ASME QME-1-2002 Qualification of ACTV Mechanical Equipment used in Nuclear Power Plants (QME-1 - 2002)《核电厂中使用的放射性机械设备的合格证书》.pdf

《ASME QME-1-2002 Qualification of ACTV Mechanical Equipment used in Nuclear Power Plants (QME-1 - 2002)《核电厂中使用的放射性机械设备的合格证书》.pdf》由会员分享，可在线阅读，更多相关《ASME QME-1-2002 Qualification of ACTV Mechanical Equipment used in Nuclear Power Plants (QME-1 - 2002)《核电厂中使用的放射性机械设备的合格证书》.pdf（140页珍藏版）》请在麦多课文档分享上搜索。

1、The American Society of Mechanical Engineers AN - AMERICAN NATIONAL STANDARD QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR POWER PlANTS ASME QME-l-Ml2 (Revision of ASME QME-1-2000) Date of Issuance: February 20, 2003 The next edition of this Standard is scheduled for publication in 20

2、04. There will be no addenda issued to this edition. ASME issues written replies to inquiries concerning interpretations of technical aspects of this Standard. ASME is the registered trademark of The American Society of Mechanical Engineers. This code or standard was developed under procedures accre

3、dited as meeting the criteria for American National Standards. The Standards Committee that approved the code or standard was balanced to assure that individuals from competent and concerned interests have had an opportunity to participate. The proposed code or standard was made available for public

4、 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 not take any position with respect to t

5、he validity of any patent rights asserted in connection with any items mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability for infringement of any applicable letters patent, nor assume any such liability. Users of a code or standard are expressl

6、y advised that determination of the validity of any such patent rights, and the risk of infringement of such rights, is entirely their own responsibility. Participation by federal agency representative($ or person($ affiliated with industry is not to be interpreted as government or industiy endorsem

7、ent of this code or standard. ASME accepts responsibility for only those interpretations of this document issued in accordance with the established ASME procedures and policies, which precludes the issuance of interpretations by individuals. No part of this document may be reproduced in any form, in

8、 an electronic retrieval system or otherwise, without the prior written permission of the publisher. The American Society of Mechanical Engineers Three Park Avenue, New York, NY 10016-5990 Copyright O 2003 by THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS All rights reserved Printed in U.S.A. Foreword

9、 Standards Committee Roster . Summary of Changes Section QR General Requirements . QR-i000 Scope . QR-2000 Purpose Organization of QME-1 QR-3000 References QR-4000 Definitions QR-5000 Qualification Principles and Philosophy . QR-6000 Qualification Specification . QR-7000 Qualification Program . QR-8

10、000 Documentation . Nonmandatory Appendices to Section QR QRA Dynamic Qualification of Mechanical Equipment . QR-A1000 Scope . QR-A3000 References QR-A5000 QR-A6000 General Seismic Qualification Requirements . QR-A7000 Qualification Methods Attachment A Guidelines for Qualification by Similarity (In

11、direct Method) Attachment B Examples of Qualification of Pumps and Valves by Analysis . Attachment C Qualification of Pumps and Valves Using Natural Earthquake Appendix QR-A Figures QR-A6300-1 QR-A6300-2 QR-A6400-1 B2 B4 c1 c2 c3 QR-A2000 Purpose QR-A4000 Definitions Response . QR-A8000 Document ati

12、on . General Discussion of Earthquake Environment and Equipment Experience Data Horizontal Design Response Spectra Scaled to 1 g Horizontal Ground Acceleration Vertical Design Response Spectra Ccaled to 1 g Horizontal Ground Acceleration Seismic Qualification Required Input Motion (RIM) Finite Eleme

13、nt Formulation of Pump Assembly Finite Element Formulation of Butterfly Valve Assembly . Seismic Motion Bounding Spectrum Horizontal Ground Motion Limits of Experience Data for Motor-Operated Valves and Limits of Experience Data for Air-Operated Diaphragm Valves, Spring- B1 Pump Assembly B3 Butterfl

14、y Valve Assembly . Substantial Piston-Operated Valves Lightweight Construction . Damping Values: Percent of Critical Damping List of Input Parameters Operated Pressure Relief Valves, and Piston-Operated Valves of Appendix QR-A Tables QR-A6210-1 Al vi Viu X xii 11 13 19 24 27 31 41 16 17 18 32 33 37

15、38 42 44 45 14 28 iii A2 B1 B2 B4 B5 B6 87 B8 B9 LI3 QR- B QR-B1000 QR-B2000 QR-B3000 QR-B4000 QR-85000 QR-B6000 QR-B7000 Section QDR QDR-1000 QDR-2000 QDR-3000 QDR-4000 QDR-5000 QDR-6000 QDR-7000 Comparative List of Physical Parameters Frequencies . Beam Stresses. psi. for ACME Service Level B Beam

16、 Stresses. psi. for ACME Service Level C Plate Stresses. psi. for ACME Service Level B Plate Stresses. psi. for ACME Service Level C Calculated Frequencies for Pump/Motor Assembly: Print of Evaluation of Behavior at Critical Locations riiiowabk Siresses ai- 2“F fr 4 b-1 . Vdve . . Other Locations .

17、4 in . Valve Nodal Displacements. in., for ACME Service Level C Guide for Qualification of Nonmetallic Parts . Scope . Purpose References Definitions Requirements . Methods of Qualification Documentation . Qualification of Dynamic Restraints . Scope . Purpose Qualification Principles and Philosophy

18、. Qualification Prograrn . Definitions Functional Specification . Documentation Requirements . Nonmandatory Appendices to Section QDR QDRA QDR-A1000 QDR-A2000 QDR-A3000 QDR-A4000 QDR-A5000 QDR-A6000 QDR-B QDR-B1000 QDR-B2000 QDR-C QDR-Ci000 QDR-C2000 QDR-C3000 Section QP QP-i000 QP-2000 QP-3000 Q P

19、-4000 QP-5000 QP-6000 QP-7000 QP-8000 Functional Specification for Dynamic Restraints Scope . Purpose References Definitions Functional Specification Contents Filing Requirements . Restraint Similarity Examples of Design Similarity . Scope . Typical Values of Restraint Functional Parameters Scope .

20、Functional Parameters Aging and Service Condition Simulation Qualification Program Introduction Qualification of Active Pump Assemblies Scope . Purpose Qualification Principles and Philosophy . References Definitions Qualification Specification . Qualification Program . Documentation . 29 34 36 38 3

21、9 39 39 39 40 40 46 46 46 46 46 46 48 51 52 52 52 52 52 55 55 60 62 62 62 62 62 62 64 65 65 65 66 66 66 66 67 67 67 67 67 68 68 68 70 72 iv Nonmandatory Appendices to Section QP QP-A Pump Specification Checklist . QP-B Pump Shaft-Seal System Specification Checklist . QP-C Pump Turbine Driver Specifi

22、cation Checklist . QP-D Pump Similarity Checklist QP-E Guidelines for Shaft-Seal System Material and Design Consideration QP-E1000 Scope . QP-E2000 Purpose QP-E3000 Definitions QP-E4000 Material Considerations . QP-E5000 Design Considerations Appendix QP-E Tables QP-E1 Shaft-Seal System Specificatio

23、n QP-E2 Limits for Unbalanced Ceals . Section QV Functional Qualification Requirements for Active Valve Assemblies for Nuclear Power Plants . introduction QV-1000 Scope . QV-2000 Purpose QV-4000 Definitions QV-5000 Qualification Requirements QV-6000 Functional Qualification Specification QV-7000 Qua

24、lification Program . QVP-7000 Parent Valve Qualification . QVC-7000 Extension of Qualification From Parent to Candidate . QV-8000 Documentation Requirements . Nonmandatory Appendix to Section QV QV-3000 References QV-A QV-Al000 QV-A2000 QV-A3000 QV-A4000 QV-A5000 QV-A6000 QV-A7000 Section QV-G QV-Gl

25、OOO QV-G2000 QV-G3000 QV-G4000 QV-G5000 QV-G6000 QV-G7000 QV-G8000 Functional Specification for Active Valves for Nuclear Power Plants . Scope . References Definitions Functional Specification Contents Functional Specification Details . FiLing Requirements . Guide to Section QV: Determination of Val

26、ve Assembly Performance Characteristics Scope . introduction References Definitions Valve Assembly Performance Characteristic Requirements General considerations . Power-Actuated Valve Assembly Considerations . Valve Considerations Purpose 73 75 76 77 78 78 78 78 78 78 79 80 81 81 82 83 83 83 84 84

27、84 85 100 106 108 108 108 108 108 108 109 110 111 111 111 111 112 112 112 115 116 V Federal regulations applicable to nuclear power plants require that measures be established to ensure that certain equipment operates as specified. This Standard sets forth requirements and fidelines that may be used

28、 to ensure that active mechanical equipment is qualified for specified service 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 power plant component replacements, modifica

29、tions, or additions. In the early 1970s, initial development of qualification standards was assigned to the ANSI N45 Committee. The N45 Committee in turn established a task force to prepare two series of standards to ensure that pumps and valves used in nuclear plant systems would function as specif

30、ied. The N45 Committees valve task force (N278) was reassigned in 1974 to the American National Standards Committee B16 and designated Subcommittee H. The first qualification standard to be issued for valves was ANSI N278.1-1975, which covered the preparation of functional specifications. In 1982, t

31、he task force was reassigned to the ACME Committee on Qualification of Mechanical Equipment Used in Nuclear Power Plants (QME) and designated the Subcommittee on Qualification of Valve Assemblies. As an interim measure, in 1983, ANSI B16.41 was issued to cover functional qualification requirements f

32、or power-operated active valve assemblies for nuclear power plants. The N45 Committees pump task force (N551), established in 1973, was assigned to ACME Nuclear Power Codes and Standards along with N278 as part of the Subcommittee QNPE, Qualification of Nuclear Plant Equipment. Both N551 and N278 op

33、erated as Subcommittee QNPE until 1982, when they were reassigned to the ACME Committee on Qualification of Mechanical Equipment Used in Nuclear Power Plants (QME) and designated as the Subcommittee on Qualifi- cation of Valve Assemblies and the Subcommittee on Qualification of Pump Assemblies. In J

34、une 1977, an IEEE/ASME agreement was formulated giving primary responsibility for qualification standards to IEEE and quality assurance standards to ASME. This arrangement remained in effect until ACME established the current Committee on Qualification of Mechanical Equipment Used in Nuclear Power P

35、lants. During 1985, the Committee on Qualification of Mechanical Equipment Used in Nuclear Power Plants researched the various formats this Standard could take. Based on the wide acceptance of ACME Section IIIs format for multiple classes, the Committee adopted a similar organizational format to acc

36、ommodate multiple equipment types covered by this Standard. As IEEE Standards 323 and 627 had already been in use many years for electrical equipment, these standards were also studied for appropriate content that should be addressed for mechanical equipment. Subsequently, the following Organization

37、 Guide was developed for this Standard and submitted to the ACME Board on Nuclear Codes and Standards for approval. On January 16, 1986, the Board on Nuclear Codes and Standards approved QMEs approach and outline for this Standard. Consistent with the guidance in ACME SI-9, ACME Guide for Metricatio

38、n of Codes and Standards SI (Metric Units) regarding metrication, SI units have been provided in narrative portions of QME-1 for 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 consistently thr

39、oughout construction of the component. Should the owner or his agent desire metric units, it sili be set forth in the design specifications. The various parts of ACME QME-1-1994 were approved by the American National Standards Institute (ANSI) on the following dates: Section QP, September 22,1992; S

40、ection QR, June 8,1993; Section QR, Appendix A, October 7, 1993; Section QR, Appendix B, May 14, 1993; and Section QV and its Appendix A, February 17,1994. Section QV is a revision and redesignation of ANSI Requests for interpretation or suggestions for improvement of this Standard should be address

41、ed to the Secretary of the ASME Committee on Qualification of Mechanical Equipment B16.41-1983. vi Used in Nuclear Power Plants, The American Society of Mechanical Engineers, Three Park Avenue, New York, NY 10016-5990. In 1996 the Board of Nuclear Codes and Standards requested ali committees reporti

42、ng to it to add SI (metric) units to all documents by replacing Customary (English) units with SI units or by showing SI units in a dual format with Customary units. The decision as to the extent of the conversion and format was left to the various committees. The Committee on Qualification of Mecha

43、nical Equipment for Nuclear Power Plants voted in 1996 to present SI units in the QME document, with Customary units in parentheses. A group of proposed changes was prepared at that time. The changes encountered a good deal of opposition. The Committee on Qualification of Mechanical Equipment for Nu

44、clear Power Plants revisited this decision at its February 29, 2000 meeting and voted to publish QME-1 with dual units, Customary as the primary units, with SI units in parentheses. This decision was further modified by the Committee to make the change apply to textual material only. Tables and figu

45、res were not to be modified. The changes made herein confirm with those decisions. The changes apply to the text as it appeared in the 1997 edition of QME-1. This Standard was approved as an American National Standard on October 31,2002. Vii COMMITTEE ON QUALIFICATION OF MECHANICAL EQUIPMENT SD PN N

46、UCLEAR FACIMTES (The following is the roster of the Committee at the time of approval of this Standard.) OFFICERS R. H. Wessman, Chair J. H. Karian. Secretary COMMITTEE PERSONNEL T. M. Adams G. A. Antaki R. W. Barnes F. R. Drahos J. R. Hoistmm S. ishimoto H. S. Koski, Jr. D. B. Nickerson, Chair F. R

47、. Drahos A. A. Fraser R. T. Hebert D. C. Stanze, Chair R. G. Visalli, Secretory H. R. Beck I. L Belt2 R. J. Cradle H. i. Gregg J. R. Holstmm B. N. Roy T. P. Ruggiem. Jr. H. S. Koski, Ir., Chair R. E. Richards, Vice Chair J. D. Page, Secretary D. Egonis H. R. Sonderegger. Chair T. M. Adams T. M. Adam

48、s G. A. Antaki R. D. Burns W. N. Mclean D. B. Nickerson T. P. Ruggiem H. C. ShafFer 111 A. G. Smyth H. R. Sonderegger D. C. Stanze SUBCOMMITTEE ON QUALIFICATION OF PUMP ASSEMBLIES S. Ishimoto J. R. Rajan B. N. Roy H. C. ShaRer 111 SUBCOMMITTEE ON QUALIFICATION OF VALVE ASSEMBLIES T. G. Scarbrough G.

49、 L. Smith A. G. Smyth H. R. Sonderegger R. Steele, Ir. Y. Takayama D. G. Thibault J. C. Watkins SUBCOMMITTEE ON QUALIFICATION OF ACTIVE DYNAMIC RESTRAINTS R. E. Fandetti D. V. Hoang M. A. Pressburger M. D. Shutt SUBCOMMITTEE ON GENERAL REQUIREMENTS (QR) S. ishimoto H. C. Shafer 111 SUBCOMMITTEE ON DYNAMIC QUALIFICATION K. A. Manoly D. P. Moore J. M. Richards viii S. Norman, Chair M. Pressburger, Secretory A. Barth D. Boes L. Camacho R. Fandetti SUBGROUP ON QDR DEVELOPMENT D. Hoang L. Phares M. Potter R. Richards M. Shutt ix ORGANIZATION OF QME-1 1 GENERAL ACME QME-1 is divided into