ASME QME-1-2012 Qualification of ACTV Mechanical Equipment Used in Nuclear Facilities (QME-1 - 2012)《核电站用放射性机械设备的合格证明》.pdf

1、Qualification of Active Mechanical Equipment Used in Nuclear FacilitiesAN AMERICAN NATIONAL STANDARDASME QME-12012(Revision of ASME QME-12007)ASME QME-12012(Revision of ASME QME-12007)Qualification of ActiveMechanical EquipmentUsed in NuclearFacilitiesAN AMERICAN NATIONAL STANDARDTwo Park Avenue New

2、 York, NY 10016 USADate of Issuance: April 24, 2013The next edition of this Standard is scheduled for publication in 2018.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. Periodically certain actions of the ASME QME Committee may be published

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5、s 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 standard was developed under procedures accredited as meeting the criteria for Americ

6、an 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 code or standard was madeavailable for public review and comment that provides an opport

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10、ibility 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 may be reproduced in any form,in an electronic retrieval system or otherwise,without

11、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 reservedPrinted in U.S.A.CONTENTSForeword viCommittee Roster . viiOrganization of QME-1 viiiSummar

12、y of Changes xSection QR General Requirements 1QR-1000 Scope 1QR-2000 Purpose 1QR-3000 References 1QR-4000 Definitions . 1QR-5000 Qualification Principles . 3QR-6000 Qualification Specification 4QR-7000 Qualification Program 4QR-8000 Documentation . 6Nonmandatory Appendices to Section QRQR-A Seismic

13、 Qualification of Active Mechanical Equipment 7QR-A1000 Scope 7QR-A2000 Purpose 7QR-A3000 References 7QR-A4000 Definitions . 7QR-A5000 Earthquake Environment and Equipment Response 9QR-A6000 Seismic Qualification Requirements . 11QR-A7000 Qualification Methods 15QR-A8000 Documentation . 22Appendix Q

14、R-A TablesQR-A6210-1 Damping Values: Percent of Critical Damping . 12QR-A7422-1 Reduction Factors 20QR-B Guide for Qualification of Nonmetallic Parts . 24QR-B1000 Scope 24QR-B2000 Purpose 24QR-B3000 References 24QR-B4000 Definitions . 24QR-B5000 Requirements . 24QR-B6000 Methods of Qualification . 2

15、6QR-B7000 Documentation . 29Section QDR Qualification of Dynamic Restraints . 30QDR-1000 Scope 30QDR-2000 Purpose 30QDR-3000 Definitions . 30QDR-4000 Qualification Principles and Philosophy . 30QDR-5000 Functional Specification 33QDR-6000 Qualification Program 33QDR-7000 Documentation Requirements .

16、 38Nonmandatory Appendices to Section QDRQDR-A Functional Specification for Dynamic Restraints 40QDR-A1000 Scope 40QDR-A2000 Purpose 40iiiQDR-A3000 References 40QDR-A4000 Definitions . 40QDR-A5000 Functional Specification Contents . 40QDR-A6000 Filing Requirements 42QDR-B Restraint Similarity 43QDR-

17、B1000 Scope 43QDR-B2000 Examples of Design Similarity 43QDR-C Typical Values of Restraint Functional Parameters 44QDR-C1000 Scope 44QDR-C2000 Functional Parameters 44QDR-C3000 Aging and Service Condition Simulation Qualification Program 44Section QP Qualification of Active Pump Assemblies 45Introduc

18、tion 45QP-1000 Scope 45QP-2000 Purpose 45QP-3000 References 45QP-4000 Definitions . 46QP-5000 Qualification Principles and Philosophy . 46QP-6000 Qualification Specification 46QP-7000 Qualification Program 48QP-8000 Documentation . 50Nonmandatory Appendices to Section QPQP-A Pump Specification Check

19、list . 51QP-A1000 Scope 51QP-A2000 Applicable Documents, Codes, and Standards . 51QP-A3000 Design and Construction Requirements . 51QP-A4000 Structural, Seismic, and Environmental Qualification Requirements 51QP-A5000 Material and Manufacturing Requirements 51QP-A6000 Testing Requirements . 51QP-A70

20、00 Documentation, Instructions, and Limitations . 52QP-B Pump Shaft-Seal System Specification Checklist . 53QP-B1000 Scope 53QP-B2000 Applicable Documents, Codes, and Standards . 53QP-B3000 Design and Construction Requirements . 53QP-B4000 Structural, Seismic, and Environmental Qualification Require

21、ments 53QP-B5000 Materials and Manufacturing Requirements . 53QP-B6000 Testing Requirements . 53QP-B7000 Documentation, Instructions, and Limitations . 53QP-C Pump Turbine Driver Specification Checklist . 54QP-C1000 Scope 54QP-C2000 Applicable Documents, Codes, and Standards . 54QP-C3000 Design and

22、Construction Requirements . 54QP-C4000 Structural, Seismic, and Environmental Qualification Requirements 54QP-C5000 Material and Manufacturing Requirements 54QP-C6000 Testing Requirements . 54QP-C7000 Documentation, Instructions, and Limitations . 54QP-D Pump Similarity Checklist 55QP-D1000 Scope 55

23、QP-D2000 Pump Design . 55QP-D3000 Process Design . 55QP-E Guidelines for Shaft-Seal System Material and Design Consideration 56QP-E1000 Scope 56ivQP-E2000 Purpose 56QP-E3000 Definitions . 56QP-E4000 Material Considerations 56QP-E5000 Design Considerations 56Appendix QP-E TablesQP-E4200-1 Shaft-Seal

24、System Specification 57QP-E5300-1 Limits for Unbalanced Seals 58Section QV Functional Qualification Requirements for Active Valve Assemblies forNuclear Facilities 59QV-1000 Scope 59QV-2000 Purpose 59QV-3000 References 59QV-4000 Definitions . 59QV-5000 Qualification Principles and Philosophy . 60QV-6

25、000 Qualification Specification 60QV-7000 Qualification Program 60QV-8000 Documentation Requirements . 69Section QV TableQV-7300-1 Valve Assembly Qualification Requirement Matrix . 61Mandatory Appendix to Section QVQV-I Qualification Specification for Active Valves . 71QV-I1000 Scope 71QV-I2000 Purp

26、ose 71QV-I3000 References 71QV-I4000 Definitions . 71QV-I5000 Functional Specification Contents . 71QV-I6000 Actuator Requirements . 72QV-I7000 Self-Operated Check Valve Characteristics . 72QV-I8000 Pressure Relief Valve Characteristics 72Section QVG Guide to Section QV: Determination of Valve Assem

27、bly PerformanceCharacteristics 73QVG-1000 Scope 73QVG-2000 Introduction 73QVG-3000 References 73QVG-4000 Definitions . 74QVG-5000 Valve Assembly Performance Characteristic Requirements . 74QVG-6000 General Considerations . 74QVG-7000 Power-Actuated Valve Assembly Considerations . 77QVG-8000 Valve Co

28、nsiderations . 78vFOREWORDFederal regulations applicable to nuclear power plants require that measures be established toensure that certain equipment operates as specified. This Standard sets forth requirements andguidelines that may be used to ensure that active mechanical equipment is qualified fo

29、r specifiedservice conditions. As determined by federal regulators and/or nuclear power plant licensees,this Standard may be applied to future nuclear power plants or existing operating nuclear powerplant component replacements, modifications, or additions.In the early 1970s, initial development of

30、qualification standards was assigned to the ANSI N45Committee. The N45 Committee in turn established a task force to prepare two series of standardsto ensure that pumps and valves used in nuclear plant systems would function as specified. TheN45 Committees valve task force (N278) was reassigned in 1

31、974 to the American NationalStandards Committee B16 and designated Subcommittee H. The first qualification standardto be issued for valves was ANSI N278.1-1975, which covered the preparation of functionalspecifications. In 1982, the task force was reassigned to the ASME Committee on Qualificationof

32、Mechanical Equipment Used in Nuclear Power Plants (QME) and designated the Subcommitteeon Qualification of Valve Assemblies. As an interim measure, in 1983, ANSI B16.41 was issuedto cover functional qualification requirements for power-operated active valve assemblies fornuclear power plants.The N45

33、 Committees pump task force (N551), established in 1973, was assigned to ASMENuclear Power Codes and Standards along with N278 as part of the Subcommittee QNPE,Qualification of Nuclear Plant Equipment. Both N551 and N278 operated as Subcommittee QNPEuntil 1982, when they were reassigned to the QME C

34、ommittee and designated as the Subcommitteeon Qualification of Valve Assemblies and the Subcommittee on Qualification of Pump Assemblies.In June 1977, an IEEE/ASME agreement was formulated giving primary responsibility for qualifi-cation standards to IEEE and quality assurance standards to ASME. Thi

35、s arrangement remainedin effect until ASME established the Committee on Qualification of Mechanical Equipment Usedin Nuclear Power Plants, now known as the Committee on Qualification of Mechanical EquipmentUsed in Nuclear Facilities.The various parts of ASME QME-11994 were approved by the American N

36、ational StandardsInstitute (ANSI) on the following dates: Section QP, September 22, 1992; Section QR, June 8, 1993;Section QR, Appendix A, October 7, 1993; Section QR, Appendix B, May 14, 1993; and Section QVand its Appendix A, February 17, 1994. Section QV was a revision and redesignation ofANSI B1

37、6.41-1983.QME-12002 was published in 2003. In September of 2003, it was recognized that the Standardhad aspects, such as the process for valve qualification, that could better use new computeranalytical techniques and that were proscriptive in nature. In addition, seismic qualificationneeded to be u

38、pdated to recognize new industry guidance. New sections were needed on standard-ization of experience-based seismic equipment qualification and the qualification of dynamicrestraints. At the time, industry experience had demonstrated that qualification to QME-1 wasrequired without the specification

39、of the parameters for which equipment needed to be qualified.The use of this Standard requires that a qualification specification be provided.ASME QME-12007 was endorsed by the Nuclear Regulatory Commission (NRC) and was thefirst edition of QME-1 to be so endorsed. It was approved as an American Nat

40、ional Standard onJune 25, 2007.The 2012 edition of this Standard was approved as an American National Standard onSeptember 17, 2012.Requests for interpretation or suggestions for improvement of this Standard should beaddressed to the Secretary of the ASME Committee on Qualification of Mechanical Equ

41、ipmentUsed in Nuclear Facilities, The American Society of Mechanical Engineers, Two Park Avenue,New York, NY 10016-5990.viCOMMITTEE ON QUALIFICATION OF MECHANICAL EQUIPMENTUSED IN NUCLEAR FACILITIES(The following is the roster of the Committee at the time of approval of this Standard.)STANDARDS COMM

42、ITTEE OFFICERSD. C. Stanze, ChairT. P. Ruggiero, Jr., Vice ChairL. Powers, SecretarySTANDARDS COMMITTEE PERSONNELT. M. Adams, JD Stevenson reference to QR-7300includes all material in Subarticle QR-7300; reference toQR-7320 includes all material in Subsubarticle QR-7320.(b) References to the Boiler

43、and Pressure Vessel Code andto Other Standards. When a reference is made to anySection of the BPVC, or to other standards, it shall beunderstood to mean the designated article, paragraph,figure, or table in the designated document. All suchreferences shall be identified in the text of this Standardb

44、y the documents issuing source and the documentsunique identification number, e.g., ASME IIISubsection NF, IEEE Std 627, or 10CFR50 Part A. Ifrequired, further reference to unique articles or para-graphs of the referenced document may also bedescribed, e.g., ASME III Subsection NF paragraphNF-3211.1

45、(a). Each short reference made in the text shallbe described in more complete detail in Article 3000 byissuing source, unique identification number, year ofpublication being referenced, and full title, e.g.,IEEE Std 382-1980, Standard for Qualification of SafetyRelated Valve Operators. References li

46、sted without yearof publication suggest that the latest version of the refer-ence was utilized in the development of this Standard. Itshould be noted by users of this Standard that regulatoryrequirements and Codes of Record for a particularnuclear power plant may take precedence over refer-ences use

47、d within this Standard. Section QR referencesixapplicable for both pumps and valves shall be describedin Article QR-3000, while references unique toSection QP or QV only will be described in Article QP-orQV-3000, as applicable.(c) References to Appendices. Two types of appendicesmay be used in this

48、Standard, designated Mandatoryand Nonmandatory. Both types of appendices are desig-nated by the prefix Q. This is followed by a letter, whichis the same one used by the section to which the appen-dix applies, e.g., QR. Mandatory appendices containrequirements that must be followed in qualification;s

49、uch references are then uniquely identified by a romannumeral, e.g., Appendix QR-I and its specific title.Nonmandatory appendices provide information orguidance; such references are designated by a capitalletter, e.g., Appendix QR-A, and its specific title.ASME QME-12012SUMMARY OF CHANGESFollowing approval by the ASME Committee on Qualification of Mechanical Equipment Usedin Nuclear Facilities and ASME, and after public review, QME-12012 was approved by theAmerican National Standards Institute on September 17, 2012.QME-12012 includes the following changes identified by a