1、AN AMERICAN NATIONAL STANDARDQuality Assurance Requirements for Nuclear Facility ApplicationsASME NQA-12008(Revision of ASME NQA-12004)Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-ASME NQA-1200
2、8(Revision of ASME NQA-12004)QualityAssuranceRequirements forNuclear FacilityApplicationsAN AMERICAN NATIONAL STANDARDThree Park Avenue New York, NY 10016Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IH
3、S-,-,-Date of Issuance: March 14, 2008The 2008 edition of this Standard is being issued with an automatic addenda subscription service.The use of an addenda allows revisions made in response to public review comments or committeeactions to be published as necessary. The next edition of this Standard
4、 is scheduled for publicationin 2011.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. The interpretations will be included with the above addenda service.ASME is the registered trademark of The American Society of Mechanical Engineers.This cod
5、e or standard was developed under procedures accredited as meeting the criteria for American NationalStandards. The Standards Committee that approved the code or standard was balanced to assure that individuals fromcompetent and concerned interests have had an opportunity to participate. The propose
6、d code or standard was madeavailable for public review and comment that provides an opportunity for additional public input from industry, academia,regulatory agencies, and the public-at-large.ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, or activity.ASME
7、does not take any position with respect to the validity of any patent rights asserted in connection with anyitems mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability forinfringement of any applicable letters patent, nor assumes any such liabilit
8、y. Users of a code or standard are expresslyadvised that determination of the validity of any such patent rights, and the risk of infringement of such rights, isentirely their own responsibility.Participation by federal agency representative(s) or person(s) affiliated with industry is not to be inte
9、rpreted asgovernment or industry endorsement of this code or standard.ASME accepts responsibility for only those interpretations of this document issued in accordance with the establishedASME procedures and policies, which precludes the issuance of interpretations by individuals.No part of this docu
10、ment may be reproduced in any form,in an electronic retrieval system or otherwise,without the prior written permission of the publisher.The American Society of Mechanical EngineersThree Park Avenue, New York, NY 10016-5990Copyright 2008 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reserv
11、edPrinted in U.S.A.Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-CONTENTS(A detailed Contents precedes each NQA Part.)Foreword ivPreparation of Technical Inquiries to the Nuclear Quality Assuran
12、ce Committee . viiCommittee Roster . viiiSummary of Changes ixPart I Requirements for Quality Assurance Programs for Nuclear Facilities(From Former NQA-1) 1Part II Quality Assurance Requirements for Nuclear Facility Applications 36Part III Nonmandatory Appendices (From Former NQA-1 and NQA-2) . 109P
13、art IV Nonmandatory Appendices: Positions and Applications Matrices . 173iiiCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-FOREWORDEarly in 1975, the American National Standards Institute (ANSI)
14、assigned overall responsibilityfor coordination among technical societies and development and maintenance of nuclear powerquality assurance standards to the American Society of Mechanical Engineers (ASME). The ASMECommittee on Nuclear Quality Assurance was constituted on October 3, 1975, and began o
15、peratingunder the ASME Procedures for Nuclear Projects. The ASME Committee on Nuclear QualityAssurance currently operates under the ASME Operating Procedures and Practices for NuclearCodes and Standards Development Committees. This Committee prepared ANSI/ASME NQA-1,Quality Assurance Program Require
16、ments for Nuclear Power Plants, and ANSI/ASME NQA-2,Quality Assurance Requirements for Nuclear Power Plants, which were first issued in 1979 and1983, respectively, as American National Standards.NQA-1-1979 was based upon the contents of ANSI/ASME N45.2-1977, Quality AssuranceProgram Requirements for
17、 Nuclear Facilities; ANSI N46.2, Revision 1, Quality Assurance ProgramRequirements for Post Reactor Nuclear Fuel Cycle Facilities; and the following seven daughterStandards of ANSI/ASME N45.2:N45.2.6-1978 Qualifications of Inspection, Examination, and Testing Personnel for NuclearPower PlantsN45.2.9
18、-1979 Requirements for Collection, Storage, and Maintenance of Quality AssuranceRecords for Nuclear Power PlantsN45.2.10-1973 Quality Assurance Terms and DefinitionsN45.2.11-1974 Quality Assurance Requirements for the Design of Nuclear Power PlantsN45.2.12-1977 Requirements for Auditing of Quality A
19、ssurance Programs for Nuclear PowerPlantsN45.2.13-1976 Quality Assurance Requirements for Control of Procurement of Items andServices for Nuclear Power PlantsN45.2.23-1978 Qualification of Quality Assurance Program Audit Personnel for NuclearPower PlantsSince the 1979 Edition was issued, NQA-1 was r
20、evised and published in 1983, 1986, 1989, 1994,1997, and 2000. From its initial publication in 1979, the Standard has retained the 18-criteriastructure of 10 CFR 50 Appendix B in a portion of the document. For this edition, Part I isorganized by the 18-criteria structure and is intended to meet and
21、implement the criteria of10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel ReprocessingPlants, dated January 20, 1975.The ASME NQA-2-1983 standard incorporated the requirements of the following quality assur-ance Standards not included in ASME NQA-1:N45.2.1-1980 Clea
22、ning of Fluid Systems and Associated Components for NuclearPower PlantsN45.2.2-1978 Packaging, Shipping, Receiving, Storage, and Handling of Items forNuclear Power PlantsN45.2.3-1973 (R1978) Housekeeping During the Construction Phase of Nuclear PowerPlantsN45.2.5-1978 Supplementary Quality Assurance
23、 Requirements for Installation,Inspection, and Testing of Structural Concrete, Structural Steel, Soils,and Foundations During the Construction Phase of Nuclear PowerPlantsN45.2.8-1975 (R1980) Supplementary Quality Assurance Requirements for Installation,Inspection and Testing of Mechanical Equipment
24、 and Systems for theConstruction Phase of Nuclear Power PlantsN45.2.15-1981 Hoisting, Rigging, and Transporting of Items for Nuclear PowerPlantsN45.2.20-1979 Supplementary Quality Assurance Requirements for SubsurfaceInvestigations for Nuclear Power PlantsivCopyright ASME International Provided by I
25、HS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-In 1984, the NQA Committee initiated work to expand the Standard to address quality assuranceprogram requirements appropriate to site characterization of high-level nuclear waste repositorie
26、s.This effort resulted in the preparation of a new standard, ASME NQA-3, Quality AssuranceProgram Requirements for the Collection of Scientific and Technical Information for SiteCharacterization of High-Level Nuclear Waste Repositories, which was issued in 1989.The NQA Committee has regularly update
27、d and revised the Standards since the 1979 Editionwas issued to improve its utility and value to the nuclear industry. In the early 1990s, the NQACommittee recognized that the NQA-1, NQA-2, and NQA-3 standards were not easily understoodand applied by all users, and some potential users were not sele
28、cting NQA-1 and NQA-2 as theirStandard of choice. The Committee decided to restructure the NQA Standards into a singlemultipart document that would improve the clarity of the standard, allow more rapid responseto varied applications of NQA requirements and guidance, and provide a performance-basedfo
29、cus. The restructured requirements, guidance, and applications appendices facilitate judiciousapplication of the entire Standard or portions of the Standard to the wide variety of workencountered by todays nuclear industry. The new structure aids improved understanding andsupports effective implemen
30、tation of the requirements, continues to address quality assuranceprogram compliance aspects, and adds focus on quality results.This multipart Standard, issued initially as NQA-1-1994, includes requirements and nonmanda-tory guidance to establish and implement a quality assurance program for any nuc
31、lear facilityapplication. Part I contains quality assurance program requirements for the siting, design, con-struction, operation, and decommissioning of nuclear facilities. Part II contains quality assurancerequirements for the planning and conducting of the fabrication, construction, modification,
32、repair, maintenance, and testing of systems, components, or activities for nuclear facilities. Part IIIcontains nonmandatory guidance and application appendices previously included in NQA-1,NQA-2, and NQA-3. Part IV contains NQA position papers, application matrices for users, cross-reference compar
33、isons to NQA, and other quality program information.The arrangement of the requirements in Part I (from former NQA-1), requirements for workpractices in Part II (from former NQA-2), and nonmandatory guidance and applications appendi-ces in Part III (from former NQA-1 and NQA-2) permits judicious app
34、lication of the entireStandard or portions of the Standard. If this edition (or post-1994 edition or addenda) is invokedby a procurement document or contract, only Parts I and II should be considered requirementsas applicable, unless other specific Parts, Subparts, or Appendices of NQA-1 are specifi
35、ed. Theguidance in Part III is not intended to be automatically imposed as supplemental requirements.The extent to which this Standard should be applied will depend upon the specific type of nuclearfacility, items, or services involved and the nature and scope and the relative importance of theactiv
36、ities being performed. The extent of application is to be determined by the organizationimposing the Standard. For example, the organization may invoke all requirements, selectedrequirements, or requirements with appropriate changes. Part III is intended to provide explana-tory information and guida
37、nce for use by organizations in developing and implementing theirprograms. It also provides examples of methods for implementing the requirements of Parts Iand II. Other methods may be equally suitable. The Standard may be applied to any structure,system, component, or activity that is essential to
38、the satisfactory performance of the facility. TheStandard may also be applied to a structure, system, component, or activity independent of afacility if its satisfactory performance is essential.The NQA Committee is aware of, and actively endorses, the growing worldwide movementtoward rational, cost
39、-effective quality assurance practices practices that focus on results. There-fore, changes considered necessary to improve the understanding and effective implementationhave been made that are intended to address compliance aspects with a focus on results. Toassure consistency with outside activiti
40、es of a similar nature, the Committee is maintaining liaisonwith other national and international groups that have a similar interest.Requests for interpretation or suggestions for improvement of this Standard should beaddressed to the Secretary of the ASME Committee on Nuclear Quality Assurance, Th
41、e AmericanSociety of Mechanical Engineers, Three Park Avenue, New York, NY 10016-5990.For a listing of the NQA publication history, refer to the following table:vCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license
42、 from IHS-,-,-NQA-1 NQA-2 NQA-3Editions Editions Editionsand and andAddenda Designator Issued Addenda Designator Issued Addenda Designator Issued1st Ed. NQA-1-1979 8/31/1979 . . . . . . . . . . . .Add. NQA-1a-1981 4/30/1981 . . . . . . . . . . . .Add. NQA-1b-1981 1/31/1982 . . . . . . . . . . . .2nd
43、 Ed. NQA-1-1983 7/1/1983 1st Ed. NQA-2-1983 8/31/1983 . . . . . .Add. NQA-1a-1983 12/31/1983 Add. NQA-2a-1985 10/15/1985 . . . . . .Add. NQA-1b-1984 3/15/1985 . . . . . . . . . . . .3rd Ed. NQA-1-1986 7/1/1986 2nd Ed. NQA-2-1986 7/1/1986 . . . . . .Add. NQA-1a-1986 2/15/1987 Add. NQA-2a-1986 2/15/19
44、87 . . . . . .Add. NQA-1b-1987 3/15/1988 Add. NQA-2b-1987 4/15/1988 . . . . . .Add. NQA-1c-1988 2/28/1989 Add. NQA-2c-1988 2/28/1989 . . . . . .4th Ed. NQA-1-1989 9/15/1989 3rd Ed. NQA-2-1989 9/30/1989 1st Ed. NQA-3-1989 3/23/1990Add. NQA-1a-1989 3/31/1990 Add. NQA-2a-1990 5/31/1990 . . . . . .Add.
45、NQA-1b-1991 4/15/1991 Add. NQA-2b-1991 5/12/1992 . . . . . .Add. NQA-1c1992 9/30/1992 . . . . . . . . . . . .5th Ed. NQA-1-1994 7/29/1994 . . . . . . . . . . . .Note (1)Add. NQA-1a-1995 1/19/1996 . . . . . . . . . . . .6th Ed. NQA-1-1997 12/31/1997 . . . . . . . . . . . .Add. NQA-1a-1999 5/25/1999 .
46、 . . . . . . . . . . .7th Ed. NQA-1-2000 5/21/2001 . . . . . . . . . . . .Add. NQA-1a-2002 12/6/2002 . . . . . . . . . . . .8th Ed. NQA-1-2004 12/22/2004 . . . . . . . . . . . .Add. NQA-1a-2005 5/3/2006 . . . . . . . . . . . .Add. NQA-1b-2007 6/1/2007 . . . . . . . . . . . .9th Ed. NQA-1-2008 3/14/2
47、008 . . . . . . . . . . . .NOTE:(1) This edition is a consolidaton of NQA-1 and NQA-2.viCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-PREPARATION OF TECHNICAL INQUIRIESTO THE NUCLEAR QUALITYASSU
48、RANCE COMMITTEEINTRODUCTIONThe ASME Nuclear Quality Assurance Committee will consider written requests for interpreta-tions and revisions to NQA Standards and develop new requirements or guidance if dictatedby technological development. The Committees activities in this regard are limited strictly t
49、ointerpretations of the requirements and guidance, or to the consideration of revisions to thepresent Standard on the basis of new data or technology. As a matter of published policy, ASMEdoes not “approve,” “certify,” “rate,” or “endorse” any item, construction, proprietary device,specific organizations, individual titles, or activity and, accordingly, inquiries requiring suchcon
