ML17264A867
| ML17264A867 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/24/1997 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
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| References | |
| NUDOCS 9705020089 | |
| Download: ML17264A867 (71) | |
Text
Attachment IIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnical Specifications IncludedPages:5.0-229705020089 970424PDRADQCK05000244PPDR)
Reporting Requirements 5.65.6Reporting Requirements 5.6.6PTLR(continued)
C.i.(C.w.ic~TheaoifjtWcighmethVds,=,.viidKCp':::-:deterp$
ne:t+e'CSpressureand~empe~raureandTTOAPA Iimitsshal'lbethosepreviously reviewedandapprovedbytheNRC.inNRCletterdatedHaygg,dgggii[iiii!!!!il:,.
AdIII11,44~I4IgyareLsdescribed inthefollowing documents:
1.LetterfromR.C.Hecredy,Rochester GasandElectricCorporation (RGimLE),
toDocumentControlDesk,NRC,Attention:
A.R.Johnson,"Application forFacilityOperating License,RevisiontoReactorCoolantSystemRCS)PressureandTemeratureLimitsReortPTLR'A,msfstvikt1ve7!Coutp~I't!88'Qll1redmeutsiy
"'Attlclllllltlt'3!VI/
Apri'i2~19r9$.2.IIAAP-1444
~".,':.PIP,-'":l1 "Hethodology UsedtoDevelopColdOverpressure Hitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,",fiictgoiis':;.!L!,.":::,:::,:.:2::."::::;::".Pe'e8~!3:-
8Yijii'~~r,,";,5lf9,6.
C.<~LC.i.wd.ThePTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluentperiodandforrevisions orsupplement thereto.R.E.GinnaNuclearPowerPlant5.0-22Amendment No.g,g Attachment IIIProposedTechnical Specifications IncludedPages:5.0-22 Reporting Requirements 5.65.6Reporting Requirements 5.6.6PTLR(continued)
C.Theanalytical methodsusedtodetermine theRCSpressureandtemperature andLTOPlimitsshallbethosepreviously reviewedandapprovedbytheNRCinNRCletterdated<NRCapprovaldocument>.
Specifically, thelimitsandmethodology isdescribed inthefollowing documents:
1.LetterfromR.C.Hecredy,Rochester GasandElectricCorporation (RGKE),toDocumentControlDesk,NRC,Attention:
A.R.Johnson,"Application forFacilityOperating License,RevisiontoReactor-Coolant System(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements,"
Attachment VI,April24,1997.2.WCAP-14040-NP-A, "Hethodology UsedtoDevelopColdOverpressure Hitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,"Sections1,2,and4,January1996.d.ThePTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluenceperiodandforrevisions orsupplement thereto.R.E.GinnaNuclearPowerPlant5.0-22Amendment No.g,PP Attachment IVGinnaStationPTLR,Revision2 GINNASTATIONPTLRRevision2RCSPRESSUREANDTEMPERATURE LIMITSREPORT(PTLR)Responsible HanagerEffective DateControlled CopyNo.
R.E.GinnaNuclearPowerPlantRCSPressureandTemperature LimitsReportRevision2ThisreportisnotpartoftheTechnical Specifications.
Thisreportisreferenced intheTechnical Specifications.
TABLEOFCONTENTS1.0RCSPRESSUREANDTEMPERATURE LIMITSREPORT........................
22.0OPERATING LIMITS...................................................
32.1RCSPressureandTemperature Limits..........................
32.2LowTemperature Overpressure Protection SystemEnableTemperature
..................................................
32.3LowTemperature Overpressure Protection Syste~Setpoints
.....33.0REACTORVESSELMATERIALSURVEILLANCE PROGRAM......................
4.0 SUPPLEMENTAL
DATAINFORMATION ANDDATATABLES.......................
45.0REFERENCES
.........................................................
5FIGURE1ReactorVesselHeatupLimitations
............................
6FIGURE2ReactorVesselCooldownLimitations
..........................
7TABLE3Calculation ofChemistry FactorsUsingSurveilCapsuleData..................................
TABLE1Surveillance CapsuleRemovalSchedule.........
TABLE2Comparison ofSurveillance MaterialwithRGl.~~~~~~~~~~~~~~~~899Predictions..
9lance10TABLE4TABLE5TABLE6Calculation ofARTSat24EFPY.............
.12ReactorVesselToughness Table(Unirradiated)
ReactorVesselSurfaceFluenceValuesat19.5and32EFPY......
11PTLRRevision2
R.E.GinnaNuclearPowerPlantPressureandTemperature LimitsReport1.0RCSPressureandTemeratureLimitsReortPTLRThisPressureandTemperature LimitsReport(PTLR)forGinnaStationhasbeenpreparedinaccordance withtherequirements ofTechnical Specification 5.6.6.Revisions tothePTLRshallbeprovidedtotheNRCafterissuance.
TheTechnical Specifications addressed inthisreportarelistedbelow:3.4.33.4.63.4.73.4.103.4.12RCSPressureandTemperature (P/T)LimitsRCSLoops-NODE4RCSLoops-NODE5,LoopsFilledPressurizer SafetyValvesLowTemperature Overpressure Protection (LTOP)SystemIPTLRRevision2
- I,I
2.0 OPERATING
LIMITSThecycle-specific parameter limitsforthespecifications listedinSection=1.0arepresented inthefollowing subsections.
Allchangestotheselimitsmustbedeveloped usingtheNRCapprovedmethodologies specified inTechnical Specification 5.6.6.Theselimitshavebeendetermined suchthatallapplicable limitsofthesafetyanalysisaremet.Allitemsthatappearincapitalized typearedefinedinTechnical Specification 1.1,"Definitions."
2.1RCSPressureandTemeratureLimits(LCO3.4.3andLCO3.4.12)(Reference 1)2.1.1TheRCStemperature rate-of-change limitsare:a.Amaximumheatupof60'Fperhour.b.Amaximumcooldownof100'Fperhour.2.1.2TheRCSP/Tlimitsforheatupandcooldownarespecified byFigures1and2,respectively.
2.1.3Theminimumboltuptemperature, usingthemethodology ofReference 2,Section2.7,is60'F.2.2LowTemeratureOverressureProtection SstemEnableTemerature(LCOs3.4.6,3.4.7,3.4.10and3.4.12)(Methodology ofReference 3,Attachment VI,Section3.4ascalculated inAttachment VIItoReference 3).2.2.1Theenabletemperature fortheLowTemperature Overpressure Protection Systemis322'F.2.3LowTemeratureOverressureProtection SstemSetpints(LCO3,4.12)2.3.1Pressurizer Power0cratedReliefValveLiftSettinLimits(Methodology ofReference 3,Attachment VIascalculated inReference 4,Attachment IV)Theliftsettingforthepressurizer PowerOperatedReliefValves(PORVs)iss411psig(includes instrument uncertainty).
PTLRRevision2
3.0 REACTORVESSELMATERIALSURVEILLANCE
PROGRAMThereactorvesselmaterialirradiation surveillance specimens shallberemovedandexaminedtodetermine changesinmaterialproperties.
TheremovalscheduleisprovidedinTable1.Theresultsoftheseexaminations shallbeusedtoupdateFigures1and2.Thepressurevesselsteelsurveillance program(Ref.5)isincompliance withAppendixHto10CFR50,entitled, "ReactorVesselRadiation Surveillance Program."
Thematerialtestrequirements andtheacceptance standardutilizethereference nil-ductility temperature, RT>>,whichisdetermined inaccordance withASTME208.Theempirical relationship betweenRT>>~andthefracturetoughness ofthereactorvesselsteelisdeveloped inaccordance withAppendixG,"Protection AgainstNon-Ductile Failure,"
tosectionIIIoftheASMEBoilerandPressureVesselCode.Thesurveillance capsuleremovalschedulemeetstherequirements ofASTME185-82.AsshownbyReference 1(specifically itsReference 51),thereactorvesselmaterialirradiation surveillance specimens indicatethatthesurveillance datameetsthecredibility discussion presented inRegulatory Guide1.99revision2where:1.Thecapsulematerials represent thelimitingreactorvesselmaterial.
2.Charpyenergyvs.temperature plotsscatteraresmallenoughtopermitdetermination of30ft-lbtemperature anduppershelfenergyunambiguously.
3.Thescatterofa,RT>>valuesarewithinthebestfitscatterlimitsasshownonTable2.Theonlyexception iswithrespecttotheIntermediate Shellwhichisnotthelimitingreactorvesselmaterial.
4.TheCharpyspecimenirradiation temperature matchesthereactorvesselsurfaceinterface temperature within+25'F.5.Thesurveillance datafallswithinthescatterbandofthematerialdatabase.
4.0 SUPPLEMENTAL
DATAINFORMATION ANDDATATABLES4.14.2TheRT>>~valueforGinnaStationlimitingbeltlinematerialis256.6Ffor32EFPYperReference l.TablesTable2containsacomparison ofmeasuredsurveillance material30ft-lbtransition temperature shiftsanduppershelfenergydecreases withRegulatory Guide1.99,Revision2predictions.
PTLRRevision2 A"LI Table3showscalculations ofthesurveillance materialchemistry factorsusingsurveillance capsuledata.Table4providesthereactorvesseltoughness data.Table5providesasummaryofthefluencevaluesusedinthegeneration oftheheatupandcooldownlimitcurves.Table6showsexample,calculations oftheARTvaluesat24EFPYforthelimitingreactorvesselmaterial.
5.0REFERENCES
1.WCAP-14684, "R.E.GinnaHeatupandCooldownLimitCurvesforNormalOperation,"
datedJune1996.2.WCAP-14040-NP-A, "Hethodology UsedtoDevelopColdOverpressure Hitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,"Revision2,January1996.3.LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC,
Subject:
"Application forAmendment toFacilityOperating License,RevisiontoReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Adminstrative ControlsRequirements,"
datedApril24,1997LetterfromR.C.Hecredy,RG8E,toA.R.Johnson,NRC,
Subject:
"Application forAmendment toFacilityOperating License,"Hethodology forLowTemperature Overpressure Protection (LTOP)Limits,"datedFebruary9,1996.5.WCAP-7254, "Rochester GasandElectric, RobertE.GinnaUnitNo.1ReactorVesselRadiation Surveillance Program,"
Hay1969.IPTLRRevision2 MATERIALPROPERTYBASISLIMITINGMATERIAL:
CIRCUMFERENTIAL WELDSA-847LIMITINGARTVALUESAT24EFPY:1/4T,232'F3/4T,196F25006664SSI060666 Ig~~,I~I'I~t~~f~~m2250~IN~2000~t~l.~LEAKTESTLIICIT~~~IiI~~Ii~tjI~g~~17501500CA1250-.1000750500250~I~UNhCCEPThBLE'PERhTION HBATUPRATEUPTO60F/Hr'.HBATUPRATEUPTOIOOF/Hr.CRITICALITY I.IMITEASEDOxINSERVICE HYDROSTATIC TESTTEMPERATURE (SSSF)FORTHESERVICEPERIODUPTOZ4~0EFPT~~IISIIhCCEPThBLE OPERATIO.N I~0050100150200250300350400450500Indicated Temperature (Beg.F.)FIGUREIREACTORVESSELHEATUPLIMITATIONS APPLICABLE FORTHEFIRST24EFPY(MITHOUTMARGINFORINSTRUNENT ERRORS)PTLRRevision2
MATERIALPROPERTYBASISLIMITINGMATERIAL:
CIRCUMFFRENTIAL VlELDSA-847LIMITINGARTVALUESAT24EFPY1/4T,232F3/4T,196F25005004ZSl00060d I~II~iI~~2250he~W20001750l.'iI!I~i~i!\tiiiii,I~I~~Ii'.!II!~~!iI~UNhCCEPTh3LE OPERATION I~i~~i~I'I!I!IIi~I'~150012501000!IIiII~IIhCCEPThBLE OPERhTION 7505.00250=cooLDo'AN BhTESP/Hr.ozo4000tooII~0050100150200250300350400450500Indicated Temperature (Deg.p)FIGURE2REACTORVESSELCOOLDOWNLIMITATIONS APPLICABLE FORTHEFIRST24EFPY(WITHOUTMARGINFORINSTRUMENT ERRORS)PTLReviSion2
Table1Surveillance CasuleRemovalScheduleVesselLocationCapsule(deg.)CapsuleLeadFactorRemovalSchedule" CapsuleFluenceE19(n/cm)"77'5767'7'370247'.993.001.851.741.741.91.6(removed) 2.7(removed) 7(removed) 17(removed)
TeOStandby.50281.1051.8643.746l'eo'b'/A NOTES:(a)Effective FullPowerYears(EFPY).(b)Tobedetermined, thereisnocurrentrequirement forremoval.(c)Reference l.IPTLRRevision2 TABLE2Surveillance Haterial30ft-lbTransition Temperature Shift30lb-ftTransition Temperature ShiftHaterialLowerShellIntermediate ShellWeldHetalHAZHetalCapsuleFluence(x10"n/cm',E>1.0HeV)".50281.1051.8643.746.50281.1051.8643.746.50281.1051.8643.746.50281.1051.8643.746Predicted"
('F)263237375259135168191218Heasured"
('F)252530420-601401651502059010095('F)374652s]4113(a)Reference 1(including itsReference 51).
IC41~I'llErs TABLE3Calculation ofChemistry FactorsUsingSurveillance CapsuleDataHaterialIntermediate ShellForging05(Tangential)
CapsuleFluence(x10'/cm',E)1.0VeV)<>.50281.1051.8643.746FF.80811.02791.17061.3418~RT(oF)N(~)25253042Sum:FF*hRopy('F)20.225.735.156.4137.4FF.65301.05661.37031.80044.8803Chemistry Factor=28.2'FIntermediate Shell.50281.105.808100.65301.0279001.05661.8641.1706001.37033.7461.34186080.51.8004Sum:80.54.8803WeldMetalChemistry Factor=16.5'F.5028.8081149.7121.0.65301.1051.8641.0279176.41.1706160.4181.3187.81.05661.3703NOTES:(a)Reference 1.3.7461.3418219.1294.01.8004Sum:854.694.8803Chemistry Factor=160.7'F(b)~RT>>~forweldmaterialistheadjustedvalueusingthe1.069ratioingfactorperReference 1appliedtothemeasuredvaluesofTable2.PTLR10Revision2 TABLE4ReactorVesselToughness Table(Unirradiated)"
NaterialDescription Intermediate ShellLowerShellCircumferential Weld(a)PerReference l.Cu(%).07.05.25Ni(%).69.69.56InitialRT>>('F)2040-4.8TABLE5ReactorVesselSurfaceFluenceValuesat19.5and32EFPY"x10"(n/cm',E)1.0~ev)EFPY19.5320o2.323.4915'.472.2030'.051.5645'969'.45(a)Reference l.PTLRRevision2 TABLE6Calculation ofAdjustedReference Temperatures at24EFPYfortheLimitingReactorVesselMaterialParameter Operating TimeMaterialLocationChemistry Factor(CF),F"'luence (f),10"n/cm(E>1.0HeV)"FluenceFact'orFFhRTgpyCFxFFyFInitialRTgpy(I)FMargin(H),'F"ART=I+(CFxFF)+HF""NOTES:(a)Valuecalculated usingTable5values.(b)ValuesfromTable3.(c)Reference 1.Circ.Weld1/4-T160.71.851.17188-4.848.3232Values24EFPYCirc.Weld3/4-T160.7.851.955153,4-4.848.3196.9PTLR12Revision2 Attachment VRedlinedVersionofLTOPMethodology identifies changestomethodology originally providedinDecember8,1995RG&ElettertoNRC)
LOWTEMPERATURE OVERPRESSURE PROTECTION SYSTEM(LTOPS)INTRODUCTION ThepurposeoftheLTOPSistosupplement thenormalplantoperational administrative controlstoprotectthereactorvesselfrombeingexposedtoconditions offastpropagating brittlefracture.
TheLTOPSalsoprotectstheResidualHeatRemoval(RHR)Systemfromoverpressurizatlon.
Thishasbeenachievedbyconservatively choosinganLTOPSsetpolntwhichpreventstheRCSfromexceeding thepressure/temperature limitsestablished by10CFRPart50AppendixG"'equirements, andtheRHRSystemfromexceeding 110%ofitsdesignpressure.
TheLTOPSisdesignedtoprovidethecapability, duringrelatively lowtemperature operation (typically lessthan350'F),toautomatically preventtheRCSpressurefromexceeding theapplicable limits.Oncethesystemisenabled,nooperatoractionIsinvolvedfortheLTOPStoperformitsIntendedpressuremitigation function.
Thus,nooperatoractionismodelledintheanalysessupporting thesetpofntselection, althoughoperatoractionmaybeinitiated toultimately terminate thecauseoftheoverpressure event.ThePORVslocatednearthetopofthepressurizer, togetherwithadditional actuation logicfromthelow-range pressurechannels, areutilizedtomitigatepotential RCSoverpressure transients.
TheLTOPSprovidesthereliefcapacityforspecifictransients whichwouldnotbemitigated bytheRHRSystemreliefvalve.Inaddition, alimitonthePORVpipingisaccommodated duetothepotential forwaterhammereffectstobedeveloped inthepipingassociated withthesevalvesasaresultofthecyclicopeningandclosingcharacteristics duringmitigation ofanoverpressure transient.
Thus,apressurelimitmorerestrictive thanthe10CFR50,AppendixG<'>allowable isimposedaboveacertaintemperature sothattheloadsonthepipingfromaLTOPSeventwouldnotaffectthepipingintegrity.
3-1 acr%s.IN Twospecifictransients havebeendefined,withtheRCSinawater-solid condition, asthedesignbasisforLTOPS.Eachofthesescenarios assumesnoRHRSystemheatremovalcapability.
TheRHRSystemreliefvalve(203)doesnotactuateduringthetransients.
Thefirsttransient consistsofaheatinjection scenarioinwhichareactorcoolantpumpinasingleloopisstartedwiththeRCStemperature asmuchas50'Flowerthanthesteamgenerator secondary sidetemperature.
Thisresultsinasuddenheatinputtoawater-solid RCSfromthesteamgenerators, creatinganincreasing pressuretransient.
Thesecondtransient hasbeendefinedasamassinjection scenariointoawater-solid RCSascausedbyoneoftwopossiblescenarios.
Thefirstscenarioisaninadvertent actuation ofthesafetyinjection pumpsintotheRCS.Thesecondscenarioisthesimultaneous isolation oftheRHRSystem,isolation ofletdown,andfailureofthenormalchargingflowcontrolstothefullflowcondition.
Eitherscenariomaybeeliminated fromconsideration depending ontheplantconfigurations whicharerestricted bytechnical specifications.
Also,variouscombinations ofchargingandsafetyinjection flowsmayalsobeevaluated onaplant-specific basis.Theresulting massinjection/letdown mismatchcausesanincreasing pressuretransient.
3.2LTOPSSetpointDetermination Rochester GasandElectricandBabcock8WilcoxNuclearTechnology (BWNT)havedeveloped thefollowing methodology whichisemployedtodetermine PORVsetpolnts formitigation oftheLTOPSdesignbasiscoldoverpressurization transients.
Thismethodology maximizes theavailable operating marginforsetpolntselection whilemaintaining anappropriate levelofprotection insupportofreactorvesselandRHRSystemintegrity.
3-2 Parameters Considered Theselection ofproperLTOPSsetpointforactuating thePORVsrequirestheconsideration ofnumeroussystemparameters including:
a.VolumeofreactorcoolantinvolvedIntransient b.RCSpressuresignaltransmission delayc.Volumetric capacityofthereliefvalvesversusopeningposition, including thepotential forcriticalflowd.Stroketimeofthereliefvalves(open6close)e.Initialtemperature andpressureoftheRCSandsteamgenerator f.MassinputrateintoRCSg.Temperature ofinjectedfluidh.Heattransfercharacteristics ofthesteamgenerators i.Initialtemperature asymmetry betweenRCSandsteamgenerator secondary waterj.Massofsteamgenerator secondary waterk.RCPstartupdynamicsI.10CFR50,Appendix6"Ipressure/temperature characteristics ofthereactorvesselm.Pressurizer PORVpiping/structural analysislimitations n.Dynamicandstaticpressuredifferences throughout theRCSandRHRSo.RHRSystempressurelimitsp.Loopasymmetry forRCPstartcasesq.Instrument uncertainty fortemperature (conditions underwhichtheLTOPSystemisplacedintoservice)andpressureuncertainty (actuation setpoint)
Theseparameters aremodelledintheBWNTRELAP5/MOD2-B&W computercode(Ref.19)3-3 whichcalculates themaximumandminimumsystempressures.
PressureLimitsSelection ThefunctionoftheLTOPSistoprotectthereactorvesselfromfastpropagating brittlefracture.
Thishasbeenimplemented bychoosingaLTOPSsetpolntwhichpreventsexceeding thelimitsprescribed bytheapplicable pressure/temperature characteristic forthespecificreactorvesselmaterialinaccordance withrulesgiveninAppendixGto10CFR50I".
TheLTOPSdesignbasistakescreditforthefactthatoverpressure eventsmostlikelyoccurduringisothermal conditions intheRCS.Therefore, itisappropriate toutilizethesteady-state AppendixGlimit.Inaddition, theLTOPSalsoprovidesforanoperational consideration tomaintaintheintegrity ofthePORVpiping,andtoprotecttheRHRSystemfromoverpressure duringtheLTOPSdesignbasistransients.
Atypicalcharacteristic 10CFR50AppendixGcuweisshownbyFigure3.1wheretheallowable systempressureincreases withIncreasing temperature.
ThistypeofcurvesetsthenominalupperlimitonthepressurewhichshouldnotbeexceededduringRCSincreasing pressuretransients basedonreactorvesselmaterialproperties.
Superimposed onthiscurvelsthePORVpipinglimitandRHRSystempressurelimitwhichisconservatively used,forsetpolntdevelopment, asthemaximumallowable pressureabovethetemperature atwhichitintersects withthe10CFR50AppendixGcurve.Whenareliefvalveisactuatedtomitigateanincreasing pressuretransient, thereleaseofavolumeofcoolantthroughthevalvewillcausethepressureincreasetobeslowedandreversedasdescribed byFigure3.2.Thesystempressurethendecreases, asthereliefvalvereleasescoolant,untilaresetpressureisreachedwherethevalveissignalled toclose.Notethatthepressurecontinues todecreasebelowtheresetpressureasthevalverecloses.
Thenominal3-4 II1>><,fikt'~,t+g+
s lowerlimitonthepressureduringthetransient lstypically established basedsolelyonanoperational consideration forthereactorcoolantpumpP1sealtomaintainanominaldifferential pressureacrossthesealfacesforproperfilm-riding performance.
Intheeventthattheavailable rangeisinsufficient toconcurrently accommodate theupperandlowerpressurelimits,theupperpressurelimitsaregivenpreference.
Thenominalupperlimit(basedontheminimumofthesteady-state 10CFR50AppendixGrequirement, theRHRSystempressurelimit,andthePORVpipinglimitations) andthenominalRCP41sealperformance criteriacreateapressurerangefromwhichthesetpoints forbothPORVsmaybeselectedasshownonFigures3.3and3.4.Wherethereisinsufficient rangebetweentheupperandlowerpressurelimitstoselectPORVsetpoints toprovideprotection againstviolation ofbothlimits,setpointselection toprovideprotection againsttheupperpressurelimitviolation shalltakeprecedence.
MassInputConsideration Foraparticular massinputtransient totheRCS,thereliefvalvewillbesignalled toopenataspecificpressuresetpoint.
However,asshownonFigure3.2,therewillbeapressureovershoot duringthedelaytimebeforethevalvestartstomoveandduringthetimethevalveismovingtothefullopenposition.
Thisovershoot isdependent onthedynamicsofthesystemandtheinputparameters, andresultsinamaximumsystempressuresomewhathigherthanthesetpressure.
Similarly therewillbeapressureundershoot, whilethevalveisrelieving, bothduetotheresetpressurebeingbelowthesetpointandtothedelayinstrokingthevalveclosed.Themaximumandminimumpressures reached(P>>><andPQiN)inthetransient areafunctionoftheselectedsetpoint(P,)asshownonFigure3.3.Theshadedarearepresents anoptimum3-5
rangefromwhichtoselectthesetpointbasedontheparticular massinputcase.Severalmassinputcasesmayberunatvariousinputflowratestoboundtheallowable setpointrange.HeatInputConsideration Theheatinputcaseisdonesimilarly tothemassinputcaseexceptthatthelocusoftransient pressurevaluesversusselectedsetpoints maybedetermined forseveralvaluesoftheinitialRCStemperature.
Thisheatinputevaluation providesarangeofacceptable setpoints dependent onthereactorcoolanttemperature, whereasthemassinputcaseislimitedtothemostrestrictive lowtemperature condition only(i.e.themassinjection transient isnotsensitive totemperature).
TheshadedareaonFigure3.4describes theacceptable bandforaheatinputtransient fromwhichtoselectthesetpointforaparticular initialreactorcoolanttemperature.
IftheLTOPSisasinglesetpolntsystem,themostlimitingresultIsusedthroughout.
FinalSetpointSelection Bysuperimposing theresultsofmultiplemassinputandheatinputcasesevaluated, (fromaseriesoffiguressuchas3.3and3.4)arangeofallowable PORVsetpoints tosatisfyboth/conditions canbedetermined.
Forasinglesetpointsystem,themostlimitingsetpointischosen,withtheupperpressurelimitgivenprecedence ifbothlimitscannotbeaccommodated.
Theselection ofthesetpolnts forthePORVsconsiders theuseofnominalupperandlowerpressurelimits.Theupperlimitsarespecified bytheminimumofthesteady-state cooldowncurveascalculated inaccordance withAppendix8to10CFR50I'I orthepeakRCSorRHR3-6 Ig Systempressurebaseduponpiping/structural analysisloads.Thelowerpressureextremeisspecified bythereactorcoolantpumpP1sealminimumdifferential pressureperformance criteria.
Uncertainties inthepressureandtemperature instrumentation utilizedbytheLTOPSareaccounted forconsistent withthemethodology ofReference
2.0. Accounting
fortheeffects'f instrumentation uncertainty imposesadditional restrictions onthesetpointdevelopment, whichisalreadybasedonconservative pressurelimitssuchasasafetyfactorof2onpressurestress,useofalowerboundKfcurveandanassumed~ITflawdepthwithalengthequalto1~8timesthevesselwallthicknes3.3Application ofASMECodeCaseN-514Ereed:'8::".I't6'L'id:,tran rt-:I!1I!-:l...,,!r.':i",,:e-::
tc;t't,OW~Ot'the:::Preeeureq deter~1ned<t~aSStf+SPPendec;8"
~"~-allewe
,paragraph G-2215,ofsectionxtoftheAsMEcode"t.QYt~te,:spp1RVgfog@fASME"::Code!Casa'N.".:.St'8'":lnclsaeae:::the.
JOJeletfttg,::,ntarglh)1A:::tl'l8~fSQIOtl~!OfifltstprBssule-tJ88lperatutst!Ilnttt;".,Oulpseirrh~WIK~,
hsi'L!tCp'Sile'nagfedercods,:case;N-".ste:.requfreet Lfg%~!o:bs;:effecthretst coolantaetnpelatureeffeesdfen
~Ok'RooeF.:::.Orgg~epgant tefnPcrateree;OOrree goadingLtd,a::.reaoforrtr Seeel~mitalp tetnPetaiure;:."::-:.Ot!
8Idfetenoerrolnethfnefdtr.:,trees e~t'Sudsceil'ee~ahteniftTtetr't+~80%F~
whichever isgreater.RTNpTisthehighestadjustedreference temperature forweldorbase3-7 metalinthebeltlineregionatadistanceone-fourth ofthevesselsectionthickness fromthevesselinsidesurface,asdetermined byRegulatory Guide1.99,Revision2.3.4EnableTemperature forLTOPSTheenabletemperature isthetemperature belowwhichtheLTOPSsystemisrequiredtobeoperablei bTrhe:Sfn~na L70:3:egabfeltsntpeinture le,,eetabliihed.uefnng::Ihe:ff fdinne;prOV¹d:::byASliilegtf Cede.'.Case,,NS O',::;:Fhe,A'8MB!Code!CsiY%.',<,'.:.i6~@ris.'en'::"en+N(RCF':,.qu,.d~teBpeYa~FN nnrreegnndfnffi'O~ihetreantnrbTee'See!!ltrrii:eetil!i'eiiiPiiiiiiire!r'll'RT:
sj,"LSgsePNiggtfeP,';-The e&QeaeWTWhinheeer iSgreateraSdeeCrtbed InSeCtiOn3.3e!Tliialdaffnlt7nn"..I'SYafenr!euPPOited!~[i!then titreebngbouestgwneds6roup~ihsafnnaTenabfe'ternpeinture federerrnfned~as(IITianr+807paf; 3-8
TheRCScoldlegtemperature limitation forstartinganRCPisthesamevalueastheLTOPSenabletemperature toensurethatthebasisoftheheatinjection transient isnotviolated.
TheStandardTechnical Specifications (STS)prohibitstartinganRCPwhenanyRCScoldlegtemperatures islessthanorequaltotheLTOPSenabletemperature unlessthesecondary sidewatertemperature ofeachsteamgenerator islessthanorequalto50'FaboveeachoftheRCScoldlegtemperatures.
3-9 Figure3.1TYPICALAPPENDIXGP/TCHARACTERISTICS I(g2500~~2000z~O15000O0U1000I-9500Clz'FNR100IMPOSEDPORVPIPINGLIMITIMPOSEDRHRSPIPINGLIMIT00100200300400500lNDICATED COOLANTTEMPERATURE,
'F3-10 Figure3.2TYRICAL:RRESSUR2'TRANSIENT
- .:(1.'REL'IEFVAVLECYCLE):.8EVPOINT-------------
RESET~Uride3-11 Figure3.3""SAP'03N3'::
>>':DET.ERMIINATIQN'(MASSINPUT):'APPENDIX:G SIAXIMUMt;IMIT'AVPMAX,'CP&SEAL':::PERFORMANCE CRITERIA;;.;;;
SETPOINTRANGEPORVSETPOIN7):PSlG ThemaximumpressurelimitistherginimumoftheAppendixGlimit,thePORVdischarge pipingstructural analysislimit,ortheRHRsystemlimit3-12
Figure3.4'(HEAT:INPUT)
-"'APPENDIX:G SIAXIMUMt;IMIT'.--------------
Pex--------
IIIRCPA:SEALIPERFORMANCE CR1TERlASETPOINTRANGE:PORVSETPOINT):PSIG ThemaximumpressurelimitIstheminimumoftheAppendixGlimit,thePORVdischarge pipingstructural analysislimit,ortheRHRsystemlimit3-13
4.0REFERENCES
NUREG1431,"Standard Technical Specifications forWestinghouse Pressurized WaterReactors",
Revision0,September, 1992.2.U.S.NuclearRegulatory Commission, "RemovalofCycle-Specific Parameter LimitsfromTechnical Specifications",
GenericLetter88-16,October,1988.3.U.S.NuclearRegulatory Commission, Radiation Embrittlement ofReactorVesselMaterials, ReulatoGufde1.99 Revislon2, May,1988.
4.CodeofFederalRegulations, Title10,Part50,"Fracture Toughness Requirements forLIght-Water NuclearPowerReactors",
AppendixG,FractureToughness Requirements.
5.ASMEBoilerandPressureVesselCode,SectionXI,"RulesforInservlce Inspection ofNuclearPowerPlantComponents",
AppendixG,FractureToughness CriteriaForProtection AgainstFailure.6.R.G.Soltesz,R.K.Disney,J.Jedruch,andS.LZiegler,NuclearRocketShielding Methods,Modification, UpdatingandInputDataPreparation.
Vol.5-Two-Dimensional DiscreteOrdinates Transport Technique, WANL-PR(LL)434, Vol.5,August1970.7.ORNLRSICDataLIbraryCollection DLC-76SAILORCoupledSelf-Shielded, 47Neutron,20Gamma-Ray, P3,CrossSectionLibraryforLightWaterReactors.
ASMEBoilerandPressureVesselCode,SectionIII,"RulesforConstruction ofNuclearPowerPlantComponents",
Division1,Subsection NB:Class1Components.
BranchTechnical PositionMTEB5-2,"Fracture Toughness Requirements",
NUREG4800 StandardReviewPlan5.3.2,Pressure-Temperature Limits,July1981,Rev.1.10.ASTME-208,StandardTestMethodforConducting Drop-Weight TesttoDetermine Nil-Ductility Transition Temperature ofFerriticSteels,ASTMStandards, Section3,AmericanSocietyforTestingandMaterials.
11.B8WOwnersGroupReportBAW-2202, "Fracture Toughness Characterization ofWF-70Weld4-1 Material",
BBWOwnersGroupMaterials Committee, September 1993.12.Letter,ClydeY.Shiraki,NuclearRegulatory Commission, toD.LFarrar,Commonwealth Edison-Company,'Exemption fromtheRequirement toDetermine theUnirradiated Reference Temperature inAccordance withtheMethodSpecified In10CFR50.61(b)(2)(i)(TACNOS.M84546andM84547),DocketNos.50-295and50404,February22,1994.13.CodeofFederalRegulations, Title10,Part50,"Fracture Toughness Requirements forLight-Water NuclearPowerReactors, AppendixH,ReactorVesselMaterialSurveillance ProgramRequirements.
14.Timoshenko, S.P.andGoodier,J.N.,TheoofElasticit, ThirdEdition,McGraw-Hill BookCo.,NewYork,1970.15.ASMEBoilerandPressureVesselCode,SectionXI,"RulesforInservice Inspection ofNuclearPowerPlantComponents",
AppendixA,AnalysisofFlaws,ArticleA@000,MethodForK,Determination.
16.WRCBulletinNo.175,PVRCRecommendations onToughness Requirements forFerriticMaterials",
WeldingResearchCouncil,NewYork,August1972.17.ASMEBoilerandPressureVesselCodeCaseN-514,SectionXI,Division1,"LowTemperature Overpressure Protection",
Approvaldate:February12,1992.18.BranchTechnical PositionRSB5-2,"Overpressurization Protection ofPressurized WaterReactorsWhileOperating atLowTemperatures",
NUREG4800 StandardReviewPlan5.2.2,Overpressure Protection, November1988,Rev.2.19.BWNT,"RELAPS/MOD2, AnAdvancedComputerProgramforLight-Water ReactorLOCAandNon-LOCATransient Analysis,"
BAW-10164P-A.20.Instrument ofAmerica(ISA)Standard67.04-1994.
4-2 Attachment VIFinalVersionofLTOPMethodology (Replaces methodology originally providedinDecember8,1995RG&ElettertoNRCwhichinturnreplacedmethodology providedinSection3toWCAP-14040)
LOWTEMPERATURE OVERPRESSURE PROTECTION SYSTEM(LTOPS)INTRODUCTION ThepurposeoftheLTOPSIstosupplement thenormalplantoperational administrative controlstoprotectthereactorvesselfrombeingexposedtoconditions offastpropagating brittlefracture.
TheLTOPSalsoprotectstheResidualHeatRemoval(RHR)Systemfromoverpressurization.
Thishasbeenachievedbyconservatively choosinganLTOPSsetpointwhichpreventstheRCSfromexceeding thepressure/temperature limitsestablished by10CFRPart50AppendixGI'Irequirements, andtheRHRSystemfromexceeding 110%ofitsdesignpressure.
TheLTOPSisdesignedtoprovidethecapability, duringrelatively lowtemperature operation (typically lessthan350'F),toautomatically preventtheRCSpressurefromexceeding theapplicable limits.Oncethesystemisenabled,nooperatoractionisinvolvedfortheLTOPStoperformitsintendedpressuremitigation function.
Thus,nooperatoractionismodelledintheanalysessupporting thesetpointselection, althoughoperatoractionmaybeinitiated toultimately terminate thecauseoftheoverpressure event.ThePORVslocatednearthetopofthepressurizer, togetherwithadditional actuation logicfromthelow-range pressurechannels, areutilizedtomitigatepotential RCSoverpressure transients.
TheLTOPSprovidesthereliefcapacityforspecifictransients whichwouldnotbemitigated bytheRHRSystemreliefvalve.Inaddition, alimitonthePORVpipingisaccommodated duetothepotential forwaterhammereffectstobedeveloped inthepipingassociated withthesevalvesasaresultofthecyclicopeningandclosingcharacteristics duringmitigation ofanoverpressure transient.
Thus,apressurelimitmorerestrictive thanthe10CFR50,AppendixGI'Iallowable isimposedaboveacertaintemperature sothattheloadsonthepipingfromaLTOPSeventwouldnotaffectthepipingintegrity.
3-1 0IIiE'II Twospecifictransients havebeendefined,withtheRCSinawater-solid condition, asthedesignbasisforLTOPS.Eachofthesescenarios assumesnoRHRSystemheatremovalcapability.
TheRHRSystemreliefvalve(203)doesnotactuateduringthetransients.
Thefirsttransient consistsofaheatinjection scenarioinwhichareactorcoolantpumpinasingleloopisstartedwiththeRCStemperature asmuchas50'Flowerthanthesteamgenerator secondary sidetemperature.
Thisresultsinasuddenheatinputtoawater-solid RCSfromthesteamgenerators, creatinganincreasing pressuretransient.
Thesecondtransient hasbeendefinedasamassinjection scenariointoawater-solid RCSascausedbyoneoftwopossiblescenarios.
Thefirstscenarioisaninadvertent actuation ofthesafetyinjection pumpsintotheRCS.Thesecondscenarioisthesimultaneous Isolation oftheRHRSystem,isolation ofletdown,andfailureofthenormalchargingflowcontrolstothefullflowcondition.
Eitherscenariomaybeeliminated fromconsideration depending ontheplantconfigurations whicharerestricted bytechnical specifications.
Also,variouscombinations ofchargingandsafetyinjection flowsmayalsobeevaluated onaplant-specific basis.Theresulting massinjection/letdown mismatchcausesanincreasing pressuretransient.
3.2LTOPSSetpointDetermination Rochester GasandElectricandBabcock&WilcoxNuclearTechnology (BWNT)havedeveloped thefollowing methodology whichisemployedtodetermine PORVsetpoints formitigation oftheLTOPSdesignbasiscoldoverpressurization transients.
Thismethodology maximizes theavailable operating marginforsetpointselection whilemaintaining anappropriate levelofprotection insupportofreactorvesselandRHRSystemintegrity.
3-2 Parameters Considered Theselection ofproperLTOPSsetpointforactuating thePORVsrequirestheconsideration ofnumeroussystemparameters including:
a.Volumeofreactorcoolantinvolvedintransient b.RCSpressuresignaltransmission delayc.Volumetric capacityofthereliefvalvesversusopeningposition, including thepotential forcriticalflowd.Stroketimeofthereliefvalves(open&close)e.Initialtemperature andpressureoftheRCSandsteamgenerator f.MassinputrateintoRCSg.Temperature ofinjectedfluidh.Heattransfercharacteristics ofthesteamgenerators i.Initialtemperature asymmetry betweenRCSandsteamgenerator secondary water1J.Massofsteamgenerator secondary waterk.RCPstartupdynamicsI.10CFR50,AppendixGt'Ipressure/temperature characteristics ofthereactorvesselm.Pressurizer PORVpiping/structural analysislimitations n.Dynamicandstaticpressuredifferences throughout theRCSandRHRSo.RHRSystempressurelimitsp.Loopasymmetry forRCPstartcasesq.Instrument uncertainty fortemperature (conditions underwhichtheLTOPSystemisplacedintoservice)andpressureuncertainty (actuation setpolnt)
Theseparameters aremodelledintheBWNTRELAP5/MOD2-B&W computercode(Ref.19)3-3 Sr';
whichcalculates themaximumandminimumsystempressures.
PressureLimitsSelection ThefunctionoftheLTOPSistoprotectthereactorvesselfromfastpropagating brittlefracture.
Thishasbeenimplemented bychoosingaLTOPSsetpolntwhichpreventsexceeding thelimitsprescribed bytheapplicable pressure/temperature characteristic forthespecificreactorvesselmaterialinaccordance withrulesgiveninAppendixGto10CFR50I".
TheLTOPSdesignbasistakescreditforthefactthatoverpressure eventsmostlikelyoccurduringisothermal conditions intheRCS.Therefore, itisappropriate toutilizethesteady-state AppendixGlimit.Inaddition, theLTOPSalsoprovidesforanoperational consideration tomaintaintheintegrity ofthePORVpiping,andtoprotecttheRHRSystemfromoverpressure duringtheLTOPSdesignbasistransients.
Atypicalcharacteristic 10CFR50AppendixGcurveisshownbyFigure3.1wheretheallowable systempressureincreases withincreasing temperature.
ThistypeofcurvesetsthenominalupperlimitonthepressurewhichshouldnotbeexceededduringRCSincreasing pressuretransients basedonreactorvesselmaterialproperties.
Superimposed onthiscurveisthePORVpipinglimitandRHRSystempressurelimitwhichisconservatively used,forsetpointdevelopment, asthemaximumallowable pressureabovethetemperature atwhichitintersects withthe10CFR50AppendixGcurve.Whenareliefvalveisactuatedtomitigateanincreasing pressuretransient, thereleaseofavolumeofcoolantthroughthevalvewillcausethepressureincreasetobeslowedandreversedasdescribed byFigure3.2.Thesystempressurethendecreases, asthereliefvalvereleasescoolant,untilaresetpressureisreachedwherethevalveissignalled toclose.Notethatthepressurecontinues todecreasebelowtheresetpressureasthevalverecloses.
Thenominal3-4 Q6p~II1tv~'=<<fj lowerlimitonthepressureduringthetransient istypically established basedsolelyonanoperational consideration forthereactorcoolantpump¹1sealtomaintainanominaldifferential pressureacrossthesealfacesforproperfilm-riding performance.
Intheeventthattheavailable rangeisinsufficient toconcurrently accommodate theupperandlowerpressurelimits,theupperpressurelimitsaregivenpreference.
Thenominalupperlimit(basedontheminimumofthesteady-state 10CFR50Appendix8requirement, theRHRSystempressurelimit,andthePORVpipinglimitations) andthenominalRCP¹1sealperformance criteriacreateapressurerangefromwhichthesetpoints forbothPORVsmaybeselectedasshownonFigures3.3and3.4.Wherethereisinsufficient rangebetweentheupperandlowerpressurelimitstoselectPORVsetpolnts toprovideprotection againstviolation ofbothlimits,setpolntselection toprovideprotection againsttheupperpressurelimitviolation shalltakeprecedence.
MassInputConsideration Foraparticular massinputtransient totheRCS,thereliefvalvewillbesignalled toopenataspecificpressuresetpolnt.
However,asshownonFigure3.2,therewillbeapressureovershoot duringthedelaytimebeforethevalvestartstomoveandduringthetimethevalveismovingtothefullopenposition.
Thisovershoot isdependent onthedynamicsofthesystemandtheinputparameters, andresultsinamaximumsystempressuresomewhathigherthanthesetpressure.
Similarly therewillbeapressureundershoot, whilethevalveisrelieving, bothduetotheresetpressurebeingbelowthesetpointandtothedelayinstrokingthevalveclosed.Themaximumandminimumpressures reached(P>>andP~,)inthetransient areafunctionoftheselectedsetpoint(Ps)asshownonFigure3.3.Theshadedarearepresents anoptimum3-5 rangefromwhichtoselectthesetpointbasedontheparticular massinputcase.SeveralmassInputcasesmayberunatvariousinputflowratestoboundtheallowable setpointrange.HeatInputConsideration Theheatinputcaseisdonesimilarly tothemassinputcaseexceptthatthelocusoftransient pressurevaluesversusselectedsetpoints maybedetermined forseveralvaluesoftheinitialRCStemperature.
Thisheatinputevaluation providesarangeofacceptable setpolnts dependent onthereactorcoolanttemperature, whereasthemassinputcaseislimitedtothemostrestrictive lowtemperature condition only(i.e.themassinjection transient isnotsensitive totemperature).
TheshadedareaonFigure3.4describes theacceptable bandforaheatinputtransient fromwhichtoselectthesetpointforaparticular initialreactorcoolanttemperature.
IftheLTOPSisasinglesetpolntsystem,themostlimitingresultisusedthroughout.
FinalSetpointSelection Bysuperimposing theresultsofmultiplemassinputandheatinputcasesevaluated, (fromaseriesoffiguressuchas3.3and3.4)arangeofallowable PORVsetpoints tosatisfybothconditions canbedetermined.
Forasinglesetpointsystem,themostlimitingsetpointischosen,withtheupperpressurelimitgivenprecedence ifbothlimitscannotbeaccommodated.
Theselection ofthesetpolnts forthePORVsconsiders theuseofnominalupperandlowerpressurelimits.Theupperlimitsarespecified bytheminimumofthesteady-state cooldowncurveascalculated inaccordance withAppendixGto10CFR50'I orthepeakRCSorRHR3-6 Systempressurebaseduponpiping/structural analysisloads.Thelowerpressureextremeisspecified bythereactorcoolantpump41sealminimumdifferential pressureperformance criteria.
Uncertainties inthepressureandtemperature instrumentation utilizedbytheLTOPSareaccounted forconsistent withthemethodology ofReference
2.0. Accounting
fortheeffectsofinstrumentation uncertainty imposesadditional restrictions onthesetpolntdevelopment, Nwhichisalreadybasedonconservative pressurelimitssuchasasafetyfactorof2onpressurestress,useofalowerboundKRcurveandanassumed~/~Tflawdepthwithalengthequalto1~8timesthevesselwallthickness.
3.3Application ofASMECodeCaseN-514iASMECodeCaseN-514I'allowsLTOPStolimitthemaximumpressureinthereactorvesselto110%ofthepressuredetermined tosatisfyAppendixG,paragraph G-2215,ofSectionXIoftheASMECode"'.Theapplication ofASMECodeCaseN-514increases theoperating marginintheregionofthepressure-temperature limitcurveswheretheLTOPSisenabled.CodeCaseN-514requiresLTOPStobeeffective atcoolanttemperatures lessthan200'Foratcoolanttemperatures corresponding toareactorvesselmetaltemperature, ata1/4tdistancefromtheinsidevesselsurface,lessthanRopy+50F,whichever isgreater.RTD~isthehighestadjustedreference temperature forweldorbasemetalinthebeltlineregionatadistanceone-fourthofthevesselsectionthickness fromthevesselInsidesurface,asdetermined byRegulatory Guide1.99,Revision2.3-7 EnableTemperature forLTOPSTheenabletemperature isthetemperature belowwhichtheLTOPSsystemisrequiredtobeoperable.
TheGlnnaLTOPSenabletemperature isestablished usingtheguidanceprovidedbyASMEXICodeCaseN-514.TheASMECodeCaseN-514supportsanenableRCSliquidtemperature corresponding tothereactorvessel1/4tmetaltemperature ofRTNp~+50For200'F,whichever isgreaterasdescribed inSection3.3.Thisdefinition lsalsosupported bytheWestinghouse Owner'sGroup.TheGinnaenabletemperature isdetermined as(RTNpY+50F)+(instrument errorI~I)+(metaltemperature difference to1/4T).TheRCScoldlegtemperature limitation forstartinganRCPisthesamevalueastheLTOPSenabletemperature toensurethatthebasisoftheheatinjection transient isnotviolated.
TheStandardTechnical Specifications (STS)prohibitstartinganRCPwhenanyRCScoldlegtemperatures islessthanorequaltotheLTOPSenabletemperature unlessthesecondary sidewatertemperature ofeachsteamgenerator islessthanorequal.to50'FaboveeachoftheRCScoldlegtemperatures.
3-8
Figure3.1TYPICALAPPENDIXGP/TCHARACTERISTICS (g2500~2000z.~~15000OEL'~U1000ClI-Q500CloF/HR100IMPOSEDPORVPIPINGLIMITIMPOSEDRHRSPIPINGLIMIT00100200300400500INDIGATEDCOOLANTTEMPERATURE,
'F3-9 P
Figure3.2TYRICAL'RESSURE:TRANSIENT
"(1';REL'IEF,',VAVLE CYCLE):;",":
RESE73-10 Figure3.3:,'.SETPO)NT::.:":
DET.ERMIINATION:
"(MASSINPUT):'APPENDIX'G MAXIMUMl.'IMIT'CP
&'SEA'L':::
PERFORMANCE
'CRrrE8%;:::;:
SETPOINTRANGE:PORVSETPOINT):PSIG ThemaximumpressurelimitistheminimumoftheAppendixGlimit,thePORVdischarge pipingstructural analysislimit,orthe'RHhsystemlimit3-11
Figure3.4-.;-SEFPQ)NT::DETERMIIMATION:
(HEAT:INP.
UT)'APPENDIX:G MAXIMUMI.'IMIT'-------------
Pue--------
PL)ÃIIRCRN:SEAL::;PE%'.QRMANCE
'CRrrERtA::::::
SETPOINT.
RANGE:p.SP,ORVSETPOIN7):PSlG ThemaximumpressurelimitistheminimumoftheAppendixGlimit,thePORVdischarge pipingstructural analysislimit,ortheRHRsystemlimit3-12 NUREG1431,"Standard Technical Specifications forWestinghouse Pressurized WaterReactors",
Revision0,September, 1992.2.U.S.NuclearRegulatory Commission, "RemovalofCycle-Specific Parameter LimitsfromTechnical Specifications",
GenericLetter88-16,October,1988.3.U.S.NuclearRegulatory Commission, Radiation Embrittlement ofReactorVesselMaterials, ReulatoGuide1.99Revision2,May,1988.4.CodeofFederalRegulations, Title10,Part50,"Fracture Toughness Requirements forLight-Water NuclearPowerReactors",
AppendixG,FractureToughness Requirements.
ASMEBoilerandPressureVesselCodeSectionXI,'RulesforInservice Inspection ofNuclearPowerPlantComponents",
AppendixG,FractureToughness CriteriaForProtection AgainstFailure.6.R.G.Soltesz,R.K.Disney,J.Jedruch,andS.IZiegier,NuclearRocketShielding Methods,Modification, UpdatingandInputDataPreparation.
Vol.5-Two-Dimensional DiscreteOrdinates Transport Technique, WANL-PR(LL)<34, Vol.5,August1970.ORNLRSICDataLIbraryCollection DLC-76SAILORCoupledSelf-Shielded, 47Neutron,20Gamma-Ray, P3,CrossSectionLibraryforLightWaterReactors.
ASMEBoilerandPressureVesselCode,SectionIII,"RulesforConstruction ofNuclearPowerPlantComponents",
Division1,Subsection NB:Class1Components.
BranchTechnical PositionMTEB5-2,"Fracture Toughness Requirements",
NUREG4800 StandardReviewPlan5.3.2,Pressure-Temperature Limits,July1981,Rev.1.10.ASTME-208,StandardTestMethodforConducting Drop-Weight TesttoDetermine Nil-Ductility Transition Temperature ofFerriticSteels,ASTMStandards, Section3,AmericanSocietyforTestingandMaterials.
11.B&WOwnersGroupReportBAW-2202, "Fracture Toughness Characterization'of WF-70WeldMaterial",
B&WOwnersGroupMaterials Committee, September 1993.4-1
u.Letter,ClydeY.Shlraki,NuclearRegulatory Commission, toD.L.Farrar,Commonwealth EdisonCompany,"Exemption fromtheRequirement toDetermine theUnirradiated Reference Temperature inAccordance withtheMethodSpecified in10CFR50.61(b)(2)(i)(TACNOS.M84546andM84547)",
DocketNos.50-295and50404,February22,1994.13.CodeofFederalRegulations, Title10,Part50,"Fracture Toughness Requirements forLight-Water NuclearPowerReactors",
AppendixH,ReactorVesselMaterialSurveillance ProgramRequirements.
14.Tlmoshenko, S.P.andGoodier,J.N.,TheoofElastlcit, ThirdEdition,McGraw-Hill BookCo.,NewYork,1970.15.ASMEBoilerandPressureVesselCode,SectionXI,"RulesforInservice Inspection ofNuclearPowerPlantComponents",
AppendixA,AnalysisofFlaws,ArticleA-3000,MethodForgDetermination.
16.WRCBulletinNo.175,"PVRCRecommendations onToughness Requirements forFerritlcMaterials",
WeldingResearchCouncil,NewYork,August1972.17.ASMEBoilerandPressureVesselCodeCaseN-514,SectionXI,Division1,"LowTemperature Overpressure Protection",
Approvaldate:February12,1992.18.BranchTechnical PositionRSB5-2,"Overpressurization Protection ofPressurized WaterReactorsWhileOperating atLowTemperatures",
NUREG4800 StandardReviewPlan5.2.2,Overpressure Protection, November1988,Rev.2.19.BWNT,"RELAPS/MOD2, AnAdvancedComputerProgramforLight-Water ReactorLOCAandNon-LOCATransient Analysis,"
BAW-10164P-A.
20.Instrument ofAmerica(ISA)Standard67.04-1994.
4-2
Attachment VIILTOPEnableTemperature Calculation 1(FirstuseofLTOPenabletemperature methodology)