Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls RequirementsML17264B067 |
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Site: |
Ginna |
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Issue date: |
10/08/1997 |
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From: |
ROCHESTER GAS & ELECTRIC CORP. |
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To: |
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Shared Package |
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ML17264B066 |
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References |
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NUDOCS 9710150247 |
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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. 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W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. 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[Table view] |
Text
eReporting Requirements 5.65.6Reporting Requirements 5.6.6PTLR(continued) c~Theanalytical methodsusedtodetermine theRCSpressureandtemperature andLTOPlimitsshallbethosepreviously reviewedandapprovedbytheNRCinNRCletterdated<NRCapprovaldocument>.
Specifically, themethodology isdescribed inthefollowing documents:
1.LetterfromR.C.Hecredy,Rochester GasandElectricCorporation (RG&E),toDocumentControlDesk,NRC,Attention:
GuyS.Vissing,"Application forFacilityOperating License,RevisiontoReactor,CoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements,"
Attachment VI,September 29,1997,assupplemented byletterfromR.C.Hecredy,RG&E,toGuyS.Vissing,NRC,"Corrections toProposedLowTemperature Overpressure Protection SystemTechnical Specification,"
October8,1997.2.WCAP-14040-NP-A, "Hethodology UsedtoDevelopColdOverpressure Hitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,"Sections1and2,January,1996.d.ThePiTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluenceperiodandforrevisions orsupplement thereto.R..E.GinnaNuclearPowerPlant,97l0%50247 97l008PDRADOCK:05000244 PPDR5.0-22Amendment No.g,PP Reporting Requirements 5.65.6Reporting Requirements 5.6.6PTLR(continued)
C.TheSohTjt5i'algeet~83os'.'".'undid,'.:::;f o.,:detep.ije,':~t,e:
RCpressureandtemp'erature andLTOPliiiiitsskale1bethnosepreviously reviewedandapprovedby,theNRC.inNRCletterdatedNayR!IT-II$6~(NRCyiappto:.vaI::-::.".:::::;do'clument>:.
Specifically, theI1eIihe+ad-methodology
~<i'sdescribed inthefollowing documents:
1.LetterfromR.C.Mecredy,Rochester GasandElectricCorporation (RGKE),toDocumentControlDesk,NRC,A<<ti:~'CW@igi:,-,,::,i,--g, "Appl'lfFacilityOperating License,RevisiontoReactorCoolantSystem(RCS)PressureandTemperature LimitsReportP.rhOI'ta'aeEt'3'On
~<>>>>~2.IIlAP-14MO~i!NP::-.':A'Methodology UsedtoDevelopColdOverpressure Mitigating SystemSetpoints andRCSHeatupandCooldownLi~ie,,"~p%!I""n---iiil:"-,:::
--icu!,L-'"-..-..=.-"'~~~96:.
~~d.ThePTLRshallbeprovidedtotheNRCuponissuanceforeachreactorvesselfluencmperiodandforrevisions orsupplement thereto.R.E.GinnaNuclearPowerPlant5.0-22Amendment No.Q,PP
2.0 OPERATING
LIMITSThecycle-specific parameter limitsforthespecifications listedinSection1.0arepresented 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 4,Enclosure 2is60'F.2.2LowTemeratureOverressureProtection SstemEnableTemerature(LCOs3.4.6,3.4.7,3.4.10and3.4.12)(Methodology ofReference 3,Attachment VIandReference 6,ascalculated inReference 7).2.2.1Theenabletemperature fortheLowTemperature Overpressure Protection Systemis322'F.2.3LowTemeratureOverressureProtection SstemSetpints(LCO3.4.12)2.3.1Pressurizer Power0cratedReliefValveLiftSettinLimits(Methodology ofReference 3,Attachment VIandReference 6,ascalculated inReference 3,Attachment VII).Theliftsettingforthepressurizer PowerOperatedReliefValves(PORVs)is~411psig(includes instrument uncertainty).
PTLRRevision2 Table3showscalculations ofthesurveillance materialchemistry factorsusingsurveillance capsuledata.Table4provides'thereactorvesseltoughness data.Table5providesasummaryofthefluencevaluesusedinthegeneration oftheheatupandcooldownlimitcurves.Table6showsexamplecalculations oftheARTvaluesat24EFPYforthelimitingreactorvesselmaterial.
5.0REFERENCES
2.3.5.6.7.WCAP-14684, "R.E.GinnaHeatupandCooldownLimitCurvesforNormalOperation,"
datedJune1996.WCAP-14040-NP-A, "Hethodology UsedtoDevelopColdOverpressure Mitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,"Revision2,January1996.LetterfromR.C.Hecredy,RGIIE,toGuyS.Vissing,NRC,
Subject:
"Application forAmendment toFacilityOperating License,RevisiontoReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements,"
datedSeptember 29,1997.LetterfromR.C.Hecredy,RGIIE,toGuyS.Vissing,NRC,"Clarifications toProposedLowTemperature Overpressure Protection SystemTechnical Specification,"
datedJune3,1997.WCAP-7254, "Rochester GasandElectric, RobertE.GinnaUnitNo.1ReactorVesselRadiation Surveillance Program,"
May1969.LetterfromR.C.Hecredy,RGIIE,toGuyS.Vissing,NRC,"Corrections toProposedLowTemperature Overpressure Protection SystemTechnical Specification,"
October8,1997.RGIIEDesignAnalysisDA-HE-97-031, "Evaluation ofGinnaRCSCoolantTemperature toSupportLTOPSRequirements,"
Revision0.PTLRRevision2
~\
~whichever isgreater.RT>>Tisthehighestadjustedreference temperature forweldorbasemetalInthebeltlineregionatadistanceone-fourth ofthevesselsectionthickness fromthevesselinsidesurface,asdetermined byRegulatory Guide1.99,Revision2.-AIQeugh3.4EnableTemperature forLTOPSTheenabletemperature Isthetemperature belowwhichtheLTOPSsystemisrequiredtobeoperable.g ill:re,:iHWS",:::
0":-y..':!b~5l.I'd':".Iiiil!:iis
.=.:I:.rrrlyA8taa!CFdNCSSe~Np
>4satt'te%8ME!CsdettCSSer N4g~d::SuppOrtS::a~..eoa8te.;F@8"!ITIO+dt~~epera u~rOeiiSSP~O,dred::te:,.",the'reeetsrereeeetttrat meta%tomcrater;Ot"":BTtsraWSO.'.keraO'O'IIV-Ttte 3-8 whichever isgreaterasdescribed InSection3.3.ttt'Nr~dsffnitiÃf s."alsoaso cnT~d':bTrtlh14o ttfeelfnghcuaeCVmerSeCrcuy'%TfjeQInnaenableternPeratu Iedet~ennnedaa(87~+::.3'Ovs~Fj Q+!gnst~u.
~i:;:eyror Peffpw:::.:Qrnasslft~e..
peratvge~diffsreneedod::
31'%Thssnaa~inurnha logiiwopressure~iagii'0~of i~heatsadLatQa'e:.eve!down.;cttrve:cTNcutatsd.':.In,ac'oordancs;:wtih:fqtltendht
'8%to:,t'OCPsRSOUtj~PsrXASME~!CcdtrsCase::::M4'tsi TheRCScoldlegtemperature limitation forstartinganRCPisthesamevalueastheLTOPSenabletemperature toensurethatthebasisoftheheatinJection transient isnotviolated.
TheRandar4-Technical Specifications
~prohibit startinganRCPwhenanyRCScoldlegtemperatures islessthanorequaltotheLTOPSenabletemperature unlessthesecondary sidewatertemperature ofeachsteamgenerator islessthanorequalto50'FaboveeachoftheRCSCOldlegtemPeratureSKOrithegreeeur!Zeryat~er Valume<IS:
3%4'CnblbVafeet.':{38~741eV Jet'.3-9 curve(with10%additional margin)ascalculated inaccordance withAppendixGto10CFR50orthepeakRCSorRHRSystempressurebaseduponpiping/structural analysisloads.Thelowerpressureextremelsspecified bythereactorcoolantpumpP1sealminimumdifferential pressureperformance criteria.
Uncertainties inthepressureandtemperature instrumentation utilizedbytheLTOPSareaccounted forconsistent withthemethodology ofReference
2.0. Accounting
fortheeffectsofinstrumentation uncertainty imposesadditional restrictions onthesetpolntdevelopment, whichisalreadybasedonconservative pressurelimitssuchasasafetyfactorof2onpressurestress,useofalowerboundK,Rcurveandanassumed~/iTflawdepthwithalengthequalto1Ntimesthevesselwalithickness.
3.3Application ofASMECodeCaseN-514ASMECodeCaseN-514II allowsLTOPStolimitthemaximumpressureinthereactorvesselto110%ofthepressuredetermined tosatisfyAppendixG,paragraph G-2215,ofSectionXIofNtheASMEGodet'I.Theapplication ofASMECodeCaseN-514increases theoperating marginintheregionofthepressure-temperature limitcurveswheretheLTOPSisenabled.CodeCaseN-514alsorequiresLTOPStobeeffective atcoolanttemperatures lessthan200'Foratcoolanttemperatures corresponding toareactorvesselmetaltemperature, ata1/4tdistancefromtheinsidevesselsurface,lessthanRTgpr+50F,whichever isgreater.RTgpyisthehighestadjustedreference temperature forweldorbasemetalinthebeltlineregionatadistanceone-fourth ofthevesselsectionthickness fromthevesselinsidesurface,asdetermined byRegulatory Guide1.99,Revision2.3-7 Itt4*
EnableTemperature forLTOPSTheenabletemperature isthetemperature belowwhichtheLTOPSsystemisrequiredtobeoperable.
TheGinnaLTOPSenabletemperature Isestablished usingtheguidanceprovidedbyASMEXICodeCaseN-514.TheASMECodeCaseN-514supportsanenableRCSliquidtemperature corresponding tothereactorvessel1/4tmetaltemperature ofRT>>r+50'For200'F,whichever isgreaterasdescribed InSection3.3.Thisdefinition isalsosupported bytheWestinghouse Owner'sGroup.TheGinnaenabletemperature isdetermined as(RTD~+50'F)+(instrument errorI~I)+(metaltemperature difference to1/4T).Themaximumallowable pressureis110%ofthesteady-state cooidowncurvecalculated inaccordance withAppendixGto10CFR50'erASMECodeCaseN-514i"ITheRCScoldlegtemperature limitation forstartinganRCPisthesamevalueastheLTOPSenabletemperature toensurethatthebasisoftheheatinjection transient isnotviolated.
TheTechnical Specifications prohibitstartinganRCPwhenanyRCScoldlegtemperatures islessthanorequaltotheLTOPSenabletemperature unlessthesecondary sidewatertemperature ofeachsteamgenerator Islessthanorequalto50'FaboveeachoftheRCScoldlegtemperatures, orthepressurizer watervolumeis(324cubicfeet(38%level).3-8