1、The Institute of Electrical and Electronics Engineers, Inc.345 East 47th Street, New York, NY 10017-2394, USACopyright 1996 by the Institute of Electrical and Electronics Engineers, Inc.All rights reserved. Published 1996. Printed in the United States of America.ISBN 1-55937-581-7No part of this pub
2、lication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher.IEEE Std 387-1995(R2007)(Revision of IEEE Std 387-1984)IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power G
3、enerating StationsSponsorNuclear Power Engineering Committeeof theIEEE Power Engineering SocietyReaffirmed 27 September 2007Approved 12 December 1995IEEE-SA Standards BoardReaffirmed 24 April 2008Approved 1 August 1996American National Standards InstituteAbstract: The criteria for the application an
4、d testing of diesel-generator units as Class 1E standbypower supplies in nuclear power generating stations is described.Keywords: aging classification, auxiliary equipment, capability, controls, design criteria, designfeatures, diesel-generator units, documentation requirements, engine, generator, l
5、oad profile,modifications, operation, periodic testing, pre-operational testing, production testing, protection,qualification requirements, rating, records, reliability program, scope, seismic qualification, site test-ing, standby power supply, testing requirements, test parameters, type testingIEEE
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16、 Copyright Clearance Center.Note: Attention is called to the possibility that implementation of this standard mayrequire 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 inconnection th
17、erewith. The IEEE shall not be responsible for identifying all patents forwhich a license may be required by an IEEE standard or for conducting inquiries intothe legal validity or scope of those patents that are brought to its attention.iiiIntroduction(This introduction is not part of IEEE Std 387-1
18、995, IEEE Standard Criteria for Diesel-Generator Units Applied asStandby Power Supplies for Nuclear Power Generating Stations.)This standard supplements IEEE Std 308-1991, IEEE Standard Criteria for Class 1E Power Systems forNuclear Power Generating Stations, in that it amplifies subclause 6.2.4 of
19、that standard (Standby powersupplies) concerning requirements for diesel-generator units.The IEEE has developed this standard to provide the principal design criteria, design features, qualificationconsiderations, and testing requirements for individual diesel-generator units, including auxiliary eq
20、uipmentand controls within the scope of this standard used in the standby power supply of a nuclear facility, whichcomply with the Nuclear Regulatory Commissions Code of Federal Regulations (10 CFR 50). This standard presents specific procedures and criteria applicable to qualifying the diesel-gener
21、ator unit andsupplements the criteria described in IEEE Std 323-1983, IEEE Standard for Qualifying Class 1EEquipment for Nuclear Power Generating Stations, and IEEE Std 627-1980, IEEE Standard for DesignQualification of Safety System Equipment Used in Nuclear Power Generating Stations.This revision
22、of the standard provides additional detail in the following areas: a) Defining specific qualification requirementsb) Clarifying scope and scope diagramc) Providing requirements for no-load and light-load operation, since extended operation under theseconditions may be detrimental to unit performance
23、d) Expanding factory production testing and site testing criteriae) Updating specific surveillance requirements f) Providing guidance for test parameters (annex C)g) Providing guidance for reliability program elements (annex D)This revision of the standard incorporates periodic testing requirements
24、described in IEEE Std 749-1983,IEEE Standard for Periodic Testing of Diesel-Generator Units Applied as Standby Power Supplies inNuclear Power Generating Stations, which has been withdrawn.Industry practice is focusing toward monitoring and trending to facilitate aging and reliabilitydeterminations.
25、This standard provides guidance for recommended test parameters and reliability programelements as described in annexes C and D. These guidelines reflect industry practices and are in agreementwith guidelines developed by the Nuclear Management and Resources Council (NUMARC), now known asthe Nuclear
26、 Energy Institute (NEI).The qualification requirements delineated in this standard consider aging considerations as potentialcommon mode failure mechanisms. Operating experience is generally available on diesel-generator unitssimilar to those covered by this standard, and is useful in establishing t
27、he effect of aging mechanisms forthose components where the technical state-of-the-art does not allow for techniques such as acceleratedaging. The basis for allowing operating experience is supplemented by noting that the application of thesediesel-generator units for nuclear service is such that th
28、e actual operating time under loaded conditions isexpected to be less than one year continuous service in the 40-year life expectancy of the plant. For areaswhere the state-of-the-art is not as limited, accelerated aging techniques should be used.Components or assemblies that have been used for test
29、ing should not be placed into in-service use unlessthey have been analyzed to demonstrate their adequacy for in-service use.ivOther industry standards exist or are being developed to cover topics related to this standard, including theAmerican Nuclear Society series standardsadescribing design requi
30、rements for diesel-generator unitauxiliary systems.Adherence to these criteria may not suffice for ensuring public health and safety because it is the integratedperformance of the structures, the fluid systems, the instrumentation systems, and the electrical systems ofthe station that establishes th
31、e consequences of accidents. Each applicant has the responsibility to ensure thatthis integrated performance is adequate.This standard was prepared by Working Group 4.2 of the Auxiliary Power Subcommittee (SC-4) of theNuclear Power Engineering Committee of the IEEE Power Engineering Society. At the
32、time this standardwas approved, the working group had the following membership:E. I. Fabri,ChairP. R. Johnson,SecretaryThe following persons were involved in the preparation of the standard, but were not working groupmembers at the time of approval.The Auxiliary Power Subcommittee (SC-4) of the Nucl
33、ear Power Engineering Committee had the followingmembership at the time this revision was approved:R. Weronick,ChairP. B. Stevens,Vice ChairJ. P. Carter,SecretaryaThese publications are available from the American Nuclear Society, 555 North Kensington Avenue, LaGrange Park, IL 60525, USA.L. F. Bedna
34、rT. N. ChanO. P. ChopraL. FusegniD. D. GaleazziL. G. HajosK. R. HoopingarnerJ. HorneF. KauffmannD. SandiforthN. A. TraegerJ. J. Burns W. FarmerR. E. AllenG. AttarianF. D. BaxterW. J. BoyerJ. ChiloyanE. I. FabriA. S. GillL. C. GonzalezD. T. GoodneyP. K. GuhaP. R. JohnsonJ. D. KueckH. C. LeakeJ. D. Ma
35、cDonaldG. MorrisB. NemroffG. L. NicelyR. D. F. ParkerC. A. PetrizzoD. J. RanftH. A. RobinsonA. R. RobyG. J. SadauskasT. R. SimsB. J. SkorasD. SmithJ. E. Stoner, Jr.R. L. SwallowsP. SzabadosvThe following persons (members of the Nuclear Power Engineering Committee) were on the ballotingcommittee:When
36、 the IEEE Standards Board approved this standard on December 12, 1995, it had the followingmembership:E. G. “Al” Kiener,ChairDonald C. Loughry,Vice ChairAndrew G. Salem,Secretary*Member EmeritusAlso included are the following nonvoting IEEE Standards Board liaisons:Satish K. AggarwalRobert E. Hebner
37、Steve SharkeyChester C. TaylorValerie E. ZelentyIEEE Standards Project EditorSatish K. AggarwalRussell E. AllenVincent BacanskasJohn T. BauerFarouk D. BaxterWes W. BowersDan F. BrosnanNissen M. BursteinAris S. CandrisS. P. CarfagnoRobert C. CarruthRobert L. CopyakGary L. DomanEdward F. DowlingArthur
38、 R. DuCharmeRich E. DulskiJay ForsterJohn M. GallagherWil C. GangloffLouis W. GaussaLuis C. GonzalezLawrence P. GradinBritton P. GrimRobert E. HallGregory K. HenrySonny KasturiJames T. KeiperJ. Donald LamontAlex MarionR. B. MillerRichard E. MillerBurt NemroffMohandas PaiJoseph R. PenlandNewell S. Po
39、rterEd W. RhoadsArnold RobyNeil P. SmithPeter B. StevensPeter SzabadosJames E. ThomasJohn T. UlloMark S. ZarGilles A. BarilClyde R. CampJoseph A. CannatelliStephen L. DiamondHarold E. EpsteinDonald C. FleckensteinJay Forster*Donald N. HeirmanRichard J. HollemanJim IsaakBen C. JohnsonSonny KasturiLor
40、raine C. KevraIvor N. KnightJoseph L. Koepfinger*D. N. “Jim” LogothetisL. Bruce McClungMarco W. MigliaroMary Lou PadgettJohn W. PopeArthur K. ReillyGary S. RobinsonIngo RschChee Kiow TanLeonard L. TrippHoward L. WolfmanviContentsCLAUSE PAGE1. Overview 11.1 Scope 11.2 Purpose. 42. References 43. Defi
41、nitions 54. Principal design criteria . 64.1 Capability. 64.2 Ratings . 74.3 Interactions. 74.4 Design and application considerations. 74.5 Design features. 95. Factory production testing . 115.1 General. 115.2 Factory production tests. 126. Qualification requirements. 136.1 General. 136.2 Initial t
42、ype tests 136.3 Aging 156.4 Seismic qualification requirements 176.5 Ongoing surveillance . 176.6 Modifications . 186.7 Documentation. 187. Site testing 187.1 Testing 187.2 Site acceptance testing . 187.3 Pre-operational testing . 207.4 Periodic testing. 217.5 Test descriptions 237.6 Records 25ANNEX
43、Annex A (informative) Method for establishing a load profile for a diesel-generator unit 27Annex B (informative) Example of aging and aged equipment testing 29Annex C (informative) Recommended diesel-generator unit monitoring and trending parameters. 35Annex D (informative) Diesel-generator unit rel
44、iability program elements. 391IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations1. Overview1.1 ScopeThis standard describes the criteria for the application and testing of diesel-generator units as Class 1Estandby power supplies
45、in nuclear power generating stations.Figure 1 shows the boundaries of systems and equipment included in the scope of this standard. Site testingis covered in clause 7, and the boundaries for site testing are given in 1.1.2.1.1.1 InclusionsThe following items are within the scope of this standard:a)
46、The diesel engine, including1) The flywheel and coupling (if applicable)2) The combustion air system, starting at the engine air intake connection, including the effects ofany remote air intake filter or silencer, or both3) The starting system4) The starting energy system5) The fuel oil system, incl
47、uding the day tank and the filters and strainers between the day tankand the engine6) The lubricating oil system7) The cooling system, starting at the point where the cooling medium is introduced to the diesel-generator unit8) The exhaust system, including the exhaust silencer, but excluding piping
48、from the engineexhaust connection to the inlet of the silencer and silencer tail pipe9) The governor systemIEEEStd 387-1995 IEEE STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY2Figure 1Scope diagram;CPSELECTRIC CIRCUITS (CONTROL, AUXILIARY POWER, ETC; MAIN POWER)NON_ELECTRICAL CHANNE
49、LS (OIL, AIR, EXHAUST, ETC; DRIVE)LIMIT OF SCOPE OF DIESEL-GENERATOR UNIT WITH INTERFACE ( ) CONTROL PROTECTION AND SURVEILLANCE SYSTEMSIEEEPOWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS Std 387-19953b) The generator, including1) The main leads terminating at the generator terminals2) The excitation and voltage regulation systemsc) The local control, protection, and surveillance systems associated with the diesel engine, thegenerator, and their auxiliary equipment and systems cited aboved) The ac and dc distribution systems associated with the diesel engine, the generator, an
