过限制燃料失效将放射性物质的释放保持在参考剂量限值内。本标准包括为ECC泵提供回收流道的电厂结构布局要求。 1.3本标准概述了ECC系统的具体要求，并与CSA N290配合使用。概述了安全系统的一般要求。1.4本标准使用术语“ECC系统”指单个系统或多个系统，具体取决于电厂设计。1.5本标准不涉及超越设计基准事故后的电厂或系统运行评估。CSA N290中提供了有关超设计基准事故的要求和指南。16.1.6在本标准中，“应”用于表示要求，即用户有义务满足的条款，以符合本标准； “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。1.7在本标准中，“应考虑”或“应考虑”是指用户评估影响并记录任何决定。 注:示例可能包括无操作、操作程序和设计特征。

N290.0-17 - General requirements for safety systems of nuclear power plantsPrefaceThis is the second edition of CSA N290.0, General requirements for safety systems of nuclear power plants. It supersedes the previous edition published in 2011. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants. Changes to this edition include the following: a) New requirements, guidance, and recommendations have been added to address lessons learned in response to the Fukushima Daiichi event. This edition has been updated for alignment with CNSC REGDOC-2.5.2. b) Consistent with industry initiatives to further classify and subdivide the beyond design basis accident regime, this Standard has been updated to address design extension conditions to the extent they are applicable to safety systems. Other requirements for beyond design basis accidents are addressed in CSA N290.16. c) The informative Annex A from CSA N290.1 has been moved to Annex B in this edition, as it is more generally applicable to safety systems. d) In addition to CSA N290.2 and CSA N290.3, the new edition of this Standard is also a companion document to CSA N290.1. This edition provides improved clarity regarding the link between CSA N290.0 and these Standards. Clarification has also been provided to distinguish between a safety system from a system that is important to safety. 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.Scope1.1 This Standard applies to the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for new and existing water-cooled nuclear power plants. Note: This Standard also applies to safety support systems as they relate to the safety systems covered by this Standard. 1.2 This Standard provides the general requirements for safety systems. This Standard is a companion document used in concert with CSA N290.1, CSA N290.2, and CSA N290.3, which outline system-specific requirements. 1.3 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. 1.4 In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions. Note: Examples can include no action, operating procedures, and design features. --------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------N290.2-17 - Requirements for emergency core cooling systems of nuclear power plantsPrefaceThis is the second edition of CSA N290.2, Requirements for emergency core cooling systems of nuclear power plants. It supersedes the previous edition published in 2011. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants. Changes to this edition include the following: a) New requirements, guidance, and recommendations have been added to address lessons learned in response to the Fukushima Daiichi event. This edition has been updated to align the Standard with CNSC REGDOC-2.5.2. b) Clause 5.14 of the previous edition of this Standard was relocated to an informative Annex of this edition to provide guidance for debris interceptor design without constraining future design options. Further guidance regarding design considerations for addressing water hammer were included in this edition based on operating experience. 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.Scope1.1 This Standard applies the design, qualification, installation, operation, maintenance, inspection, and documentation of the emergency core cooling (ECC) system for new and existing water-cooled nuclear power plants. 1.2 This Standard also applies to all support systems required to ensure that the ECC system is able to maintain adequate heat transfer for as long as necessary to maintain the release of radioactive material within reference dose limits by limiting fuel failure. This Standard includes requirements for the layout of plant structures to provide a recovery flow path to the ECC pumps. 1.3 This Standard outlines the specific requirements for ECC system, and is used in concert with CSA N290.0, which outlines general requirements for safety systems. 1.4 This Standard uses the term "ECC system" to refer to either a single system or multiple systems depending on the plant design. 1.5 This Standard does not address the assessment of plant or system operation following beyond design basis accident. Requirements and guidance regarding beyond design basis accident are provided in CSA N290.16. 1.6 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. 1.7 In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions. Note: Examples can include no action, operating procedures, and design features.