1、Quality Assurance Requirements for Nuclear Facility ApplicationsAN AMERICAN NATIONAL STANDARDASME NQA-12012(Revision of ASME NQA-12008)Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-Copyright ASM
2、E International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-ASME NQA-12012(Revision of ASME NQA-12008)Quality AssuranceRequirements forNuclear FacilityApplicationsAN AMERICAN NATIONAL STANDARDTwo Park Avenue New York, NY
3、10016 USACopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-Date of Issuance: March 15, 2013The next edition of this Standard is scheduled for publication in 2014.ASME issues written replies to inqui
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13、ed 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 Assurance Comm
14、ittee . 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 . 34Part III Guidance for Implementing Part I and II Requirements . 115Part I
15、V Guidance on the Application and Use of NQA-1 184iiiCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-(12) FOREWORDEarly in 1975, the American National Standards Institute (ANSI) assigned overall r
16、esponsibilityfor 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 operatingunder the A
17、SME 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 Requirements for Nuclear P
18、ower 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 Nuclear Facilities
19、; 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 PlantsN45.2.9-1979 Requirements
20、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 Assurance Programs f
21、or 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 revised and publishe
22、d in 1983, 1986, 1989, 1994,1997, 2000, 2004, and 2008. From its initial publication in 1979, the Standard has retained the18-criteria structure of 10 CFR 50 Appendix B in a portion of the document. For this edition,Part I is organized by the 18-criteria structure and is intended to meet and impleme
23、nt thecriteria of 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and FuelReprocessing Plants, 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 Cleaning of
24、 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 Requir
25、ements 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 and Sy
26、stems 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 IHS unde
27、r 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 repositories.This
28、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 updated and r
29、evised 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 selecting N
30、QA-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-basedfocus. Th
31、e 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 implementation
32、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 nuclear fa
33、cilityapplication. 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,repair,
34、 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 comparisons t
35、o 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 applicatio
36、n 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 specified. The
37、guidance 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 theactivities b
38、eing 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 guidance for
39、 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 the sat
40、isfactory 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-effect
41、ive 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 activities of a
42、 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, The Ameri
43、canSociety of Mechanical Engineers, Two 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 from IHS
44、-,-,-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 Ed. NQA-
45、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 . . . . . . . . . . . .Add. NQA-1c-1985 12/31/1985 . . . . . . . . . . . .3rd Ed. NQA-1-1986 7/1/1986 2nd Ed. NQA-2-1986 7/1/1986 . . . . . .Add. NQA-
46、1a-1986 2/15/1987 Add. NQA-2a-1986 2/15/1987 . . . . . .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 A
47、dd. NQA-2a-1990 5/31/1990 . . . . . .Add. NQA-1b-1991 4/15/1991 Add. NQA-2b-1991 5/12/1992 . . . . . .Add. NQA-1c-1992 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 . . . .
48、. . . . . . . .Add. NQA-1a-1999 5/25/1999 . . . . . . . . . . . .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 . . .
49、 . . . . . . . . .9th Ed. NQA-1-2008 3/14/2008 . . . . . . . . . . . .Add. NQA-1a-2009 7/20/2009 . . . . . . . . . . . .Add. NQA-1b-2011 1/4/2011 . . . . . . . . . . . .10th Ed. NQA-1-2012 3/15/2013 . . . . . . . . . . . .NOTES:(1) This edition is a consolidaton of NQA-1 and NQA-2.(2) NQA editions and addenda prior to 1989 were titled ANSI/ASME NQA.viCopyright ASME Internatio
