N290。0-11，核电厂安全系统的一般要求参考:这是CSA N290的第一版。0，核电厂安全系统的一般要求。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。范围:1.1本标准涵盖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。1.2本标准规定了安全系统的一般要求。本标准是CSA N290的配套文件。2和N290。3.概述了具体要求。1.3在CSA标准中，“应”用于表示要求，即用户有义务满足的条款，以符合标准；“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-------------------------------------------------------------------------------------------------------N290。3-16核电厂安全壳系统的要求参考:这是CSA N290的第二版。3、核电站安全壳系统的要求。它取代了2011年出版的第一版。这个新版本是根据从福岛事故中吸取的教训而开发的，专门针对一个帖子- 事故设计压力b）通风c）氢气浓度控制要求d）多机组站/事件本新版已与CNSC REGDOC-2.5.2和CSA N290一致。16.本标准作为核电厂安全壳系统的通用标准编写，并确立了核安全设计、鉴定、安装、运行、维护、检查和文件编制。本标准的使用者应注意，加拿大核设施的选址、设计、制造、施工、安装、调试、运行和退役应遵守《核安全与控制法案》及其法规。加拿大核安全委员会可能会对本标准中规定的要求施加额外的要求。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。 范围:1.1本标准适用于现有和新建水冷核电厂的安全壳系统。注:1）“现有核电站”指2011年之前获得初始运行许可的核电站。2）新建核电站和现有核电站的要求可能有所不同。如果新厂房和现有厂房的要求不同，则明确说明不同之处。1.2本标准作为CSA N290的配套文件编写。概述了安全系统的一般要求。本标准及其配套文件规定了安全壳系统的设计、鉴定、安装、操作、维护、检查和文件要求。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、设计特征。

N290.0-11,General requirements for safety systems of nuclear power plantsPreface:This is the first edition of CSA N290.0,General requirements for safety systems of nuclear power plants. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.Scope:1.1This Standard covers the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for a water-cooled nuclear power plant.1.2This Standard provides the general requirements for the safety systems. This Standard is a companion document of CSA N290.2 and N290.3, which outline specific requirements.1.3In CSA standards, "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.-------------------------------------------------------------------------------------------------------N290.3-16Requirements for the containment system of nuclear power plantsPreface:This is the second edition of CSA N290.3,Requirements for the containment system of nuclear power plants. It supersedes the first edition, published in 2011.This new edition was developed in response to the lessons learned from the Fukushima accident to specifically addressa) post-accident design pressuresb) ventingc) hydrogen gas concentration control requirementsd) multi-unit stations/eventsThis new edition has been made to align with CNSC REGDOC-2.5.2 and CSA N290.16.This Standard has been written as a general standard for the containment system of nuclear power plants, and establishes the nuclear safety design, qualification, installation, operation, maintenance, inspection, and documentation.Users of this Standard are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to theNuclear Safety and Control Actand itsRegulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard.This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.Scope:1.1This Standard applies to the containment system of existing and new water-cooled nuclear power plants.Notes:1)"Existing nuclear power plants" refers to those licensed for initial operation prior to 2011.2)The requirements for new builds and existing plants might differ. Where requirements differ for new builds and existing plants, the difference is explicitly stated.1.2This Standard was written as a companion document to CSA N290.0, which outlines general requirements for safety systems.This Standard, with its companion document, specifies requirements for the design, qualification, installation, operation, maintenance, inspection, and documentation of a containment system.1.3In 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.1.4In 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, design features.