ASME QME-1-2017 Qualification of Active Mechanical Equipment Used in Nuclear Facilities.pdf

1、Qualification of Active Mechanical Equipment Used in Nuclear FacilitiesAN AMERICAN NATIONAL STANDARDASME QME-12017(Revision of ASME QME-12012)ASME QME-12017(Revision of ASME QME-12012)Qualification of ActiveMechanical EquipmentUsed in NuclearFacilitiesAN AMERICAN NATIONAL STANDARDTwo Park Avenue New

2、 York, NY 10016 USADate of Issuance: August 23, 2017The next edition of this Standard is scheduled for publication in 2022.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. Periodically certain actions of the ASME QME Committee may be published

3、 as Cases. Casesand interpretations are published on the ASME Web site under the Committee Pages athttp:/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

4、 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 receive an e-mail notification when errata are posted toaparticular code or standard.This

5、optioncanbefoundontheappropriateCommitteePageafterselecting“Errata”inthe“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 American NationalStand

6、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 forpublic review andcomment thatprovides an opportunityfor additional

7、 publicinput 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 anyitem

8、s 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 rights,

9、 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 those

10、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 permi

11、ssion of the publisher.The American Society of Mechanical EngineersTwo Park Avenue, New York, NY 10016-5990Copyright2017 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrinted in U.S.A.CONTENTSForeword viCommittee Roster . viiiOrganization of QME-1 ixSummary of Changes xiSection QR

12、 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 and Certification Requirements 6Mandatory Appendix to Section QRQR-I Qualifi

13、cations and Duties of Registered Professional Engineers forCertification Activities 8QR-I-1000 Scope 8Nonmandatory Appendices to Section QRQR-A Seismic Qualification of Active Mechanical Equipment 10QR-A-1000 Scope 10QR-A-2000 Purpose 10QR-A-3000 References 10QR-A-4000 Definitions . 10QR-A-5000 Eart

14、hquake Environment and Equipment Response 12QR-A-6000 Seismic Qualification Requirements . 14QR-A-7000 Qualification Methods 18QR-A-8000 Documentation . 25Appendix QR-A TablesQR-A-6210-1 Damping Values: Percent of Critical Damping . 15QR-A-7422-1 Reduction Factors 23QR-B Guide for Qualification of N

15、onmetallic Parts . 27QR-B-1000 Scope 27QR-B-2000 Purpose 27QR-B-3000 References 27QR-B-4000 Definitions . 27QR-B-5000 Requirements . 27QR-B-6000 Methods of Qualification . 29QR-B-7000 Documentation . 32QR-C Sample Registered Professional Engineer Certification Statements 33Appendix QR-C FormsQR-C-1

16、Sample Qualification Specification (QP, QV) Certification Statement 34QR-C-2 Sample Qualification Specification (QDR) Certification Statement 34QR-C-3 Sample Qualification Report (QP, QV) Certification Statement . 35QR-C-4 Sample Qualification Report (QDR) Certification Statement 35QR-C-5 Sample App

17、lication Report (QP, QV) Certification Statement . 36QR-C-6 Sample Application Report (QDR) Certification Statement . 36iiiSection QDR Qualification of Dynamic Restraints . 37QDR-1000 Scope 37QDR-2000 Purpose 37QDR-3000 Definitions . 37QDR-4000 Qualification Principles and Philosophy . 38QDR-5000 Qu

18、alification Specification 40QDR-6000 Qualification Program 41QDR-7000 Documentation Requirements . 46Mandatory Appendix to Section QDRQDR-I Qualification Specification for Dynamic Restraints 48QDR-I-1000 Scope 48QDR-I-2000 Purpose 48QDR-I-3000 References 48QDR-I-4000 Definitions . 48QDR-I-5000 Quali

19、fication Specification Contents . 48QDR-I-6000 Filing Requirements 50Nonmandatory Appendices to Section QDRQDR-A Restraint Similarity 51QDR-A-1000 Scope 51QDR-A-2000 Examples of Design Similarity 51QDR-B Typical Values of Restraint Functional Parameters 52QDR-B-1000 Scope 52QDR-B-2000 Functional Par

20、ameters 52QDR-B-3000 Aging and Service Condition Simulation Qualification Program 53Section QP Qualification of Active Pump Assemblies 54QP-1000 Scope 54QP-2000 Purpose 54QP-3000 References 54QP-4000 Definitions . 54QP-5000 Qualification Principles and Philosophy . 55QP-6000 Qualification Specificat

21、ion 55QP-7000 Qualification Program 56QP-8000 Documentation . 60Mandatory Appendix to Section QPQP-I Qualification Specification for Active Pump Assemblies. 62QP-I-1000 Scope 62QP-I-2000 Purpose 62QP-I-3000 References 62QP-I-4000 Definitions . 62QP-I-5000 Qualification Specification Contents . 62Non

22、mandatory Appendices to Section QPQP-D Pump Similarity Checklist 70QP-D-1000 Scope 70QP-D-2000 Pump Design . 70QP-D-3000 Process Design . 70QP-E Guidelines for Shaft-Seal System Material and Design Consideration 71QP-E-1000 Scope 71QP-E-2000 Purpose 71QP-E-3000 Definition 71QP-E-4000 Material Consid

23、erations 71QP-E-5000 Design Considerations 71ivAppendix QP-E TablesQP-E-4200-1 Shaft-Seal System Specification 72QP-E-5300-1 Limits for Unbalanced Seals 73Section QV Qualification Requirements for Active Valve Assemblies for NuclearFacilities 74QV-1000 Scope 74QV-2000 Purpose 74QV-3000 References 74

24、QV-4000 Definitions . 74QV-5000 Qualification Principles and Philosophy . 75QV-6000 Qualification Specification 75QV-7000 Qualification Program 75QV-8000 Documentation Requirements . 87Section QV TableQV-7300-1 Valve Assembly Qualification Requirement Matrix . 77Mandatory Appendix to Section QVQV-I

25、Qualification Specification for Active Valves . 89QV-I-1000 Scope 89QV-I-2000 Purpose 89QV-I-3000 References 89QV-I-4000 Definitions . 89QV-I-5000 Qualification Specification Contents . 89QV-I-6000 Actuator Requirements . 90QV-I-7000 Self-Operated Check Valve Characteristics . 90QV-I-8000 Pressure R

26、elief Valve Characteristics 91QV-I-9000 Special Material Requirements 91QV-I-10000 Installation Requirements . 91QV-I-11000 Maintenance Requirements . 91QV-I-12000 Qualification Requirements . 91QV-I-13000 Inservice Testing . 91QV-I-14000 Filing Requirements 91Nonmandatory Appendix to Section QVQV-B

27、 Static Side Load Testing for Power-Actuated and Relief ValveAssemblies 92QV-B-1000 Scope 92QV-B-2000 Purpose 92QV-B-3000 Definitions . 92QV-B-4000 General Requirements 92QV-B-5000 Test Method 93QV-B-6000 Evaluation of Results . 94QV-B-7000 Extrapolation of Results for Power-Operated Valves . 95Sect

28、ion QVG Guide to Section QV: Determination of Valve Assembly PerformanceCharacteristics 96QVG-1000 Scope 96QVG-2000 Introduction 96QVG-3000 References 96QVG-4000 Definitions . 97QVG-5000 Valve Assembly Performance Characteristic Requirements . 97QVG-6000 General Considerations . 97QVG-7000 Power-Act

29、uated Valve Assembly Considerations . 100QVG-8000 Valve Considerations . 101vFOREWORDFederal 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

30、 to ensure that active mechanical equipment is qualified for 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, modification

31、s, or additions.In the early 1970s, initial development of qualification standards was assigned to theN45 Committee of the American National Standards Institute (ANSI). The N45 Committee inturn established a task force to prepare two series of standards to ensure that pumps and valvesused in nuclear

32、 plant systems would function as specified. The N45 Committees valve task force(N278)wasreassignedin1974totheAmericanNationalStandardsCommitteeB16anddesignatedSubcommittee H. The first qualification standard to be issued for valves was ANSI N278.1-1975,whichcoveredthepreparationoffunctionalspecifica

33、tions.In1982,thetaskforcewasreassignedtoTheAmericanSocietyofMechanicalEngineers(ASME)CommitteeonQualificationofMechanicalEquipment Used in Nuclear Power Plants (QME) and designated the Subcommittee on Qualifica-tion of Valve Assemblies. As an interim measure, in 1983, ANSI B16.41 was issued to cover

34、functional qualification requirements for power-operated active valve assemblies for nuclearpower plants.The N45 Committees pump task force (N551), established in 1973, was assigned toASME Nuclear Power Codes and Standards along with N278 as part of the Subcommittee QNPE,Qualification of Nuclear Pla

35、nt Equipment. Both N551 and N278 operated as Subcommittee QNPEuntil 1982, when they were reassigned to the QME Committee and designated as, respectively,the Subcommittee on Qualification of Pump Assemblies and the Subcommittee on Qualificationof Valve Assemblies. In June 1977, an agreement between t

36、he Institute of Electrical and ElectronicsEngineers (IEEE) and ASME was formulated, giving primary responsibility for qualificationstandards to IEEE and for quality assurance standards to ASME. This arrangement remained ineffect until ASME established the Committee on Qualification of Mechanical Equ

37、ipment UsedinNuclearPowerPlants,nowknownastheCommitteeonQualificationofMechanicalEquipmentUsed in Nuclear Facilities.The various parts of ASME QME-11994 were approved by ANSI on the following dates:SectionQP,September22,1992;SectionQR,June8,1993;SectionQR,NonmandatoryAppendixA,October 7, 1993; Secti

38、on QR, Nonmandatory Appendix B, May 14, 1993; and Section QV and itsNonmandatory Appendix A, February 17, 1994. Section QV was a revision and redesignation ofANSI B16.41-1983.QME-12002 was published in 2003. In September 2003, it was recognized that the Standardhad aspects, such as the process for v

39、alve qualification, that could better use new computeranalytical techniques and that were proscriptive in nature. In addition, seismic qualificationneededtobeupdatedtorecognizenewindustryguidance.Newsectionswereneededonstandard-ization of experience-based seismic equipment qualification and the qual

40、ification of dynamicrestraints. At the time, industry experience had demonstrated that qualification to QME-1 wasrequired without the specification of the parameters for which equipment needed to be qualified.The use of this Standard requires that a Qualification Specification be provided.ASME QME-1

41、2007 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 National Standard onJune 25, 2007.The 2012 edition of this Standard was approved as an American National Standard onSeptember 17, 2012.The 2017 edition of

42、this Standard was approved as an American National Standard onMarch 21, 2017.viRequests for interpretation or suggestions for improvement of this Standard should beaddressed to the Secretary of the ASME Committee on Qualification of Mechanical EquipmentUsed in Nuclear Facilities, The American Societ

43、y of Mechanical Engineers, Two Park Avenue,New York, NY 10016-5990.viiCOMMITTEE 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 COMMITTEE OFFICERSM. A. Pressburger, ChairT. M. Adams, V

44、ice ChairL. Powers, SecretaryK. Verderber, SecretarySTANDARDS COMMITTEE PERSONNELT. M. Adams, S 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 and Pressure Vessel Code(ASME BPVC) and to

45、Other Standards. When a referenceis made to any Section of the BPVC, or to other stan-dards, it shall be understood to mean the designatedarticle,paragraph,figure,ortableinthedesignateddoc-ument. All such references shall be identified in the textof this Standard by the documents issuing source andt

46、he documents unique identification number, e.g.,ASMEBPVC,SectionIII,SubsectionNF;IEEEStd627;or10CFR50 Part A. If required, further reference to uniquearticles or paragraphs of the referenced document mayalso be described, e.g., ASME BPVC, Section III,Subsection NF, subpara. NF-3211.1(a). Each short

47、refer-ence made in the text shall be described in more com-plete detail in Article 3000 by issuing source, uniqueidentification number, year of publication being refer-enced, and full title, e.g., IEEE Std 382-1980, Standardfor Qualification of Safety Related Valve Operators. Ref-erences listed with

48、out the year of publication suggestthat the latest version of the reference was used in thedevelopment of this Standard. It should be noted byusers of this Standard that regulatory requirements andCodes of Record for a particular nuclear power plantmay take precedence over references used within thi

49、sStandard. Section QR references applicable for bothxpumpsandvalvesshallbe describedinArticleQR-3000,while references unique to Section QP or Section QVonly will be described in Article QP-3000 orArticle QV-3000, as applicable.(c) References to Appendices. Two types of appendixare included in this Standard, designated Mandatoryand Nonmandatory. Both types of appendix are desig-natedbytheprefixQ.Thisisfollowedbyletter(s),whichare the same used by the section to which the appendixapplies, e.g., QR. Mandatory appendices containrequirements that must be followed in qualification;