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Reliability and maintenance programs for nuclear power plants 核电站的可靠性和维护计划
发布日期: 2019-06-01
范围1。1反应堆和其他潜在源本标准提供了水冷核电站SSC的要求和指南。本标准适用于与a)水冷动力反应堆相关的SSC;和b)向环境释放大量放射性物质的其他潜在来源。注:1)本标准可用于指导水冷核电站以外的核设施,例如研究反应堆。2) “向环境释放大量放射性物质的其他潜在来源”包括湿储存间和干用燃料储存设施。 1.2公共安全和其他目的本标准的要求仅适用于以下一个或两个条件适用的安全相关SSC:a)SSC故障导致核事故;(b)SSC故障会削弱缓解或监测核事故的能力。注:1)在加拿大,核事故被划分为预期运行事故、设计基准事故和超出设计基准事故,包括设计扩展条件和严重事故。 2) 例如,本标准的要求不适用于SSC的功能,其目的是保护工人免受常规或核危害;b) 防止、缓解或监测水冷核电站常规运行产生的废水;c) 满足保障要求;预防或减轻恶意行为。1.3新建和现有设施本标准适用于新建和现有水冷核电站。注:1)“现有核电站”是指2019年之前初始许可的核电站。 2) “新核电站”是指2018年后最初获得许可的核电站。3)本标准指出,要求可能仅适用于新核电站或现有核电站。1.4单反应堆和多反应堆设施本标准适用于带有一个或多个水冷动力反应堆的核电站。1.5事故前条件本标准仅限于在核事故发生前进行的活动。注:例如,本标准不涉及事故后恢复措施或严重事故管理指南。 1.6遵守其他标准1。6.1本标准的要求不取代其他CSA标准的要求。注:例如,本标准第6.5条中的要求不会取代CSA N285中的检验和测试要求。0; 和b)CSA N293。1.6.2本标准的要求可能会增加其他CSA标准的要求。注:例如,如果消防系统被确定为对安全重要的系统(见第5条),则本标准的要求可能会增加CSA N293的要求。 1.7本标准中的术语“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。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。
Scope1.1 Reactors and other potential sourcesThis Standard provides the requirements and guidance for SSC at a water-cooled NPP. This Standard applies to SSC associated witha) water-cooled power reactors; andb) other potential sources of significant radioactive releases to the environment.Notes:1) This Standard may be used to provide guidance for nuclear facilities other than water-cooled NPPs, e.g., research reactors.2) "Other potential sources of significant radioactive releases to the environment" include wet storage bays and dry used fuel storage facilities.1.2 Public safety and other purposesThe requirements of this Standard apply only to safety-related SSC for which one or both of the following conditions apply:a) the failure of the SSC results in a nuclear incident; orb) the failure of the SSC impairs the ability to mitigate or monitor a nuclear incident.Notes:1) In Canada, nuclear incidents have been classified as anticipated operational occurrences, design basis accidents, and beyond design basis accidents, including design extension conditions and severe accidents.2) The requirements of this Standard do not apply, for example, to functions of SSC whose purpose is toa) protect workers from conventional or nuclear hazards;b) prevent, mitigate or monitor effluents resulting from the routine operation of water cooled NPPs;c) satisfy safeguards requirements; ord) prevent or mitigate malevolent acts.1.3 New and existing facilitiesThis Standard applies to both new and existing water-cooled NPPs.Notes:1) "Existing NPPs" refers to NPPs initially licensed before 2019.2) "New NPPs" refers to NPPs initially licensed after 2018.3) This Standard notes where requirements might apply only to a new NPP or only to an existing NPP.1.4 Single and multi-reactor facilitiesThis Standard applies to NPPs with one or more water-cooled power reactors.1.5 Pre-incident conditionsThis Standard is limited to activities that are performed prior to the initiation of a nuclear incident.Note: This Standard does not address, for example, post-accident recovery actions or severe accident management guidance.1.6 Compliance with other standards1.6.1The requirements of this Standard do not supersede requirements in other CSA Standards. Note: For example, the requirements in Clause 6.5 of this Standard do not supersede the inspection and testing requirements ina) CSA N285.0; andb) CSA N293.1.6.2The requirements of this Standard might augment the requirements of other CSA Standards.Note: For example, if a fire protection system is identified as a system important to safety (see Clause 5), then the requirements of this Standard might augment the requirements of CSA N293.1.7 TerminologyIn 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. In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions.
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发布单位或类别: 加拿大-加拿大标准协会
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