IEEE 603-2009 en Standard Criteria for Safety Systems for Nuclear Power Generating Stations《核电站安全系统准则》.pdf

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13、2009 (Revision of IEEE Std 603-1998) IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations Sponsor IEEE Nuclear Power Engineering Committee of the IEEE Power +1 978 750 8400. Permission to photocopy portions of any individual standard for educational classroom use can also

14、be obtained through the Copyright Clearance Center. Introduction This introduction is not part of IEEE Std 603-2009, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations. This standard establishes minimum functional design criteria for the power, instrumentation, and contr

15、ol portions of nuclear power generating station safety systems. These criteria are established to provide a means for promoting appropriate practices for design and evaluation of safety system performance and reliability. However, adhering to these criteria will not necessarily fully establish the a

16、dequacy of any safety systems functional performance and reliability; nonetheless, omission of any of these criteria will, in most instances, be an indication of safety system inadequacy. Application The criteria established by this standard apply to those systems defined as safety systems and do no

17、t necessarily apply to all the structures, systems, and components required for comprehensive plant safety. Although the scope is limited to safety systems, many of the principles may have applicability to equipment provided for safe shutdown, accident monitoring display instrumentation, preventive

18、interlock features, or any other structures, systems, and components related to safety, or all of the above. To determine those systems subject to these criteria, an analysis of the overall plant response to postulated design basis events shall be performed. Good engineering judgment should be exerc

19、ised in this analysis so that the adequate margins exist in the design to protect the heath and safety of the public without imposing unduly restrictive criteria on the design. Interdisciplinary approach The safety system criteria herein are established using a systems approach to the design of the

20、power, instrumentation, and control portion of the safety system, as opposed to a specific engineering discipline approach (that is, electrical, mechanical, or civil). It is recognized that the safety functions cannot be accomplished without mechanical as well as electrical equipment and circuitry.

21、It shall also be recognized that some safety functions may be implemented using digital computers and computer programs. Therefore, the design by other disciplines should consider these criteria. In order for the safety system to meet the requirements of this standard and the supportive standards, t

22、he aggregate design of the safety system (without regard to discipline) may be constrained. For example, the consideration of common-cause failure is an item that requires interdisciplinary review and design solution. Such constraints are themselves implicit interface requirements imposed upon the i

23、ndividual constituent parts to enable the entire safety system to meet these requirements. The areas where this standard interfaces with other standards are shown in Figure 1. While this standard takes a systems approach to the design of the power, instrumentation, and control portion of the safety

24、system, it does not attempt to establish new or different criteria for mechanical equipment or components. Such an attempt by a user is a misapplication of this standard. Nor does this standard attempt to establish the system-level requirements that may be required by mechanical or civil equipment;

25、for example, in-service inspection of piping is intentionally excluded. This standard provides criteria for the safety system without conflicting with existing standards. This standard is not intended to duplicate or conflict with component design requirements such as the ASME Boiler and Pressure Ve

26、ssel Code B5.aRather this standard is to complement and interface with such documents. This standard and aThe numbers in brackets correspond to those of the bibliography in Annex C. iv Copyright 2009 IEEE. All rights reserved. others establish systems criteria while additional codes and standards es

27、tablish detailed requirements for the functional adequacy of the individual constituent parts of the safety system. Evolution This standard was evolved from IEEE Std 603-1980. It represents the latest Subcommittee 6 (SC-6) publication of a systems criteria document. The series began with IEEE Std 27

28、9-1968, a trial-use standard for protection systems. This was followed by IEEE Std 279-1971 B7, a standard for protection systems; IEEE Std 279-1971 has since been withdrawn. IEEE Std 603-1977, a trial use standard for safety systems was issued in 1977. IEEE Std 603 was revised and issued in 1980, 1

29、991, and 1998. This latest issue represents the current revision to the IEEE standard for safety systems. Relationship to other standards This standard establishes functional and design criteria that are general in nature. It requires supportive standards containing both general and detailed criteri

30、a to comprise a minimal set of requirements for the safety system. Other IEEE standards prepared in support of the criteria of this standard are referenced throughout this standard. Various other standards by organizations such as American National Standards (ANS), the International Atomic Energy Ag

31、ency (IAEA), International Electricity Commission (IEC), and American Society of Mechanical Engineers (ASME) provide additional information on aspects covered in this standard. International standard IEC 60231A (1969-01) also contains functional and design criteria for safety systems. The definition

32、 of the term safety system in Clause 3 references the Code of Federal Regulations Title 10 Part 100.bThis definition is the same as used by other groups, such as the ANS and Instrumentation Society of America (ISA). This is per agreements made with other organizations. Purpose of revision The purpos

33、e of this revision is to revise the existing standard document to 1) reflect current industry practices and user feedback, 2) align the document for compatibility with related IEEE standards, and 3) incorporate the results of future work items identified in the forward from the 1998 version of IEEE

34、Std 603. IEEE Std 603 was revised to recognize the issuance of IEEE Std 497-2002. Although the forward of IEEE Std 603-1998 stated that ANSI/ANS-4.5-1980 B1 and IEEE Std 497-1981 were to be combined as ANS 4.5, ANS 4.5-1989 was withdrawn and IEEE Std 497 was revised and issued in 2002. References to

35、 ANSI/ANS 51.1-1983, Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants, and ANSI/ANS 52.1-1983, Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants, were removed since these standards were withdrawn by the ANS. bInformation on referen

36、ces can be found in Clause 2. v Copyright 2009 IEEE. All rights reserved. Future work Annex B enhancements on EMI/RFI. Notice to users Laws and regulations Users of these documents should consult all applicable laws and regulations. Compliance with the provisions of this standard does not imply comp

37、liance to any applicable regulatory requirements. Implementers of the standard are responsible for observing or referring to the applicable regulatory requirements. IEEE does not, by the publication of its standards, intend to urge action that is not in compliance with applicable laws, and these doc

38、uments may not be construed as doing so. Copyrights This document is copyrighted by the IEEE. It is made available for a wide variety of both public and private uses. These include both use, by reference, in laws and regulations, and use in private self-regulation, standardization, and the promotion

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41、 effect. In order to determine whether a given document is the current edition and whether it has been amended through the issuance of amendments, corrigenda, or errata, visit the IEEE Standards Association web site at http:/ieeexplore.ieee.org/xpl/standards.jsp, or contact the IEEE at the address l

42、isted previously. For more information about the IEEE Standards Association or the IEEE standards development process, visit the IEEE-SA web site at http:/standards.ieee.org. Errata Errata, if any, for this and all other standards can be accessed at the following URL: http:/standards.ieee.org/readin

43、g/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/ index.html. vi Copyright 2009 IEEE. All rights reserved. vii Copyright 2009 IE

44、EE. All rights reserved. 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

45、therewith. The IEEE is not responsible for identifying Essential Patent Claims for which a license may be required, for conducting inquiries into the legal validity or scope of Patents Claims or determining whether any licensing terms or conditions provided in connection with submission of a Letter

46、of Assurance, if any, or in any licensing agreements are reasonable or non-discriminatory. Users of this standard are expressly advised that determination of the validity of any patent rights, and the risk of infringement of such rights, is entirely their own responsibility. Further information may

47、be obtained from the IEEE Standards Association. Participants At the time this standard was submitted to the IEEE-SA Standards Board for approval, the Safety Systems and Single Failure Criteria, Working Group 6.3 had the following membership: Royce D. Beacom, Chair Wesley W. Bowers Britton Grim Mich

48、ael H. Miller David Theriault Michael Waterman At the time this standard was submitted to the IEEE-SA Standards Board for approval, Subcommittee 6 under the Nuclear Power Engineering Committee (NPEC) had the following membership: David J. Zaprazny, Chair Mark Santschi, Secretary Ijaz Ahmad Royce D.

49、Beacom Wesley W. Bowers John J. Disosway Patrick Gove Ron Greenthaler Britton Grim Daryl L. Harmon David A. Horvath Randy C. Jamison Ron Jarrett Paul J. Loeser Barry S. Marcus Michael H. Miller W. R. Odess-Gillet Ifti Rana John B. Waclo Michael Waterman Paul Yanosy The following members of the individual balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention. William J. Ackerman Satish Aggarwal Stan Arnot George Ballassi Farouk Baxter Royce D. Beacom Robert Beavers William Bloethe Wesley W. Bowers Daniel Brosnan Nis