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商品级物项适用性确认标准体系研究
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  • 英文篇名:Study on the Standard System of Commercial Grade Dedication
  • 作者:何志军 ; 宋磊
  • 英文作者:HE Zhijun;SONG Lei;China Nuclear Power Engineering Co.,Ltd.;
  • 关键词:核电厂 ; 商品级物项 ; 商品级物项适用性确认 ; 标准体系 ; 法规 ; 导则 ; 技术评价
  • 英文关键词:Nuclear power plant;;Commercial grade item(CGI);;Commission grade dedication(CGD);;Standard system;;Codes;;Guidelines;;Technical evaluation
  • 中文刊名:ZDYB
  • 英文刊名:Process Automation Instrumentation
  • 机构:中国核电工程有限公司;
  • 出版日期:2019-06-20
  • 出版单位:自动化仪表
  • 年:2019
  • 期:v.40;No.454
  • 语种:中文;
  • 页:ZDYB201906015
  • 页数:6
  • CN:06
  • ISSN:31-1501/TH
  • 分类号:72-77
摘要
目前,新建和在役核电厂大量使用商品级物项代替核安全相关物项。为确保商品级物项(CGI)在核电厂核安全相关场合能够满足要求的安全功能,需要对商品级物项执行技术评价和验收过程。通过对商品级物项适用性确认(CGD)标准体系的起源、地位、作用和现状进行分析,以及对CGD相关法规、导则、标准和技术报告等文件进行归纳和总结,梳理出CGD标准体系的层次关系。重点研究了各层次主要标准的内容和相互联系。探讨了CGD标准体系在我国核电设计和运行过程中的适用性,对我国核电标准体系进一步健全和完善提出了建议。该研究对着手制定CGD标准,具有一定的体系规划启发和借鉴意义。
        At present,a large number of new and in-service nuclear power plants use commercial grade items(CGI) instead of nuclear safety-related items.In order to ensure that commercial grade items can meet the requirements of nuclear safety-related applications in nuclear power plants,technical evaluation and acceptance of commercial grade items are required.Through the analysis of the origin,status,function and current situation of the standard system of commercial grade dedication(CGD),and the summary of the relevant CGD regulations,guidelines,standards and technical reports,the hierarchical relationship of CGD standard system is sorted out,and the contents and interrelations of main standards at all levels are emphatically studied.The applicability of CGD standard system in the process of nuclear power design and operation in China is discussed.Suggestions are put forward for further improvement and perfection of China's nuclear power standard system,which will provide some inspiration and reference for planning of CGD standard system.
引文
[1] 毋琦,任莉华,李世欣,等.核电厂数字化设备的商品级评定[J].自动化仪表,2015,36(7):58-62.
    [2] U.S.NRC.Reporting of defects and noncompliance:10 CFR 21[S].2015.
    [3] U.S.NRC.Quality assurance criteria for nuclear power plants and fuel reprocessing plants:Appendix B to 10 CFR 50 [S].2007.
    [4] U.S.NRC.Quality assurance program criteria (design and construction):RG 1.28 [S].2010.
    [5] U.S.NRC.Criteria for use of computers in safety systems of nuclear power plants:RG 1.152 [S].2011.
    [6] EPRI.Guideline for the acceptance of commercial-grade items in nuclear safety-related applications:EPRI TR-3002002982 [R].2014.
    [7] EPRI.Guideline for sampling in the commercial-grade Item acceptance process:EPRI TR-017218 [R].1999.
    [8] EPRI.Guidelines for safety classification of systems,components,and parts used in nuclear power plant applications:EPRI NP-6895 [R].1991.
    [9] EPRI.Guidelines for the technical evaluation of replacement items in nuclear power plants:EPRI TR-1008256 [R].2006.
    [10]EPRI.Guidelines for the technical evaluation of replacement items in nuclear power plants:EPRI NP-6406 [S].1999.
    [11]中国国家标准化管理委员会.核电厂安全系统中数字计算机的适用准则:GB/T 13629-2008 [S].2008.
    [12]国家能源局.核电厂安全级电气设备零部件更换要求:NB/T 2008-2012 [S].2012.

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