ANSI ASME NQA-1-2017 Quality Assurance Requirements for Nuclear Facility Applications.pdf
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1、Quality Assurance Requirements for Nuclear Facility ApplicationsAN AMERICAN NATIONAL STANDARDASME NQA-12017(Revision of ASME NQA-12015)ASME NQA-12017(Revision of ASME NQA-12015)Quality AssuranceRequirements forNuclear FacilityApplicationsAN AMERICAN NATIONAL STANDARDTwo Park Avenue New York, NY 1001
2、6 USADate of Issuance: January 18, 2018The next edition of this Standard is scheduled for publication in 2019.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. Interpretations are published on the ASME Web site under the Committee Pages athttp:
3、/cstools.asme.org/ as they are issued.Errata to codes and standards may be posted on the ASME Web site under the 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
4、.The Committee Pages can be found at http:/cstools.asme.org/. There is an option available toautomatically receive 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 “PublicationInf
5、ormation” section.ASME is the registered trademark of The American Society of Mechanical Engineers.This code 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
6、 that individuals fromcompetent and concerned interests have had an opportunity to participate. The proposed 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.
7、ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, or activity.ASME 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
8、 standard against liability forinfringement of any applicable letters patent, nor assume any such liability. 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
9、.Participation by federal agency representative(s) or person(s) affiliated with industry is not to be interpreted 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 pr
10、ocedures and policies, which precludes the issuance of interpretations by individuals.No part of this document 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 Avenu
11、e, New York, NY 10016-5990Copyright 2018 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrinted in U.S.A.CONTENTS(A detailed Contents precedes each NQA Part.)Foreword ivCorrespondence With the NQA Committee . viCommittee Roster . viiiIntroduction . xSummary of Changes xiPart I Requ
12、irements 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 Parts I and II Requirements 118Part IV Guidance on the Application and Use of NQA-1 219iiiFOREWORDThis S
13、tandard is intended to serve the global nuclear industry responsible for the safety andquality of nuclear facilities and activities.It is intended to be applied to any structure, system, component, activity, or organization thatis essential to the safe, reliable, and efficient performance of a nucle
14、ar facility and any activitiesindependent of a facility that may affect performance. It is also intended to be applied to allphases of a nuclear facility life cycle and to related activities.This Standard reflects industry experience and current understanding of the quality assurancerequirements nec
15、essary to achieve safe, reliable, and efficient utilization of nuclear energy andmanagement and processing of radioactive materials. The Committee on Nuclear QualityAssurance (NQA) actively endorses the growing worldwide movement toward rational, cost-effective quality assurance practices practices
16、that focus on results. The NQA Committee alsomaintains liaison with national and international groups that have similar interests in quality toassure consistency and maximum applicability of the Standard in a global setting. Consequently,the NQA Committee has regularly updated and revised the Standa
17、rd since its first edition wasissued in 1979 to improve its utility, effect on nuclear safety, and value to the nuclear industry.ThisStandard includesrequirementsand guidanceandisorganized inthefollowing fourparts:(a) Part I contains requirements for a Quality Assurance Program for nuclear facilitya
18、pplications.(b) Part II contains additional quality assurance requirements for the planning and conduct ofspecific work activities conducted under a Quality Assurance Program developed in accordancewith Part I.(c) Part III contains guidance for implementing the requirements of Parts I and II.(d) Par
19、t IV contains guidance for the application of NQA-1 and comparisons of NQA-1 withother quality requirements.Early in 1975, the American National Standards Institute (ANSI) assigned overall responsibilityfor coordination among technical societies and development and maintenance of nuclear powerqualit
20、y assurance standards to the American Society of Mechanical Engineers (ASME). TheASME Committee on NQA was constituted on October 3, 1975, and assumed responsibility forthe ANSI/ASME N.45 series documents. Currently, the NQA Committee operates under theASME requirements for Nuclear Codes and Standar
21、ds Development Committees.This Committee initially preparedANSI/ASME NQA-11979 Quality Assurance Program Requirements for Nuclear PowerPlantsANSI/ASME NQA-21983 Quality Assurance Requirements for Nuclear Power PlantsANSI/ASME NQA-31989 Quality Assurance Requirements for High Level WasteManagementFor
22、 a detailed history of the NQA Committee and evolution of the Standard, go to:http:/cstools.asme.org/csconnect/CommitteePages.cfm?CommitteepO10500000 however, they should not contain proprietary names orinformation.Requests that are not in the format described above may be rewritten in the appropria
23、te formatby the Committee prior to being answered, which may inadvertently change the intent of theoriginal request.Moreover, ASME does not act as a consultant for specific engineering problems or for thegeneral application or understanding of the Standard requirements. If, based on the inquiryviinf
24、ormationsubmitted,itis theopinionoftheCommitteethat theInquirershouldseekassistance,the inquiry will be returned with the recommendation that such assistance be obtained.ASME procedures provide for reconsideration of any interpretation when or if additionalinformation that might affect an interpreta
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