ASME NQA-1-2012 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2012)《核设施应用的质量保证要求》.pdf
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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
4、ries concerning interpretations of technical aspects of thisStandard. Interpretations are published on the ASME Web site under the Committee Pages athttp:/cstools.asme.org/. Interpretations are also included with each edition.Errata to codes and standards may be posted on the ASME Web site under the
5、 Committee Pages toprovide corrections to incorrectly published items, or to correct typographical or grammatical errorsin codes and standards. Such errata shall be used on the date posted.The Committee Pages can be found at http:/cstools.asme.org/. There is an option available toautomatically recei
6、ve an e-mail notification when errata are posted to a particular code or standard.This option can be found on the appropriate Committee Page after selecting “Errata” in the “PublicationInformation” section.ASME is the registered trademark of The American Society of Mechanical Engineers.This code or
7、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 proposed cod
8、e 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 does
9、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 liability. Us
10、ers 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 interpret
11、ed 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 document
12、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 EngineersTwo Park Avenue, New York, NY 10016-5990Copyright 2013 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrint
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
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