1、Qualification ofActive Mechanical Equipment Used in Nuclear Power PlantsAN AMERICAN NATIONAL STANDARDASME QME-12007(Revision of ASME QME-12002)Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-ASME
2、QME-12007(Revision of ASME QME-12002)Qualification ofActive MechanicalEquipment Used inNuclear Power PlantsAN 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 witho
3、ut license from IHS-,-,-Date of Issuance: November 28, 2007The next edition of this Standard is scheduled for publication in 2010. There will be no addendaissued to this edition.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. Interpretations
4、are published on the ASME Web site under the Committee Pages athttp:/cstools.asme.org as they are issued.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 NationalStand
5、ards. 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 opportunity for additi
6、onal 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 not take any position with respect to the validity of any patent rights asserted in connection with a
7、nyitems mentioned in this document, and does not undertake to insure anyone utilizing a 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 r
8、ights, 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 interpreted asgovernment or industry endorsement of this code or standard.ASME accepts responsibility for only
9、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 the prior written
10、 permission of the publisher.The American Society of Mechanical EngineersThree Park Avenue, New York, NY 10016-5990Copyright 2007 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrinted in U.S.A.Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo re
11、production or networking permitted without license from IHS-,-,-CONTENTSForeword viiCommittee Roster . ixOrganization of QME-1 xSummary of Changes xiiSection QR General Requirements 1QR-1000 Scope . 1QR-2000 Purpose 1QR-3000 References 1QR-4000 Definitions 1QR-5000 Qualification Principles . 3QR-600
12、0 Qualification Specification . 4QR-7000 Qualification Program . 4QR-8000 Documentation . 6Nonmandatory Appendices to Section QRQR-A Seismic Qualification of Active Mechanical Equipment 7QR-A1000 Scope . 7QR-A2000 Purpose 7QR-A3000 References 7QR-A4000 Definitions 8QR-A5000 Earthquake Environment an
13、d Equipment Response 9QR-A6000 Seismic Qualification Requirements 11QR-A7000 Qualification Methods 15QR-A8000 Documentation . 22Attachment A Guidelines for Qualification by Similarity (Indirect Method) 24Attachment B Examples of Qualification of Pumps and Valves by Analysis . 28Attachment C Qualific
14、ation of Pumps and Valves Using Natural EarthquakeExperience Data 38Appendix QR-A FiguresB-1 Pump Assembly 29B-2 Finite Element Formulation of Pump Assembly 30B-3 Butterfly Valve Assembly . 34B-4 Finite Element Formulation of Butterfly Valve Assembly . 35C-1 Seismic Motion Bounding Spectrum Horizont
15、al Ground Motion 39C-2 Limits of Experience Data for Motor-Operated Valves andSubstantial Piston-Operated Valves 41C-3 Limits of Experience Data for Air-Operated Diaphragm Valves, Spring-Operated Pressure Relief Valves, and Piston-Operated Valves ofLightweight Construction . 42Appendix QR-A TablesQR
16、-A6210-1 Damping Values: Percent of Critical Damping 12QR-A7422-1 Reduction Factors . 20A-1 List of Input Parameters 26A-2 Comparative List of Physical Parameters 27B-1 Calculated Frequencies for Pump/Motor Assembly: Print ofFrequencies . 31B-2 Evaluation of Behavior at Critical Locations . 33B-3 Al
17、lowable Stresses at 200F for 4-in. Valve . 36iiiCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-B-4 Beam Stresses, psi, for ASME Service Level B 36B-5 Beam Stresses, psi, for ASME Service Level C
18、36B-6 Plate Stresses, psi, for ASME Service Level B 36B-7 Plate Stresses, psi, for ASME Service Level C 36B-8 Other Locations . 37B-9 4-in. Valve Nodal Displacements, in., for ASME Service Level C 37QR-B Guide for Qualification of Nonmetallic Parts 43QR-B1000 Scope . 43QR-B2000 Purpose 43QR-B3000 Re
19、ferences 43QR-B4000 Definitions 43QR-B5000 Requirements . 43QR-B6000 Methods of Qualification 45QR-B7000 Documentation . 48Section QDR Qualification of Dynamic Restraints 49QDR-1000 Scope . 49QDR-2000 Purpose 49QDR-3000 Definitions 49QDR-4000 Qualification Principles and Philosophy . 49QDR-5000 Func
20、tional Specification . 52QDR-6000 Qualification Program . 52QDR-7000 Documentation Requirements . 57Nonmandatory Appendices to Section QDRQDR-A Functional Specification for Dynamic Restraints 59QDR-A1000 Scope . 59QDR-A2000 Purpose 59QDR-A3000 References 59QDR-A4000 Definitions 59QDR-A5000 Functiona
21、l Specification Contents 59QDR-A6000 Filing Requirements . 61QDR-B Restraint Similarity. 62QDR-B1000 Scope . 62QDR-B2000 Examples of Design Similarity . 62QDR-C Typical Values of Restraint Functional Parameters 63QDR-C1000 Scope . 63QDR-C2000 Functional Parameters 63QDR-C3000 Aging and Service Condi
22、tion Simulation Qualification Program 63Section QP Qualification of Active Pump Assemblies. 64Introduction 64QP-1000 Scope . 64QP-2000 Purpose 64QP-3000 References 64QP-4000 Definitions 65QP-5000 Qualification Principles and Philosophy . 65QP-6000 Qualification Specification . 65QP-7000 Qualificatio
23、n Program . 67QP-8000 Documentation . 69Nonmandatory Appendices to Section QPQP-A Pump Specification Checklist 70QP-A1000 Scope . 70QP-A2000 Applicable Documents, Codes, and Standards . 70QP-A3000 Design and Construction Requirements 70ivCopyright ASME International Provided by IHS under license wit
24、h ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-QP-A4000 Structural, Seismic, and Environmental Qualification Requirements . 70QP-A5000 Material and Manufacturing Requirements 70QP-A6000 Testing Requirements . 70QP-A7000 Documentation, Instructions, and Limi
25、tations 71QP-B Pump Shaft-Seal System Specification Checklist 72QP-B1000 Scope . 72QP-B2000 Applicable Documents, Codes, and Standards . 72QP-B3000 Design and Construction Requirements 72QP-B4000 Structural, Seismic, and Environmental Qualification Requirements . 72QP-B5000 Materials and Manufacturi
26、ng Requirements 72QP-B6000 Testing Requirements . 72QP-B7000 Documentation, Instructions, and Limitations 72QP-C Pump Turbine Driver Specification Checklist 73QP-C1000 Scope . 73QP-C2000 Applicable Documents, Codes, and Standards . 73QP-C3000 Design and Construction Requirements 73QP-C4000 Structura
27、l, Seismic, and Environmental Qualification Requirements . 73QP-C5000 Material and Manufacturing Requirements 73QP-C6000 Testing Requirements . 73QP-C7000 Documentation, Instructions, and Limitations 73QP-D Pump Similarity Checklist. 74QP-D1000 Scope . 74QP-D2000 Pump Design . 74QP-D3000 Process Des
28、ign 74QP-E Guidelines for Shaft-Seal System Material and Design Consideration 75QP-E1000 Scope . 75QP-E2000 Purpose 75QP-E3000 Definitions 75QP-E4000 Material Considerations . 75QP-E5000 Design Considerations 75Appendix QP-E TablesQP-E1 Shaft-Seal System Specification 76QP-E2 Limits for Unbalanced S
29、eals . 77Section QV Functional Qualification Requirements for Active Valve Assembliesfor Nuclear Power Plants . 78QV-1000 Scope . 78QV-2000 Purpose 78QV-3000 References 78QV-4000 Definitions 78QV-5000 Qualification Principles and Philosophy . 79QV-6000 Qualification Specification . 79QV-7000 Qualifi
30、cation Program . 79QV-8000 Documentation Requirements . 88Section QV TableQV-7300 Valve Assembly Qualification Requirement Matrix . 80Mandatory Appendix to Section QVQV-I Qualification Specification for Active Valves 90QV-I1000 Scope . 90QV-I2000 Purpose 90QV-I3000 References 90QV-I4000 Definitions
31、90QV-I5000 Functional Specification Contents 90vCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-QV-I6000 Actuator Requirements 91QV-I7000 Self-Operated Check Valve Characteristics . 91QV-I8000 Pre
32、ssure Relief Valve Characteristics . 91Nonmandatory Appendix to Section QVQV-A Functional Specification for Active Valves for Nuclear Power Plants 92QV-A1000 Scope . 92QV-A2000 Purpose 92QV-A3000 References 92QV-A4000 Definitions 92QV-A5000 Functional Specification Contents 92QV-A6000 Functional Spe
33、cification Details . 93QV-A7000 Filing Requirements . 94Section QV-G Guide to Section QV: Determination of Valve Assembly PerformanceCharacteristics . 95QV-G1000 Scope . 95QV-G2000 Introduction 95QV-G3000 References 95QV-G4000 Definitions 96QV-G5000 Valve Assembly Performance Characteristic Requirem
34、ents 96QV-G6000 General Considerations . 96QV-G7000 Power-Actuated Valve Assembly Considerations . 99QV-G8000 Valve Considerations 100viCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-FOREWORDFede
35、ral 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 for specifiedservice conditions.
36、 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 qualification standards was a
37、ssigned 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.The N45 Committees valve task force (N278) was reassigned in 1974 to the American NationalS
38、tandards 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 Mechanical Equipment Used in
39、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 Committees pump task force (
40、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 ASME Committee on Qualification of
41、 MechanicalEquipment Used in Nuclear Power Plants (QME) and designated as the Subcommittee onQualification of Valve Assemblies and the Subcommittee on Qualification of Pump Assemblies.In June 1977, an IEEE/ASME agreement was formulated giving primary responsibility forqualification standards to IEEE
42、 and quality assurance standards to ASME. This arrangementremained in effect until ASME established the current Committee on Qualification of MechanicalEquipment Used in Nuclear Power Plants.During 1985, the Committee on Qualification of Mechanical Equipment Used in Nuclear PowerPlants researched th
43、e various formats this Standard could take. Based on the wide acceptanceof ASME Section IIIs format for multiple classes, the Committee adopted a similar organizationalformat to accommodate multiple equipment types covered by this Standard. As IEEE Standards323 and 627 had already been in use many y
44、ears for electrical equipment, these standardswere also studied for appropriate content that should be addressed for mechanical equipment.Subsequently, the following Organization Guide was developed for this Standard and submittedto the ASME Board on Nuclear Codes and Standards for approval. On Janu
45、ary 16, 1986, theBoard on Nuclear Codes and Standards approved QMEs approach and outline for this Standard.Consistent with the guidance in ASME SI-9 ASME Guide for Metrication of Codes andStandards SI (Metric Units) regarding metrication, SI units have been provided in narrativeportions of QME-1 for
46、 general information only, and the U.S. Customary units are the standard.Either U.S. Customary units or SI units may be used, but one system shall be used consistentlythroughout construction of the component. Should the owner or his agent desire metric units, itsill be set forth in the design specif
47、ications.The various parts of ASME QME-11994 were approved by the American National 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 SectionQV and its Appendix
48、 A, February 17, 1994. Section QV is a revision and redesignation ofANSI B16.41-1983.In 1996 the Board of Nuclear Codes and Standards requested all committees reporting to it toadd SI (metric) units to all documents by replacing Customary (English) units with SI units orby showing SI units in a dual
49、 format with Customary units. The decision as to the extent of theviiCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-conversion and format was left to the various committees. The Committee on Qualification ofMechanical Equipment for Nuclear Power
