IEEE-344-2004.pdf
《IEEE-344-2004.pdf》由会员分享,可在线阅读,更多相关《IEEE-344-2004.pdf(65页珍藏版)》请在三一文库上搜索。
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
- 配套讲稿:
如PPT文件的首页显示word图标,表示该PPT已包含配套word讲稿。双击word图标可打开word文档。
- 特殊限制:
部分文档作品中含有的国旗、国徽等图片,仅作为作品整体效果示例展示,禁止商用。设计者仅对作品中独创性部分享有著作权。
- 关 键 词:
- IEEE 344 2004
链接地址:https://www.31doc.com/p-3771617.html