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1、IEEE Std 344-2004 (Revision of IEEE Std 344-1987) 344 TM IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations 3 Park Avenue, New York, NY 10016-5997, USA IEEE Power Engineering Society Sponsored by the Nuclear Power Engineering Committee 8 J
2、une 2005 Print: SH95327 PDF: SS95327 -,-,- IEEE Std 344 -2004 (Revision of IEEE Std 344-1987) IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations Sponsor Nuclear Power Engineering Committee of the IEEE Power Engineering Society Approved 8 D
3、ecember 2004 IEEE-SA Standards Board -,-,- The Institute of Electrical and Electronics Engineers, Inc. 3 Park Avenue, New York, NY 10016-5997, USA Copyright 2005 by the Institute of Electrical and Electronics Engineers, Inc. All rights reserved. Published 8 June 2005. Printed in the United States of
4、 America. IEEE is a registered trademark in the U.S. Patent +1 978 750 8400. Permission to photocopy portions of any individual standard for educational classroom use can also be obtained through the Copyright Clearance Center. NOTEAttention is called to the possibility that implementation of this s
5、tandard may require use of subject matter covered by patent rights. By publication of this standard, no position is taken with respect to the existence or validity of any patent rights in connection therewith. The IEEE shall not be responsible for identifying patents for which a license may be requi
6、red by an IEEE standard or for conducting inquiries into the legal validity or scope of those patents that are brought to its attention. -,-,- iv Copyright 2005 IEEE. All rights reserved. Introduction This revision of IEEE Std 344-1987 was developed to expand and clarify guidance for developing prog
7、rams to seismically qualify Class 1E equipment for nuclear power generating stations. Specific areas of amplification included are based on experience gained since 1987. The Class 1E equipment to be qualified by procedures or standards based upon this revised recommended practice can be of many form
8、s; therefore, this recommended practice presents the guidelines for many acceptable seismic qualification methods with the intent of permitting the user to make a judicious selection from the options offered. This revised recommended practice attempts to define more fully the procedures by which Cla
9、ss 1E equipment can be seismically qualified. It presents the methods that are known by the working group to be practices that are acceptable to the nuclear power generation industry, its equipment suppliers, and the industrial test and analysis facilities utilized by the industry. The clarification
10、 and update of methods in this recommended practice reflect an effort to recommend state-of-the-art techniques at the time of publication. The methods and definitions presented in this revision are not intended to limit other seismic qualification techniques. Exceptions to these recommended practice
11、s may be made at any time where it can be shown that the substituted procedure verifies that the equipment can perform its safety function with justifiable methodology. The basis for a technical justification may be, but is not limited to, partial analysis, tests on similar equipment, experience dat
12、a, or a combination thereof. Engineering judgment may be used in conjunction with these methods. Exceptions to these guidelines, which are founded on a broad base of actual test, analysis, and earthquake experience, supplemented by engineering judgment, may be used to meet the intent of this standar
13、d, provided the methods are justified. The Foreword of the 1987 revision of this standard noted that experience-based methods for seismic qualification of equipment were under development, and Clause 9 of the 1987 revision contained interim guidance for the use of experience data for this purpose. S
14、ince then, development of the experience-based approach has been furthered by the Seismic Qualification Utility Group (SQUG). The SQUG approach was used at many nuclear power plants to resolve USI A-46. It has also been adopted, in part, and used by other governmental and industrial organizations. A
15、ccordingly, Clause 10 and relevant parts of Clause 11 of this revision of the standard have been rewritten to incorporate the results of this development. Use of the experience-based approach in this recommended practice is acceptable for use in nuclear plants if it is consistent with the plants lic
16、ensing/regulatory design basis. Issues related to use of median-centered in-structure response spectra for the earthquake experience-based method, operating basis earthquake (OBE) requirements associated with the test experience method, and generation of a test-experience spectrum were considered at
17、 length by the working group in the preparation of this document. Further guidance for qualification of replacement components and devices within an existing, previously qualified larger equipment assembly by the earthquake experience-based method is deferred to the next revision of the standard. Sp
18、ecial consideration could be added to determine how to extend earthquake experience data to replacement of components and devices in a previously qualified equipment assembly so that there is sufficient detail and traceability in the areas of equipment performance (physical configuration, operationa
19、l, and dynamic), installation, excitation, and demonstration of safety function. Adherence to this recommended practice to obtain equipment seismic qualification alone will not suffice for assurance of public health and safety since it is the integrated performance of structures, fluid systems, This
20、 introduction is not part of IEEE Std 344-2004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations. -,-,- Copyright 2005 IEEE. All rights reserved. v instrumentation systems, electrical systems, and man/machine interface systems of a nucle
21、ar power generating station that establishes totally safe operating conditions. This standard was prepared by Subcommittee 2 Working Group 2.5 (Seismic) of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. Notice to users Errata Errata, if any, for this and all other sta
22、ndards can be accessed at the following URL: http:/ standards.ieee.org/reading/ieee/updates/errata/index.html. Users are encouraged to check this URL for errata periodically. Interpretations Current interpretations can be accessed at the following URL: http:/standards.ieee.org/reading/ieee/interp/ i
23、ndex.html. Patents Attention is called to the possibility that implementation of this standard may require use of subject matter covered by patent rights. By publication of this standard, no position is taken with respect to the existence or validity of any patent rights in connection therewith. The
24、 IEEE shall not be responsible for identifying patents or patent applications for which a license may be required to implement an IEEE standard or for conducting inquiries into the legal validity or scope of those patents that are brought to its attention. Participants At the time this standard was
25、balloted, Working Group SC 2.5 (Seismic) of Subcommittee 2 (Qualification) of the Nuclear Power Engineering Committee had the following membership: James Parello, a Chair a Member of the Writing Group b Past Chair of the Working Group Mostafa A. Ahmeda Paul D. Baughmana Suresh Channarasappaa Garry V
26、. Chapmana Pei-Ying Chena Walter Djordjevica Robert Enis Gregory Ferguson Gregory Hardy Paul Ibanez Johnny Jenkins Robert Kassawara Mohsin Khan Bruce M. Lorya William LaPayb Darren Martin Donald P. Moorea Karur S. Parthasarathy Daniel J. Pomerening John M. Richardsa William Schmidta K. M. Skreinerb
27、Donald Smith Richard G. Starcka vi Copyright 2005 IEEE. All rights reserved. At the time this standard was balloted, Subcommittee 2 (Qualification) under the Nuclear Power Engineering Committee had the following membership: Satish K. Aggarwal, Chair Robert Lofaro, Secretary At the time this standard
28、 was balloted, the Nuclear Power Engineering Committee had the following membership: John P. Carter, Chair John J. Disosway, Vice Chair David A. Horvath, Secretary Bohumil Bartonicek Paul D. Baughman Anup K. Behera Brij M. Bharteey Thomas Brewington Nissen M. Burstein Craig R. Butcher Steve Casadeva
29、ll Suresh Channarasappa Garry V. Chapman Javier Alonso Chicote Marty Chipkin Jeff Chivers Sun Yeong Choi James M. Dean Liviu Nicolae Delcea Dennis E. Dellinger Philip DiBenedetto Quang H. Duong Frank Drumm Wells D. Fargo Artur J. Faya Robert Francis James F. Gleason Patrick Gove William L. Hadovski
30、Peter Helander Thomas R. Hencey III Jerrell C. Henley David A. Horvath Craig S. Irish Serena A. Jagtiani-Krause Sushant Kapur Mohsin Khan Henry Leung Bruce M. Lory Darin R. Martin P. G. McQuillan Daniel R. Mikow Todd Mitton Asif Mohiuddin Edward Mohtashemi Carole Monchy-Leroy Bill Newell James Parel
31、lo Janez Pavsek Daniel J. Pomerening Robert Queenan John M. Richards Fredrick Roy Steve Sandberg Glen E Schinzel Roderick Simms Kjell Spang Richard G. Starck Marek Tengler Marco Van Uffelen Laszlo Varga Carl Weber John Wheless John White Toni Wittamore Richard T. Wood Toshio Yamamoto Satish K. Aggar
32、wal Ijaz Ahmad George Attarian Farouk D. Baxter Brij M. Bharteey Wesley W. Bowers Daniel F. Brosnan Nissen M. Burstein Robert C. Carruth Surin K. Dureja Stephen A. Fleger Robert Fletcher Robert B. Fuld James F. Gleason Dale Goodney Britton P. Grim Paul R. Johnson Harvey C. Leake John D. MacDonald J.
33、 Scott Malcolm Alexander Marion Michael H. Miller Gerald L. Nicely Roger D. Parker Glen E. Schinzel Neil P. Smith James E. Stoner John Taylor James E. Thomas Terence J. Voss John Waclo John White Paul L. Yanosy, Sr. David J. Zaprazny Copyright 2005 IEEE. All rights reserved. vii The following member
34、s of the individual balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. When the IEEE-SA Standards Board approved this standard on 8 December 2004, it had the following membership: Don Wright, Chair Steve M. Mills, Vice Chair Judith Gorman,
35、Secretary *Member Emeritus Also included are the following nonvoting IEEE-SA Standards Board liaisons: Satish K. Aggarwal, NRC Representative Richard DeBlasio, DOE Representative Alan Cookson, NIST Representative Don Messina IEEE Standards Project Editor Satish K. Aggarwal Faropuk D. Baxter Wesley W
36、. Bowers Thomas Brewington Daniel F. Brosnan Nissen M. Burstein Salvatore Carfagno John P. Carter Suresh Channarasappa Garry V. Chapman Dr. Guru Dutt Dhingra Philip DiBenedetto John J. Disosway Surin Dureja Amir El-Sheikh Jay Forster James F. Gleason Lawrence Gradin Britton P. Grim Randall Groves Aj
37、it Gwal Paul R. Johnson Harvey C. Leake John D. MacDonald G. Michel William Mindick James Parello Roger D. Parker Fredrick Roy James Ruggieri Neil P. Smith Richard G. Starck James E. Stoner James E. Thomas John Ullo Terence J. Voss John White Paul L. Yanosy, Sr. Li Zhang Chuck Adams Stephen Berger M
38、ark D. Bowman Joseph A. Bruder Bob Davis Roberto de Marca Boisson Julian Forster* Arnold M. Greenspan Mark S. Halpin Raymond Hapeman Richard J. Holleman Richard H. Hulett Lowell G. Johnson Joseph L. Koepfinger* Hermann Koch Thomas J. McGean Daleep C. Mohla Paul Nikolich T. W. Olsen Ronald C. Peterse
39、n Gary S. Robinson Frank Stone Malcolm V. Thaden Doug Topping Joe D. Watson -,-,- viiiCopyright 2005 IEEE. All rights reserved. Contents 1.Overview 1 1.1 Scope 1 1.2 Purpose. 2 2.Normative references. 2 3.Definitions . 2 4.General discussion of earthquake environment and equipment response . 5 4.1 E
40、arthquake environment 5 4.2 Equipment on foundations. 5 4.3 Equipment on structures 5 4.4 Simulating the earthquake . 6 4.5 Support structure and interactions . 7 5.Seismic qualification approach 7 6.Damping. 8 6.1 Introduction 8 6.2 Measurement of damping 8 6.3 Application of damping. 9 7.Analysis
41、. 10 7.1 Introduction 10 7.2 Dynamic analysis. 10 7.3 Static coefficient analysis 12 7.4 Nonlinear equipment response. 12 7.5 Other dynamic loads 13 7.6 OBE and SSE analysis. 13 7.7 Documentation of analysis. 13 8.Testing . 13 8.1 Introduction 13 8.2 Proof and generic testing . 17 8.3 Fragility test
42、ing 18 8.4 Device testing 18 8.5 Assembly testing 18 8.6 Test methods 19 8.7 Test documentation 29 Copyright 2005 IEEE. All rights reserved. ix 9.Combined analysis and testing. 29 9.1 Introduction 29 9.2 Modal testing . 29 9.3 Extrapolation for similar equipment 31 9.4 Shock testing 32 9.5 Extrapola
43、tion for multicabinet assemblies. 33 9.6 Other test/analysis 33 10.Experience 33 10.1 Introduction 33 10.2 Earthquake experience data . 33 10.3 Test experience data. 37 10.4 Special considerations 39 11.Documentation. 40 11.1 General. 40 11.2 Qualification specification requirements.41 11.3 Seismic
44、qualification report. 41 Annex A (informative) Measurement of ZPA. 45 Annex B (informative) Frequency content and stationarity 46 Annex C (informative) Fragility testing 47 Annex D (informative) Test duration and number of cycles. 49 Annex E (informative) Statistically independent motions. 52 Annex
45、F (informative) Bibliography. 53 -,-,- Copyright 2005 IEEE. All rights reserved. 1 IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations 1. Overview This recommended practice is divided into 11 clauses. Clause 1 provides the scope of this rec
46、ommended practice. Clause 2 lists normative references to other standards that are useful in applying this recommended practice. Clause 3 provides definitions that are either not found in other standards or have been modified for use with this recommended practice. Clause 4 provides background infor
47、mation on earthquake behavior and on the performance of equipment during simulated seismic events. Clause 5 defines the most commonly used methods for seismic qualification of equipment contained in this recommended practice. Clause 6 provides guidance on the measurement and application of damping i
48、n the seismic qualification of equipment. Clause 7 provides procedures for two approaches most commonly used to seismically qualify equipment by analysis. Clause 8 provides procedures for the commonly used methods for seismic qualification of equipment by test. Clause 9 provides guidelines for seism
49、ic qualification of equipment that cannot be practically qualified by analysis or testing alone. Clause 10 provides guidelines for two approaches to seismically qualify equipment using experience data for a reference equipment class. Clause 11 provides documentation guidelines for the seismic qualification of eq