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1、Recognized as an American National Standard (ANSI) IEEE Std 805-1984 IEEE Recommended Practice for System Identification in Nuclear Power Plants and Related Facilities Sponsor Power Generation Committee of the IEEE Power Engineering Society Approved June 23, 1983 IEEE Standards Board Approved Novemb
2、er 15, 1984 American National Standards Institute Copyright 1984 by The Institute of Electrical and Electronics Engineers, Inc 345 East 47th Street, New York, NY 10017, USA No part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior wr
3、itten permission of the publisher. IEEE Standards documents are developed within the Technical committees of the IEEE Societies and the Standards Coordinating Committees of the IEEE Standards Board. Members of the committees serve voluntarily and without compensation. They are not necessarily member
4、s of the Institute. The standards developed within IEEE represent a consensus of the broad expertise on the subject within the Institute as well as those activities outside of IEEE which have expressed an interest in participating in the development of the standard. Use of an IEEE Standard is wholly
5、 voluntary. The existence of an IEEE Standard does not imply that there are no other ways to produce, test, measure, purchase, market, or provide other goods and services related to the scope of the IEEE Standard. Furthermore, the viewpoint expressed at the time a standard is approved and issued is
6、subject to change brought about through developments in the state of the art and comments received from users of the standard. Every IEEE Standard is subjected to review at least once every five years for revision or reaffirmation. When a document is more than five years old, and has not been reaffi
7、rmed, it is reasonable to conclude that its contents, although still of some value, do not wholly reflect the present state of the art. Users are cautioned to check to determine that they have the latest edition of any IEEE Standard. Comments for revision of IEEE Standards are welcome from any inter
8、ested party, regardless of membership affiliation with IEEE. Suggestions for changes in documents should be in the form of a proposed change of text, together with appropriate supporting comments. Interpretations: Occasionally questions may arise regarding the meaning of portions of standards as the
9、y relate to specific applications. When the need for interpretations is brought to the attention of IEEE, the Institute will initiate action to prepare appropriate responses. Since IEEE Standards represent a consensus of all concerned interests, it is important to ensure that any interpretation has
10、also received the concurrence of a balance of interests. For this reason IEEE and the members of its technical committees are not able to provide an instant response to interpretation requests except in those cases where the matter has previously received formal consideration. Comments on standards
11、and requests for interpretations should be addressed to: Secretary, IEEE Standards Board 345 East 47th Street New York, NY 10017 USA iii Foreword (This Foreword is not a part of IEEE Std 805-1984, IEEE Recommended Practice for System Identification in Nuclear Power Plants and Related Facilities.) In
12、 April 1979, the Working Group on Unique Identification in Power Plants of the Station Design Subcommittee was formed and charged with the task of producing a series of recommended practices for unique identification in power plants. Later, realizing that this concept provided the same benefits to o
13、ther types of facilities, the title was extended to include and related facilities. This series of recommended practices, entitled the Energy Industry Identification Systems (ELIS), provides a single source of unique identification of systems, structures, and components for all types of power genera
14、tion and related facilities with provision for the inclusion of currently established plant system identifier codes. Using this series of recommended practices, which includes principles, a table of component function identifier codes, implementation instructions, and system descriptions for the var
15、ious types of power plants and related facilities, a user can correlate a system, structure, or component with another organization for purposes of reporting, comparison, or general communication. Numerous economic, safety, and convenience benefits can be derived from this concept. IEEE Std 805 deal
16、s with system descriptions and system codes for nuclear power plant systems. The purpose of this working group was to generate an industry-wide language of communication which users could employ at the interface of their organizations and which would not require them to change a viable identificatio
17、n concept which they were using internally. In the event that the users do not have a viable identification concept of their own, they may choose to employ this concept for their internal applications since it has been successfully applied by several utilities and architect/engineering firms. If con
18、flicts with other standards are discovered, they will be handled in a revision. This recommended practice was prepared by the Working Group for Unique Identification in Power Plants and Related Facilities, Station Design Subcommittee of the Power Generation Committee. At the time this recommended pr
19、actice was approved, the members of the working group were: J. L. Parris, Chair O. M. Anderson Alex Barlas M. R. Belew V. T. Carlson L.T. Gordon D.T. Hall F. J. Hebdon W. C. Henry P. J. Hoefler F. H. Hoernschmeyer S. Jordan J. R. Koupal S. Mukho R. D. Nalven D. A. Norman F. M. Patterson R. W. Rohwed
20、er C. O. Remine M. H. Rothstein P. D. Sierer, Jr R. L. Simard G. E. Simoneaux F. W. Sloat J. G. Staudt At the time the IEEE Standards Board approved this standard on June 23, 1983 it had the following members: James H. Beall, Chair Edward Chelotti, Vice Chair Sava I. Sherr, Secretary J. J. Archambau
21、lt John T. Boettger J. V. Bonucchi Rene Castenschiold Edward J. Cohen Len S. Corey Donald C. Fleckenstein Jay Forster Donald H. Heirman Irvin N. Howell Joseph L. Koepfinger* Irving Kolodny George Konomos R. F. Lawrence John E. May iv Donald T. Michael* John P. Riganati Frank L. Rose Robert W. Seelba
22、ch Jay A. Stewart Clifford O. Swanson Robert E. Weiler W. B. Wilkens Charles J. Wylie *Member emeritus At the time this recommended practice was approved, the members of the Power Generation Committee were: R. Zwigler, Chair D. Diamant, Vice Chair R. W. Cantrell, Secretary J. C. Appiarius W. W. Avri
23、l M. S. Baldwin J. H. Bellack I. B. Berezowski G. Berman G. C. Boyle F. L. Brennan P. G. Brown E. F. Chelotti H. E. Church, Jr C. H. Clarridge R. S. Coleman R. E. Cotta M. L. Crenshaw R. S. Darke P. Davidson A. C. Dolbec G. R. Engman W. H. Esselman V. F. Estcourt T. F. Faulkner W. M. Fenner A. H. Fe
24、rber D. I. Gorden R. D. Handel J. J. Heagerty M. E. Jackowski E. F. Kaprielian F. E. Keay P. R. Landrieu S. Law P. Lewis H. E. Lokay G. L. Luri J. T. Madill J. D. Mather O. S. Mazzoni A. J. McElroy T. M. McMahon J. L. Mills W.S. Morgan P. A. Nevins S. Nikolokockos J. T. Nikolas R. E. Penn J. D. Plax
25、co R. J. Reiman F. D. Robbins D. E. Roberts W.J. Rom Rg Scott J. J. Seibert M. N. Sprouse A. J. Spurgin R. B. Squires J. V. Stephens G. I. Stillman J. E. Stoner, Jr V. C. Sulzberger S. Tjepkema R. H. Waltman E. J. Warchol M. Warren K. L. West J. P. Whooley R. F. Willet C. J. Wylie T. D. Younkins Com
26、ments, suggestions, and requests for interpretation may be addressed to: Secretary IEEE Standards Board The Institute of Electrical and Electronic Engineers, Inc. 345 East 47th Street New York, NY 10017 Authorized licensed use limited to: SOUTH CHINA UNIVERSITY OF TECHNOLOGY. Downloaded on March 25,
27、 2009 at 00:07 from IEEE Xplore. Restrictions apply. v CLAUSEPAGE 1. Scope and Purpose 1 2. Discussion.1 3. References.2 4. Conventions 8 5. System Descriptions14 Copyright 1984 IEEE All Rights Reserved1 IEEE Recommended Practice for System Identification in Nuclear Power Plants and Related Faciliti
28、es 1. Scope and Purpose 1.1 Scope This recommended practice provides a single source of nuclear power plant system descriptions which, along with related recommended practices concerning unique identification principles and definitions, component function identifiers, and implementation instructions
29、, makes up a concept for uniquely identifying systems, structures, and components of light water nuclear power plant projects (electric power generating stations) and related facilities. Fossil, hydro, and other types of power plants are not included in this edition. 1.2 Purpose The purpose of this
30、series of recommended practices is to present a common language of communication which will permit a user to correlate a system, structure, or component with another organization for the purposes of reporting, comparison, or general communication. It does not require a using organization to change i
31、ts own internal identification concept, but if the organization chooses to do so it has only to transcode at the interface from their internal language to this common language concept. The user may choose to adopt this concept for internal organizational use. It represents the accumulated practice o
32、f the industry assimilated into one set of practices. A significant feature of this concept is that the unique identification code identifies the function at the component level and not the hardware itself. 2. Discussion The system descriptions concentrate on system function and include such interna
33、l details as is necessary to clearly support the system function description. They are not intended to serve as design input. System diagrams also show connections with major interfacing systems, and major components in these interfacing systems, where appropriate to enhance communication of the sys
34、tem function. The system description grouping, as indicated by the first character of 2Copyright 1984 IEEE All Rights Reserved IEEE Std 805-1984IEEE RECOMMENDED PRACTICE FOR SYSTEM IDENTIFICATION the two-alpha-character code, is designed to favor the convenience of plant operation rather than plant
35、design and construction. The system descriptions and diagrams represent typical systems and are not intended for design purposes. When a system function can be accomplished by significantly different system internal designs, the system description includes a brief identification of major design alte
36、rnatives to serve as an aid for correlating plant specific system designs with this classification concept. The differences among PWR system nomenclature and system designs were not included in this classification concept because of the functional similarity among the different PWR designs, A single
37、 set of system nomenclature and system boundaries has been defined for all PWR designs. The major differences between PWR and BWR system nomenclature and system internal designs have been preserved in that separate system descriptions and diagrams are provided, where appropriate. The symbols used in
38、 the system diagrams were selected to represent accepted practice as much as possible. 3. References When the following standards referred to in this recommended practice are superseded by a revision, the latest revision shall apply. 1 ANSI/IEEE Std 100-1977, IEEE Standard Dictionary of Electrical a
39、nd Electronics Terms. 2 IEEE Std 803-1983, IEEE Recommended Practice for Unique Identification in Power Plants and Related FacilitiesPrinciples and Definitions. 3 IEEE Std 803A-1983, IEEE Recommended Practice for Unique Identification in Power Plants and Related FacilitiesComponent Function Identifi
40、ers. 4 IEEE Std 804-1983, IEEE Recommended Practice for Unique Identification in Power Plants and Related FacilitiesImplementation. Table 1EIIS System ListAlphabetical by System Code A Primary Heat Source Systems Group AAControl Rod Drive System (BWR)Fig 2 AAControl Rod Drive System (PWR)Fig 3 ABRea
41、ctor Coolant System (PWR)Fig 4 ACReactor Core System ADReactor Recirculation System (BWR)Fig 5 B Engineered Safety Systems Group BAAuxiliary/Emergency Feedwater System (PWR) BBContainment Combustible Gas Control System BCContainment Ice Condenser System (PWR) Refrigeration SubsystemFig 8 BCContainme
42、nt Ice Condenser System (PWR) Ice Condenser SubsystemFig 9 BDContainment Leakage Control System BEContainment Spray System (PWR)Fig 10 BFContainment Vacuum Relief System Copyright 1984 IEEE All Rights Reserved3 IN NUCLEAR POWER PLANTS AND RELATED FACILITIESIEEE Std 805-1984 BGHigh-Pressure Core Spra
43、y System (BWR)Fig 11 BHEmergency/Standby Gas Treatment SystemFig 12 BIEssential Service Water SystemFig 13 BJHigh-Preseure Coolant Injection System (BWR)Fig 14 BKContainment Fan Cooling System (PWR)Fig 15 BLIsolation Condenser System (BWR)Fig 16 BMLow Pressure Core Spray System (BWR)Fig 17 BNReactor
44、 Core Isolation Cooling System (BWR)Fig 18 BOResidual Heat Removal/Low Pressure Coolant Injection System (BWR)Fig 19 BPResidual Heat Removal/Low Pressure Safety Injection System (PWR)Fig 20 BQHigh Pressure Safety Injection System (PWR)Fig 21 BRStandby Liquid Control System (BWR)Fig 22 BSUltimate Hea
45、t Sink System BTSuppression Pool Makeup System (BWR)Fig 23 C Reactor Auxiliaries Systems Group CABoron Recycle System (PWR)Fig 24 CBChemical and Volume Control/Makeup and Purification System (PWR)Fig 25(a) and (b) CCClosed/Component Cooling Water SystemFig 26 CDControl Rod Drive Cooling System (PWR)
46、Fig 27 CEReactor Water Cleanup System (BWR)Fig 28 CFReactor Services System CGSuppression Pool Purification System (BWR)Fig 29 D Fuel Management Systems Group DAFuel Pool Cooling and Purification System DBNuclear Fuel Services System DCDiesel Fuel Oil SystemFig 30 DRFuel Oil Receiving Storage, and T
47、ransfer SystemFig 31 DFNuclear Fuel Transfer System E Electrical Power Systems Group EAMedium-Voltage Power System (601V through 35 kV)Fig 32 EBMedium-Voltage Power SystemClass 1EFig 33 ECLow-Voltage Power System (600V and less)Fig 34 EDLow-Voltage Power SystemClass 1EFig 35 EEInstrument and Uninter
48、ruptible Power SystemFig 36 EFInstrument and Uninterruptible Power SystemClass 1EFig 37 E1DC Power SystemFig 38 EJDC Power SystemClass 1EFig 39 EKEmergency Onsite Power Supply SystemFig 40 ELMain Generator Output Power SystemFig 41 F Electrical Support Systems Group FACable Raceway System Table 1EII
49、S System ListAlphabetical by System Code (Continued) 4Copyright 1984 IEEE All Rights Reserved IEEE Std 805-1984IEEE RECOMMENDED PRACTICE FOR SYSTEM IDENTIFICATION FBCathodic Protection System FCGrounding and Lightning Protection System FDHeat Tracing System FEHeat Tracing SystemClass 1E FFNormal AC Lighting System FGStandby AC Lighting System FHEmergency DC Lighting System FICommunications System FJStation Generation Telemetering System FKSwitchyard System I Instrumentation and Monitoring Systems Group IASecurity System IBAnnunciator Sy
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