1、AN AMERICAN NATIONAL STANDARDStandards and Guides for Operation and Maintenance of Nuclear Power PlantsASME OM-S/G2007(Revision of ASME OM-S/G2003)Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-A
2、SME OM-S/G2007(Revision of ASME OM-S/G2003)Standards andGuides forOperation andMaintenance ofNuclear PowerPlantsAN AMERICAN NATIONAL STANDARDThree Park Avenue New York, NY 10016Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted
3、without license from IHS-,-,-Date of Issuance: October 17, 2007The 2007 edition of this Standard is being issued with an automatic addenda subscription service.The use of addenda allows revisions made in response to public review comments or committeeactions to be published on a regular yearly basis
4、; revisions published in addenda will becomeeffective 6 months after the Date of Issuance of the addenda. The next edition of this Standard isscheduled for publication in 2010.ASME issues written replies to inquiries concerning interpretations of technical aspects of thisStandard. The interpretation
5、s will be included with the above addenda service and are publishedon the ASME Web site under the Committee Pages at http:/cstools.asme.org as they are issued.ASME is the registered trademark of The American Society of Mechanical Engineers.This code or standard was developed under procedures accredi
6、ted as meeting the criteria for American NationalStandards. The Standards Committee that approved the code or standard was balanced to assure that individuals fromcompetent and concerned interests have had an opportunity to participate. The proposed code or standard was madeavailable for public revi
7、ew and comment that provides an opportunity for additional public input from industry, academia,regulatory agencies, and the public-at-large.ASME does not “approve,” “rate,” or “endorse” any item, construction, proprietary device, or activity.ASME does not take any position with respect to the valid
8、ity of any patent rights asserted in connection with anyitems mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability forinfringement of any applicable letters patent, nor assumes any such liability. Users of a code or standard are expresslyadvised
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10、 code or standard.ASME accepts responsibility for only those interpretations of this document issued in accordance with the establishedASME procedures and policies, which precludes the issuance of interpretations by individuals.No part of this document may be reproduced in any form,in an electronic
11、retrieval system or otherwise,without the prior written permission of the publisher.The American Society of Mechanical EngineersThree Park Avenue, New York, NY 10016-5990Copyright 2007 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERSAll rights reservedPrinted in U.S.A.Copyright ASME International Prov
12、ided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-CONTENTS(A detailed Contents precedes each OM-SG2007 Part.)Foreword ivPreparation of Technical Inquiries to the Committee on Operation andMaintenance of Nuclear Power Plants viCommi
13、ttee Roster . viiPreface ixSummary of Changes xSTANDARDSPart 2 Performance Testing of Closed Cooling Water Systems inLWR Power Plants . 1Part 3 Requirements for Preoperational and Initial Start-up VibrationTesting of Nuclear Power Plant Piping Systems . 9Part 12 Loose Part Monitoring in Light-Water
14、Reactor Power Plants . 42Part 16 Performance Testing and Inspection of Diesel Drive Assemblies inLWR Power Plants . 60Part 21 Inservice Performance Testing of Heat Exchangers in Light-WaterReactor Power Plants 79Part 24 Reactor Coolant and Recirculation Pump Condition Monitoring . 134Part 25 Perform
15、ance Testing of Emergency Core Cooling Systems inLight-Water Reactor Power Plants 154Part 26 Determination of Reactor Coolant Temperature From DiverseMeasurements . 178GUIDESPart 5 Inservice Monitoring of Core Support Barrel Axial Preload inPressurized Water Reactor Power Plants 185Part 7 Requiremen
16、ts for Thermal Expansion Testing of Nuclear PowerPlant Piping Systems 209Part 11 Vibration Testing and Assessment of Heat Exchangers 223Part 14 Vibration Monitoring of Rotating Equipment in Nuclear Power Plants . 259Part 17 Performance Testing of Instrument Air Systems in Light-WaterReactor Power Pl
17、ants 282Part 19 Preservice and Periodic Performance Testing of Pneumatically andHydraulically Operated Valve Assemblies in Light-Water ReactorPower Plants 296Part 23 Inservice Monitoring of Reactor Internals Vibration in PWR Power Plants . 301iiiCopyright ASME International Provided by IHS under lic
18、ense with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-FOREWORDThe Committee on Operation and Maintenance of Nuclear Power Plants (O however, legible, handwritten inquirieswill be considered.(f) The inquiry shall include name and mailing address of the inqu
19、irer.(g) The inquiry shall be submitted to the following address: Secretary, Committee on Operationand Maintenance of Nuclear Power Plants, The American Society of Mechanical Engineers, ThreePark Avenue, New York, NY 10016-5990.viCopyright ASME International Provided by IHS under license with ASME N
20、ot for ResaleNo reproduction or networking permitted without license from IHS-,-,-ASME COMMITTEE ON OPERATION ANDMAINTENANCE OF NUCLEAR POWER PLANTSAs of July 20, 2006STANDARDS COMMITTEER. I. Parry, Chair R. E. Martel IIIG. R. Palmer, Vice Chair J. W. MeyerJ. L. Berger, Secretary C. N. PendletonJ. E
21、. Allen J. G. RocasolanoA. A. Dermenjian C. W. RowleyK. G. DeWall T. P. Ruggiero, Jr.A. M. DiBiasio L. SageR. S. Hartley C. D. SellersM. Honjin D. M. SwannD. J. Kanuch S. R. SwantnerS. S. Lee C. L. ThibaultR. C. Lippy G. I. ZiglerA. M. Marion J. J. ZudansHONORARY MEMBERS (STANDARDS COMMITTEE)J. W. S
22、tacey J. S. G. WilliamsSPECIAL COMMITTEE ON STANDARDS PLANNINGA. A. Dermenjian, Chair A. MarionJ. D. Hallenbeck, Secretary G. E. SchinzelJ. A. Brown C. D. SellersR. Grantom C. L. ThibaultM. Honjin G. I. ZiglerS. S. Lee J. J. ZudansSUBCOMMITTEE ON OM CODESD. M. Swann, Chair J. D. HallenbeckW. L. Just
23、ice, Vice Chair R. G. KershawT. N. Chan B. P. LindenlaubS. D. Comstock R. C. LippyK. G. DeWall T. G. ScarbroughSubgroup ISTA/ISTCR. E. Emrath, Chair R. C. LippyA. N. Anderson A. MarionR. Binz IV G. E. McGovernG. Cappuccio J. D. PageS. D. Comstock J. W. PerkinsR. S. Hartley R. RanaS. R. Khan J. G. Ro
24、casolanoH. S. Koski, Jr. L. SageR. E. LaBeaf S. R. SemanviiSubgroup ISTBT. P. Ruggiero, Jr., Chair I. T. KisiselW. L. Justice, Secretary M. C. ManciniR. Binz IV R. E. Martel IIIL. F. Firebaugh J. D. PageR. S. Hartley C. N. PendletonP. R. Hitchcock N. B. StocktonD. J. Kanuch D. M. SwannJ. W. Kin W. R
25、. TomlinsonSubgroup ISTDR. Rana, Chair S. A. NormanG. R. Palmer, Vice Chair L. A. PharesG. Bedi R. L. Portmann, Jr.D. P. Brown M. D. PotterR. E. Day M. A. PressburgerR. E. Fandetti R. E. RichardsP. D. Huber P. G. ScholarH. S. Koski, Jr. M. D. ShuttR. E. LaBeafSubgroup ISTEG. L. Zigler, Chair A. Mari
26、onA. A. Dermenjian, Vice Chair J. G. RocasolanoJ. A. Brown C. W. RowleyD. C. Fischer G. E. SchinzelM. Honjin C. D. SellersSubgroup on Relief ValvesS. D. Comstock, Chair T. P. NederostekP. A. Bradshaw, Secretary S. L. Quan, Sr.A. M. DiBiasio A. H. RolloC. A. Glass D. SanfordS. F. Harrison S. R. Seman
27、W. F. Hart D. G. ThibaultW. D. Lynn, Jr. P. W. TurrentineSubgroup on Motor-Operated ValvesK. G. DeWall, Chair P. G. McQuillanR. G. Kershaw, Secretary T. S. NeckowiczT. N. Chan T. G. ScarbroughJ. L. Daniels C. W. SmithS. Hale C. L. ThibaultC. H. Hansen D. G. Van PeltJ. M. LyleCopyright ASME Internati
28、onal Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-Subgroup on Air-Operated ValvesL. J. Victory, Jr., Chair W. D. MarriottJ. D. Hallenbeck, Secretary T. P. Sanders, Jr.J. I. Hjalmarson S. M. UnikewiczC. J. LindenSubgroup on
29、 Check ValvesB. P. Lindenlaub, Chair T. B. MaanaviE. Noviello, Secretary W. D. MorrowD. A. Cruz M. T. RobinsonM. Ebel J. L. SabinaL. I. Ezekoye A. R. SimonK. A. Hart J. M. StrishnaL. D. Lukens T. E. ThygesenSUBCOMMITTEE ON STANDARDS AND GUIDESR. F. Bosmans T. J. RiccioG. I. Ottoman, Jr. S. R. Swantn
30、erW. R. Peebles, Jr. D. A. TestaSubgroup on Diesel GeneratorsT. N. Chan, Chair S. J. LoeperA. G. Killinger, Vice Chair L. W. PriceK. R. Blackall A. P. PusateriD. D. Galeazzi S. M. UnikewiczA. L. Ho D. V. ZinkR. A. Kayler, Jr.Subgroup on Functional SystemsJ. W. Meyer, Chair J. R. HayesJ. J. Dore, Jr.
31、 W. R. Peebles, Jr.F. P. Ferraraccio S. R. SwantnerviiiSubgroup on Piping SystemsD. E. Olson, Chair K. A. KhuzaieK. E. Atkins A. N. NguyenK. K. Fujikawa J. S. G. WilliamsR. G. Gilada T. D. YuanSubgroup on Rotating EquipmentR. E. Brokenshire, Chair G. I. Ottoman, Jr.Subgroup on Heat ExchangersR. H. B
32、ernhard V. ChandraSubgroup on RTDsT. J. Riccio, Chair A. F. MadlenerA. Hartwig W. C. PhoenixSubgroup on OM-29B. J. Scott, Chair R. I. ParryJ. D. Hallenbeck S. L. Quan, Sr.D. J. Kanuch T. G. ScarbroughS. S. Lee G. E. SchinzelT. S. NeckowiczTask Group on Pump Performance-Based ISTJ. H. Maxwell, Chair
33、M. L. Bridges, Jr.V. G. Arzani H. L. HassenpflugR. Binz IV D. J. KanuchR. F. Bosmans J. D. PageCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-PREFACEORGANIZATION OF THIS DOCUMENTThis document is
34、arranged into Standards and Guides,subdivided into Parts as follows:StandardsPart 2 Performance Testing of Closed CoolingWater Systems in LWR Power PlantsPart 3 Requirements for Preoperational and InitialStart-up Vibration Testing of Nuclear PowerPlant Piping SystemsPart 12 Loose Part Monitoring in
35、Light-Water Reac-tor Power PlantsPart 16 Performance Testing and Inspection of Die-sel Drive Assemblies in LWR Power PlantsPart 21 Inservice Performance Testing of HeatExchangers in Light-Water Reactor PowerPlantsPart 24 Reactor Coolant and Recirculation PumpCondition MonitoringPart 25 Performance T
36、esting of Emergency CoreCooling Systems in Light-Water ReactorPower PlantsPart 26 Determination of Reactor Coolant Tempera-ture From Diverse MeasurementsGuidesPart 5 Inservice Monitoring of Core Support BarrelAxial Preload in Pressurized Water ReactorPower PlantsPart 7 Requirements for Thermal Expan
37、sion Test-ing of Nuclear Power Plant Piping SystemsPart 11 Vibration Testing and Assessment of HeatExchangersPart 14 Vibration Monitoring of Rotating Equipmentin Nuclear Power PlantsPart 17 Performance Testing of Instrument Air Sys-tems in Light-Water Reactor Power PlantsPart 19 Preservice and Perio
38、dic Performance Testingof Pneumatically and Hydraulically Oper-ated Valve Assemblies in Light-Water Reac-tor Power PlantsixPart 23 Inservice Monitoring of Reactor InternalsVibration in PWR Power PlantsParts 2, 3, 5, 7, 8, 13, and 16 were previously publishedin ASME/ANSI OM-1987 up to and including t
39、heOMc-1990 Addenda and were incorporated into ASMEOM-S/G1990.Parts 1, 4, 6, and 10 from ASME/ANSI OM-1987, upto and including the OMc-1990 Addenda, were incorpo-rated into ASME OM Code-1990, as follows:OM Code PreviousDesignation OM-1987 DesignationAppendix 1 Part 1 Requirements for InservicePerform
40、ance Testing ofNuclear Power PlantPressure Relief DevicesSubsection ISTD Part 4 Examination and Perform-ance Testing of NuclearPower Plant DynamicRestraints (Snubbers)Subsection ISTB Part 6 Inservice Testing ofPumps in Light-WaterReactor Power PlantsSubsection ISTC Part 10 Inservice Testing of Valve
41、sin Light-Water ReactorPower PlantsCORRESPONDENCESuggestions for improvement of this document orinclusion of additional topics should be sent to the fol-lowing address: Secretary, Committee on Operation andMaintenance of Nuclear Power Plants, The AmericanSociety of Mechanical Engineers, Three Park A
42、venue,New York, NY 10016-5990.ADDENDA SERVICEThis edition of ASME OM-S/G includes an automaticaddenda subscription service up to the publication ofthe next edition. The addenda subscription service willinclude approved new Parts, revisions to the existingParts, and issued interpretations. The interp
43、retationswill be included as part of the addenda service, but arenot part of the Standard or Guide.Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS-,-,-ASME OM-S/G2007SUMMARY OF CHANGESFollowing approv
44、al by the ASME Committee on Operation and Maintenance of Nuclear PowerPlants and ASME, and after public review, ASME OM-S/G2007 was approved by the AmericanNational Standards Institute on August 17, 2007.ASME OM-S/G2007 consists of OM-S/G2003, OMa-S/G2004, and OMb-S/G2005; editorialchanges, revision
45、s, and corrections; as well as the following change identified by a marginnote, (07).Page Location Change145 Part 24, 9.2.4 Equation corrected by errataxCopyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction or networking permitted without license from IHS
46、-,-,-ASME OM-S/G2007 PART 2 (STANDARDS)STANDARDSPART 21 Introduction . 22 Definitions 23 References 34 Establish System Testing Boundaries 35 Identify System Performance Requirements 36 Identify Testable Characteristics That Represent Performance Requirements . 37 Establish Acceptance Criteria for T
47、estable Characteristics . 58 Develop Test Procedures and Perform Testing, Inspections, andEngineering Analysis. 59 Evaluate Test Data . 810 Prepare Documentation 8Figure1 CCWS Typical Flow Diagram . 41Copyright ASME International Provided by IHS under license with ASME Not for ResaleNo reproduction
48、or networking permitted without license from IHS-,-,-PART 2 (STANDARDS) ASME OM-S/G2007PART 2Performance Testing of Closed CoolingWater Systems in LWR Power Plants1 INTRODUCTION1.1 ScopeThis Part establishes the requirements for preserviceand inservice testing to assess the operational readinessof certain closed cooling water systems (CCWS) usedin LWR power plants.The CCWS covered are those required to perform aspecific function in shutting down a reactor to the safeshutdown condition, in maintaining the safe shutdowncondition, or in mitigating the consequences of anaccident.
