ImageVerifierCode 换一换
格式:PDF , 页数:36 ,大小:230.76KB ,
资源ID:430928      下载积分:5000 积分
快捷下载
登录下载
邮箱/手机:
温馨提示:
如需开发票,请勿充值!快捷下载时,用户名和密码都是您填写的邮箱或者手机号,方便查询和重复下载(系统自动生成)。
如填写123,账号就是123,密码也是123。
特别说明:
请自助下载,系统不会自动发送文件的哦; 如果您已付费,想二次下载,请登录后访问:我的下载记录
支付方式: 支付宝扫码支付 微信扫码支付   
注意:如需开发票,请勿充值!
验证码:   换一换

加入VIP,免费下载
 

温馨提示:由于个人手机设置不同,如果发现不能下载,请复制以下地址【http://www.mydoc123.com/d-430928.html】到电脑端继续下载(重复下载不扣费)。

已注册用户请登录:
账号:
密码:
验证码:   换一换
  忘记密码?
三方登录: 微信登录  

下载须知

1: 本站所有资源如无特殊说明,都需要本地电脑安装OFFICE2007和PDF阅读器。
2: 试题试卷类文档,如果标题没有明确说明有答案则都视为没有答案,请知晓。
3: 文件的所有权益归上传用户所有。
4. 未经权益所有人同意不得将文件中的内容挪作商业或盈利用途。
5. 本站仅提供交流平台,并不能对任何下载内容负责。
6. 下载文件中如有侵权或不适当内容,请与我们联系,我们立即纠正。
7. 本站不保证下载资源的准确性、安全性和完整性, 同时也不承担用户因使用这些下载资源对自己和他人造成任何形式的伤害或损失。

版权提示 | 免责声明

本文(ANSI ANS 3.2-2012 Managerial administrative and quality assurance controls for the operational phase of nuclear power plants《核电站运作阶段的管理 行政 以及质量保证控制》.pdf)为本站会员(registerpick115)主动上传,麦多课文库仅提供信息存储空间,仅对用户上传内容的表现方式做保护处理,对上载内容本身不做任何修改或编辑。 若此文所含内容侵犯了您的版权或隐私,请立即通知麦多课文库(发送邮件至master@mydoc123.com或直接QQ联系客服),我们立即给予删除!

ANSI ANS 3.2-2012 Managerial administrative and quality assurance controls for the operational phase of nuclear power plants《核电站运作阶段的管理 行政 以及质量保证控制》.pdf

1、ANSI/ANS-3.2-2012managerial, administrative, and qualityassurance controls for the operationalphase of nuclear power plantsANSI/ANS-3.2-2012ANSI/ANS-3.2-2012American National StandardManagerial, Administrative, and QualityAssurance Controls for the OperationalPhase of Nuclear Power PlantsSecretariat

2、American Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-3.2Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved March 20, 2012by theAmerican National Standards Institute, Inc.AmericanNationalStandard

3、Designation of this document as an American National Standard attests thatthe principles of openness and due process have been followed in the approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under the proce

4、dures of the Standards Commit-tee of the American Nuclear Society; these procedures are accredited by theAmerican National Standards Institute, Inc., as meeting the criteria forAmer-ican National Standards. The consensus committee that approved the stan-dard was balanced to ensure that competent, co

5、ncerned, and varied interestshave had an opportunity to participate.An American National Standard is intended to aid industry, consumers, gov-ernmental agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notprecl

6、ude anyone from manufacturing, marketing, purchasing, or using prod-ucts, processes, or procedures not conforming to the standard.By publication of this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The c

7、ontent of this standard reflects acceptable practice at the time ofits approval and publication. Changes, if any, occurring through developmentsin the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany t

8、ime in accordance with established procedures. Users of this standardare cautioned to determine the validity of copies in their possession and toestablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individu

9、al or by any ad hoc group of individuals.Responses to inquiries about requirements, recommendations, and0or permis-sive statements i.e., “shall,” “should,” and “may,” respectively! should be sentto the Standards Department at Society Headquarters. Action will be taken toprovide appropriate response

10、in accordance with established procedures thatensure consensus.Comments on this standard are encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USACopyright 2012 by American Nuclear Society. All rights re

11、served.Any part of this standard may be quoted. Credit lines, should read “Extracted fromAmerican National Standard ANSI0ANS-3.2-2012 with permission of the publisher,the American Nuclear Society.” Reproduction prohibited under copyright conventionunless written permission is granted by the American

12、 Nuclear Society.Printed in the United States of AmericaInquiryRequestsThe American Nuclear Society ANS! Standards Committee will provide re-sponses to inquiries about requirements, recommendations, and0or permissivestatementsi.e., “shall,” “should,” and “may,” respectively!in American NationalStand

13、ards that are developed and approved by ANS. Responses to inquiries willbe provided according to the Policy Manual for the ANS Standards Committee.Nonrelevant inquiries or those concerning unrelated subjects will be returnedwith appropriate explanation. ANS does not develop case interpretations ofre

14、quirements in a standard that are applicable to a specific design, operation,facility, or other unique situation only, and therefore is not intended for genericapplication.Responses to inquiries on standards are published in ANSs magazine, NuclearNews, and are available publicly on the ANS Web site

15、or by contacting the ANSStandards Administrator.InquiryFormatInquiry requests must include the following:1! the name, company name if applicable, mailing address, and telephonenumber of the inquirer;2! reference to the applicable standard edition, section, paragraph, figure and0ortable;3! the purpos

16、es of the inquiry;4! the inquiry stated in a clear concise manner;5! a proposed reply, if the inquirer is in a position to offer one.Inquiries should be addressed toAmerican Nuclear SocietyATTN: Standards Administrator555 N. Kensington AvenueLa Grange Park, IL 60526or standardsans.orgForewordThis Fo

17、reword is not a part of American National Standard “Managerial, Administrative,and Quality Assurance Controls for the Operational Phase of Nuclear Power Plants,”ANSI0ANS-3.2-2012.!Preparation of the first edition of this standard commenced in 1969 prior to theestablishment of formal quality assuranc

18、e requirements for the operation ofnuclear power plants. Historically, the administrative controls section of FacilityOperating License Technical Specifications had contained provisions for meetingmany of the requirements that subsequently became identified with qualityassurance i.e., the managerial

19、 and administrative controls that assure that thequality designed into the facility is maintained! during operation. It was theoriginal intent of the standard to define administrative controls for this purpose.The subcommittee that developed the initial version of this standard had amembership whose

20、 experience was primarily in power reactor operation, and itdeveloped a document that would provide guidance for administrative controlsover activities associated with the operation of nuclear power plants.At the sametime, ASME Subcommittee N45.2, Nuclear Quality Assurance Standards, wasdeveloping q

21、uality assurance standards related to design, construction, and op-eration of nuclear facilities.The U.S. Nuclear Regulatory CommissionNRC!issued its Safety Guide 33nowRegulatory Guide 1.33, Rev. 2, “Quality Assurance Program Requirements Op-eration!” Feb. 1978!RG 1.33!#, endorsing Draft 8 of ANS-3.

22、2 which laterbecame ANSI N18.7-1972, “Administrative Controls and Quality Assurance forthe Operational Phase of Nuclear Power Plants”! and ANSI0ASME N45.2-1971,“Quality Assurance Program Requirements for Nuclear Power Plants.” Becauseof this dual endorsement, the two committees attempted to develop

23、a singlestandard. The result of that effort was ANSI N18.7-1976, which was later redes-ignated ANS-3.2, i.e., ANSI N18.7-1976 ANS-3.2!, “Administrative Controls andQuality Assurance for the Operational Phase of Nuclear Power Plants,” whichwas subsequently endorsed by RG 1.33 for use by nuclear power

24、 plants duringthe operation phase.Following the Three Mile Island Unit 2 accident in 1979, the American NuclearSociety ANS! revised ANSI N18.7-1976 ANS-3.2! to incorporate the adminis-trative “lessons learned” into the standard and published it as ANSI0ANS-3.2-1982, “Administrative Controls and Qual

25、ityAssurance for the Operational Phaseof Nuclear Power Plants,” to clearly focus ANSI0ANS-3.2-1982 on operationaland administrative quality controls. At the same time, ASME issued ANSI0ASME NQA-1-1979, “QualityAssurance Program Requirements for Nuclear PowerPlants,” to focus clearly on design and co

26、nstruction applications of quality as-surance. ANSI0ANS-3.2-1982 and ANSI0ASME NQA-1-1979 superseded severalof the ANSI0ASME N45.2 standards, which had previously been incorporated byreference into ANSI N18.7-1976 ANS-3.2!.ANSI0ASME NQA-l-1983 and ANSI0ASME NQA-la-1983 Addenda, “Quality As-surance P

27、rogram Requirements for Nuclear Power Plants,” were subsequentrevisions of ANSI0ASME NQA-1-1979 and were endorsed by Regulatory Guide1.28, Rev. 3, “Quality Assurance Program Requirements Design and Construc-tion!”Aug. 1985!. TheANS-3.2 editions were never endorsed by the NRC througha revision to RG

28、1.33, and the industry continued to utilize ANSI N18.7-1976ANS-3.2! as the endorsed standard.SinceANSI0ANS-3.2-1982 was published, the industry moved progressively closerto an all-operating reactor environment in the 1980s and 1990s with little designand construction activities during that time.ANSI

29、0ANS-3.2-1988, “AdministrativeiControls and Quality Assurance for the Operational Phase of Nuclear PowerPlants,” recognized this fact and incorporated many changes to emphasize oper-ational aspects and performance-based quality assurance techniques.ANSI0ANS-3.2-1994, “Administrative Controls and Qua

30、lity Assurance for the OperationalPhase of Nuclear Power Plants,” continued the strong emphasis on this ap-proach. Again, ANSI0ANS-3.2-1982, ANSI0ANS-3.2-1988, and ANSI0ANS-3.2-1994 were not endorsed through a revision to RG 1.33, and existing power plantschose differing paths to revise the requirem

31、ents of existing quality standardsthat were endorsed by the NRC.Since there were few new quality assurance initiatives actively being pursued inthe late 1990s, a decision was made in 1999 to reaffirm ANSI0ANS-3.2-1994. Asefforts within the nuclear industry continue to redefine the approach to qualit

32、yassurance, including changes to enhance the efficiency and effectiveness of im-plementing 10 CFR 50, Appendix B Code of Federal Regulations, Title 10,“Energy,” Part 50, “Domestic Licensing of Production and Utilization Facilities,”Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and

33、 FuelReprocessing Plants”!, in nuclear plant operations, maintenance, and supportingactivities, the ANS-3.2 Working Group continued to work with the industry todevelop revisions of this standard.ANSI0ANS-3.2-2006, “Administrative Controls and Quality Assurance for theOperational Phase of Nuclear Pow

34、er Plants,” was a revision that changed ANS-3.2 to be more in line with the formatting of ANSI0ANS NQA-1-1994, “QualityAssurance Program for Nuclear Facilities,” and 10 CFR 50, Appendix B. It wasapparent that many of the requirements from ANSI0ANS NQA-1-1994 wereduplicated in ANSI0ANS-3.2-2006. The

35、working group modified the standard toprovide the proper emphasis on the difference between design0construction andoperations0administration but did not fully remove all duplication. Again, ANSI0ANS-3.2-2006 was not endorsed through a revision to RG 1.33.Over the years many of the operating plants h

36、ave shifted from utilizing ANSI0ASME N45.2-1971 to various versions of ANSI0ASME NQA-1. While the revi-sions to ANSI N18.7-1976 ANS-3.2! were ongoing, RG 1.33 was not revised, andthe industry continued to utilize ANSI N18.7-1976 ANS-3.2!. Over the yearsmany utilities utilized the NRC license and qua

37、lity assurance program changeprocess to apply alternate approaches to implement the guidance contained inRG 1.33.With the advent of utilities planning and licensing new facilities, there became aneed to develop license applications that committed to the latest endorsed ver-sions of the existing stan

38、dards. In preparing for licensing of new facilities, itbecame apparent that the basic quality assurance requirements that were re-ferred to in ANSI N18.7-1976 ANS-3.2! were outdated and current criteria hadbeen incorporated into ASME NQA-1. The NRC revised Regulatory Guide 1.28,Rev. 4, “Quality Assu

39、rance Program Criteria Design and Construction!” June2010!, to endorseANSI0ASME NQA-1-2008 and NQA-1a-2009Addenda, “QualityAssurance Requirements for Nuclear Facility Applications.” To ensure that therewas no duplication of the requirements contained in ANSI0ASME NQA-1-2008and NQA-1a-2009 Addenda an

40、d to ensure that the managerial and administra-tive controls necessary for the safe operation of the plant received the neededfocus, the working group developed a major revision to the standard that sepa-rated the quality assurance controls from the managerial and administrativecontrols. Since the c

41、ombination of ANSI0ASME NQA-1-2008 and NQA-1a-2009Addenda and ANSI0ANS-3.2-2012, “Managerial, Administrative, and Quality As-surance Controls for the Operational Phase of Nuclear Power Plants,” providesiithe quality assurance requirements and the managerial controls necessary forsafe operation of nu

42、clear facilities, the working group continued with the objec-tive to have ANS-3.2 supplement NQA-1 for operating plants. This industryguidance was fully coordinated with the ASME NQA-1 Standards Committee.ANSI0ANS-3.2-2012 continues to be based on the philosophy that the assuranceof quality is the r

43、esponsibility of the individual performing the task, thus assur-ing that quality is achieved and is not the sole responsibility of the formallyestablished quality assurance organizational group. Therefore, this standardfocuses on the managerial and administrative controls that support this philosoph

44、y.This standard might reference documents and other standards that have beensuperseded or withdrawn at the time the standard is applied. A statement hasbeen included in the references section that provides guidance on the use ofreferences.This standard does not incorporate the concepts of generating

45、 risk-informedinsights, performance-based requirements, or a graded approach to quality as-surance. The user is advised that one or more of these techniques could enhancethe application of this standard.This revised standard was prepared by the ANS-3.2 Working Group and re-viewed by the ANS-21 Subco

46、mmittee and the ANS Nuclear Facility StandardsCommittee NFSC!. At the time of the revision, the membership of the ANS-3.2Working Group was the following:M. E. Smith Chair!, Nuclear Innovations North AmericaC. L. Eldridge Vice Chair!, Furgo William Lettis compli-ance with regulations specifying radia

47、tion doseand contamination criteria; or plant reliability.Applicable portions of this standard may alsobe used for activities at reactors specificallyexcluded in the scope.This standard is intended to be implementedtogether with the applicable elements of ANSI0ASME NQA-1-2008 and NQA-1a-2009Addenda2

48、#. ANSI0ASME NQA-1-2008 and NQA-1a-2009 Addenda is the standard that providesthe appropriate quality assurance require-ments for all phases. This standard providesthe managerial and administrative require-ments needed to assure safe operation of afacility.2 DefinitionsThe terms defined in ANSI0ASME

49、NQA-1-2008 and NQA-1a-2009 Addenda apply to thisstandard and are not duplicated herein.experiments: performance of those plant op-erations executed under controlled conditionsin order to establish characteristics or valuesnot previously known.1!Numbers in brackets refer to corresponding numbers in Sec. 4, “References.”1independent review: review completed by per-sonnel not having direct responsibility or di-rect involvement in the work function underreview.managerial and administrative controls:orders, instructions, procedures, policies, prac-tices, and

copyright@ 2008-2019 麦多课文库(www.mydoc123.com)网站版权所有
备案/许可证编号:苏ICP备17064731号-1