RG1.26 核电厂物项质量组分级及其标准 2007

REGULATORY GUIDE 1.26
QUALITY GROUP CLASSIFICATIONS AND STANDARDS FOR WATER-，STEAM-，AND RADIOACTIVE-WASTE-CONTAINING COMPONENTS OF NUCLEAR POWER PLANTS
核电厂物项质量组分级及其标准（2007）RG1.26
General Design Criterion 1, “Quality Standards and Records,” as set forth i n Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), “Licensing of Production and Utilization Facilities” (Ref. 1), requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Under 10 CFR 50.55a, “Codes and Standards,” certain systems and components of boiling- and pressurized-water-cooled nuclear power reactors must be designed, fabricated, erected, and tested in accordance with the standards for Class 1, 2, and 31 components given in Section III, “Nuclear Power Plant Components,” of the American Society of Mechanical Eng ineers (ASME) Boiler and Pressure V essel Code (Ref. 2) or equivalent quality standards. This guide describes a quality classification system related to specified national standards that may be used to determine quality standards acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for satisfying General Design Criterion 1 for other safety-related components containing water, steam, or radioactive material in light-water-cooled nuclear power plants.
一般设计标准1，“质量标准和记录”，载列在附录A，“通用设计标准核电厂”，标题10，第50，联邦法规法典（10 CFR第50部分），“许可生产和利用设施“（参考文献1），需要的结构，系统和安全重要部件的设计，制造，架设，测试，质量标准要执行安全功能的重要性相称。

根据10 CFR50.55a，“规范和标准”，某些系统和部件的沸点和加压水冷核电反应堆必须设计，制造，架设，测试按照标准的1级，2，3个组分，在第三节，“核电厂零组件，”美国机械工程师学会（ASME）锅炉及压力容器规范（参考文献2）或同等质量标准。

本指南介绍了相关的质量分级制度，指定的国家标准，可用于确定质量标准，美国核管理委员会（NRC）的工作人员接受其他与安全相关的部件含有水，蒸汽满足一般设计标准1，或光水冷核电厂的放射性物质。

In editions of the ASME Boiler and Pressure V essel Code published before 1971, Section III uses the terms Class A, Class B, and Class C in lieu of Class 1, Class 2, and Class 3.
第三节ASME锅炉和压力容器规范1971年以前出版的版本中，使用的术语类A，B类，C类代替1级，2级和3级。

This regulatory guide contains information collections that are covered by the requirements of 10 CFR Part 50 which the Office of Management and Budget (OMB) approved under OMB control number 3150-0011. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
这种监管指南包含所涵盖的信息集合，由10 CFR第50部分的管理和预算办公室（OMB）批准根据OMB控制号3150-0011的要求。

NRC的既不执行也不赞助任何单位，一个人是不允许回应，信息收集的
要求或规定，除非请求文件显示当前有效的OMB控制编号。

In the early 1970s, the NRC staff developed a quality classification system to provide licensees with guidance for satisfying General Design Criterion 1. The system consists of four quality groups, A through D; methods for assigning components to those quality groups; and specific quality standards applied to each quality group. When the NRC issued Revision 2 of this guide in June 1975 and Draft Revision 3 for public comment in February 1976, 10 CFR 50.55a required only that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested to the highest available national standards; this corresponded to the quality standards for Quality Group A of the NRC system. On March 15, 1984, the Commission published a final rule (Ref. 3) amending 10 CFR 50.55a to incorporate by reference the criteria in Section III of the ASME Code, as they relate to the design and fabrication of Class 2 and 3 components (Quality Group B and C components, respectively).
NRC的工作人员在20世纪70年代初，制定了质量分级制度，持牌人提供指导，为满足一般设计标准1。

该系统由四个质量组，A至D;质量分组要素设定的方法，以及具体的质量标准。

当NRC发布本指南的第2次修订在1975年6月和1976年2月，征求公众意见的修订草案3，只需要10 CFR50.55a反应堆冷却剂压力边界的组件被设计，制造，架设，测试到可用的最大国家标准;符合质量标准，质量A组的NRC系统。

1984年3月15日，该委员会发表了最终规则（注释3）修正10 CFR50.55a将参考在第三节ASME规范的标准，因为它们涉及到的设计和制造的2级和3个组成部分（质量B组和C元件，分别）。

Because the quality group classification system is well-established, this Revision 4 of Regulatory Guide 1.26 retains the method described in previous versions for determining acceptable quality standards for Quality Group B, C, and D components. Other systems not covered by this guide, such as instrument and service air, diesel engines and their generators and auxiliary support systems, diesel fuel, emergency and normal ventilation, fuel handling, and radioactive waste management systems,2 should be designed, fabricated, erected, and tested to quality standards commensurate with the safety function to be performed. The evaluation to establish the quality group classification of these other systems should consider the guidance provided in Regulatory Positions 1 and 2of this guide.
因为质量组的分类系统是行之有效的，所以监管指南1.26（第4版）决定保留之前版本中质量B组，C和D的分类。

其他系统不包括本指南，如仪器和服务的空气，柴油发动机和发电机和辅助支持系统，柴油，紧急情况和正常通风，燃料处理，放射性废物管理系统，应设计，制作，搭建起，与要执行的安全功能的质量标准进行测试。

评估这些系统建立质量组分类应考虑在监管位置1和2OF的本指南提供的指导。

The Quality Group B standards given in Table 1 of this guide should be applied to water- and steam-containing pressure vessels, heat exchangers (other than turbines and condensers), storage tanks,piping, pumps, and valves that are either (1) part of the reactor coolant pressure boundary defined in 10 CFR 50.2 but excluded from the requirements of 10 CFR 50.55a3 pursuant to paragraph (c)(2) of that section, or (2) not part of the reactor coolant pressure boundary but part of the Following:
本指南表1中给出的质量B组的标准，应适用于水和蒸汽的压力容器，换热器（除了涡轮机和冷凝器），储罐，管道，泵，阀门，他们是反应堆冷却剂的一部分——10 CFR50.2，但除10 CFR50.55a3根据条（c）款（2），也适用于（2）不属于反应堆冷却剂压力边界的范围，但属于下列情形的：
(a) systems or portions of systems important to safety that are designed for (i) emergency core cooling, (ii) postaccident containment heat removal, or (iii) Postaccident fission product removal
（一）安全重要系统，是专为系统或部分（一）应急堆芯冷却，（二）事故后安全壳排热，或（iii）事故后的裂变产物去除
(b) systems or portions of systems important to safety that are designed for (i) reactor shutdown or (ii) residual heat removal
（二）系统或部分系统重要的安全设计（I）停堆或（ii）余热排出
(c) those portions of the steam systems of boiling-water reactors extending from the outermost containment isolation valve up to but not including the turbine stop and bypass valves,5 and connected piping up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation; alternatively, for boiling-water reactors containing a shutoff valve (in addition to the two containment isolation valves) in the main steamline and the main feedwater line, those portions of the steam and feedwater systems extending from the outermost containment isolation valves up to and including the shutoff valve or the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation
（三）沸水反应堆的蒸汽系统的那些部分延伸的从最外层的安全壳隔离阀，但不包括涡轮机停止阀和旁路阀，连接管道包括第一阀是常闭的，或能够自动闭合装置可替代地，在所有的反应器正常操作模式;包含在主蒸汽管线和主给水管道截止阀（除了两个安全壳隔离阀）的沸水反应堆，蒸汽和给水系统的那些部分从所述最外层壳隔离阀包括截止阀或第一阀是常闭的或能够自动闭合装置的正常的反应器操作的所有模式期间
(d) those portions of the steam and feedwater systems of pressurized-water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves, and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation
（四）的加压水反应堆的蒸汽和给水系统的那些部分延伸出来并包括蒸汽发生器的二次侧，并包括最外层的安全壳隔离阀，连接管道，包括第一阀（包括一个安全或溢流阀），要么是常闭或能够自动关闭，在所有反应堆正常运行模式
(e) systems or portions of systems that are connected to the reactor coolant pressure
boundary and are not capable of being isolated from the boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure
（五）系统或部分系统被连接到反应堆冷却剂压力边界和不能够被孤立的边界由两个阀门，其中每一个可以是常闭的，或能够自动闭合装置在正常反应器操作的所有模式
备注：system5：The turbine stop valve and turbine bypass valve, although not included in Quality Group B, should be subjected to a quality assurance program at a level generally equivalent to Quality Group B.
涡轮截止阀和汽轮机旁路阀，虽然不包括在质量B组，应受到质量保证水平相当于B组质量
Quality Group C
The Quality Group C standards given in Table 1 of this guide should be applied to water-, steam-, and radioactive-waste-containing pressure vessels; heat exchangers (other than turbines and condensers); storage tanks; piping; pumps; and valves that are not part of the reactor coolant pressure boundary or included in Quality Group B but part of the following:
质量C组本指南表1中给出的标准，应适用于水，蒸汽，和含放射性废物的压力容器，换热器（除涡轮机和冷凝器之外）;储罐，管道，泵和阀门，它们不属于反应堆冷却剂压力边界或质量B组，但部分包括以下：
(a) cooling water and auxiliary feedwater systems or portions of those systems5 important to safety that are designed for (i) emergency core cooling, (ii) postaccident containment heat removal, (ii) postaccident containment atmosphere cleanup, or (iv) residual heat removal from the reactor and from the spent fuel storage pool (including primary and secondary cooling systems), although Quality Group B includes portions of those systems that are required for their safety functions and that (i) do not operate during any mode of normal reactor operation and (ii) cannot be tested adequately.
（a）冷却水和辅助给水系统或部分这些系统重要的安全设计（i）应急堆芯冷却，（ii）事故后壳散热，（iii）事故后壳大气清理，或（iv）余热去除从反应堆和乏燃料贮存池（包括小学和中学的冷却系统），虽然质量B组包括部分系统，其安全功能所必需的，并认为（i）不工作在任何模式下的正常反应器及（ii）不能被充分测试
(b) cooling water and seal water systems or portions of those systems important to safety that are designed for the functioning of components and systems important to safety, such as reactor coolant pumps, diesels, and the control room
（b）冷却水和密封水系统或那些安全重要系统组件按照安全重要系统相关要求设计，如，如反应堆冷却剂泵、柴油机、主控室。

(c) systems or portions of systems that are connected to the reactor coolant pressure boundary and are capable of being isolated from that boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure6
（c）连接到反应堆冷却剂压力边界的系统，并且能够从该边界被隔离了阀门，其中每一个可以是常闭或能够自动闭合装置在正常反应器操作的所有模式的系统或部分的
(d) systems, other than radioactive waste management systems, not covered by Regulatory Positions 2(a) through 2(c) (above) that contain or may contain radioactive material and whose postulated failure would result in conservatively calculated potential offsite doses [using meteorology as re commended in Regulatory Guide 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors” (Ref. 5), and Regulatory Guide 1.4, “Assumptions Used for Evaluating the Potential Radiolo gical Consequences of a Loss-of-Coolant Accident for Pressurized-Water Reactors” (Ref. 6)] that exceed 0.5 rem to the whole body or its equivalent to any part of the body; only single component failures need be assumed for those systems located in Seismic Category I structures, and no credit should be taken for automatic isolation from other components in the system or for treatment of released material, unless the isolation or treatment capability is designed to the appropriate seismic and quality group standards and can withstand loss of offsite power and a single failure of an active component,
（d）放射性废物管理系统以外的系统，不包括由监管仓2（a）至2（C）（以上），其中包含或使用所推荐的气象可能含有放射性物质，其假设的失败会导致保守计算潜在的异地剂量[1.3管理指南，“假设用于评估潜在放射性后果丢失的沸水反应堆失水事故”（注释5），用于评估潜在放射性后果的监督管理指南1.4“的假设需假定那些位于地震分类系统的压水反应堆“（参考文献6）]超过0.5雷姆的整个身体或身体的任何部分相当于只有单一组件故障丢失事故始发应自动隔离老子结构，没有信用在系统中的其它构件或释放出来的材料的处理，除非使用了隔离或治疗能力被设计成适当的地震，高质量的产品组的标准，并能承受丧失外电和活性组分的单点故障，
Quality Group D
The Quality Group D standards gi v en in Table 1 of thi s guide should be applied to waterand steam-containing components that are not part of the reactor coolant pressure boundary or included in Quality Groups B or C, but are part of systems or portions of systems that contain or may contain radioacti v e material.
质量D组
质量D组本指南表1中给出的标准，应适用于水和蒸汽的设备，它们不属于反应堆冷却剂压力边界的一部分，或B或C组，但系统或部分可能含有放射性物质。

D. IMPLEMENTATION
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff’s plans for using this regulatory guide. No backfitting is intended or approved in . Except in those cases in which an applicant or licensee proposes or has previously established an accep table alternative method for complying with specified portions of the NRC’s regulations, the NRC staff will use the methods described in this guide to evaluate (1) submittals in connection with applications for construction permits, standard plant design certifications, operating licenses, early site permits, and combined licenses; and (2) submittals from operating reactor licensees who voluntarily propose to initiate system modifications if there is a clear nexus between the
proposed modifications and the subject for which guidance is provided herein.
本节的目的是提供信息，以申请人和被许可人使用这种监管指南的有关的NRC人员的计划。

不能擅自变更，除非申请人或持牌建议或以前已经建立了一个可以接受的替代方法符合NRC的规定的指定部分，NRC工作人员将使用本指南中描述的方法评价与应用（1）提交文件施工许可证，标准厂房的设计认证，经营许可证，早站点许可证，以及联合许可证和经营反应堆持牌人自愿提出启动系统的修改，如果有一个明确的修改建议和主题之间的关系（2）提交文件本文提供指导。

REGULATORY ANALYSIS / BACKFIT ANALYSIS
The regulatory analysis and backfit analysis for this regulatory guide are available in Draft Regulatory Guide DG-1152, “Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-con taining Components of Nuclear Power Plants” (Ref. 13). The NRC issued DG-1152 in November 2006 to solicit public comment on the draft of this Revision 4 of Regulatory Guide 1.26.
监管分析/不大的改形分析
这个监管指导的监管分析和不大的改形分析可在法规草案指南DG-1152“质量组分类和标准的水，蒸汽和含放射性废物的组成部分”核电厂（参考文献13）。

NRC发出DG-1152于2006年11月，征求公众意见，对修订草案41.26监管指南。