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| {{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSION,IntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant,UnitNo.1))))DocketNo))50244APPLICATIONFORAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RG&E"),holderofProvisionalOperatingLicenseNo.DPR-18,herebyrequeststhatSections3.1.4and4.1berevisedintheTechnicalSpecificationssetforthinAppendixAtothatlicense.ThisrequestforachangeinTechnicalSpecificationsissubmittedinresponsetoaletterdatedSeptember24,1981fromMr.DennisM.Crutchfield,Chief,OperatingReactorsBranchNo.5regardingreactorcoolantsystemiodineactivityTheproposedtechnicalspecificationchangeissetforthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachmentB.Thisevaluationalsodemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.TheproposedchangeshavebeenclearlyidentifiedasanNRCpositionintheNRC'sStandardTechnicalSpecificationsforWestinghouseplants.Thereforeafeeof$4,000isrequired.>>ooososo6>>o>~>'PDR.'ADQCK05000244.P-'~'":PDR'' | | {{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION, IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.1))))DocketNo))50244APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission" |
| fFrIFIttt WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoProvisionalOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.Whie,Jr.ExecutiveVicePresidentSubscribedandsworntobeforemeonthisl7dayofMay,1982.GARYL.EISSNRYPUBLIC,StateofN.Y.MonroeCo.hfyCommfssfonExpfresMarsh30,19~ | | ),Rochester GasandElectricCorporation |
| Iireg~-,~p)t~s.~',"3N0~4 AttachmentA1~RevisetheTechnicalSpecificationsbyreplacingthefollowingpages:3.1-21,'.1-22,3.1-23,3.1-24,4.1-8,4.1-9,4.1-10-2.Addpage4.1-12. | | ("RG&E"), |
| MaximumCoolantActivitSecifications:Wheneverthereactoriscriticalorthereactorcoolantaveragetemperatureisgreaterthan500oF:a.Thetotalspecificactivityofthereactorcoolantshallnotexceed84/EpCi/gm,whereEistheaveragebetaandgammaenergiesperdisintegrationinMev.b.TheI-131equivalentoftheiodineactivityinthereactorcoolantshallnotexceed1.0ju:i/gm.cdTheI-131equivalentoftheiodineactivityonthesecondarysideofasteamgeneratorshallnotexceed0~l~Ci/gm.Ifthelimitof3.1.4.l.aisexceeded,thenbesubcriticalwithreactorcoolantaveragetemperaturelessthan500Fwithin8hours.a~IftheI-131equivalentactivityinthereactorcoolantexceedsthelimitof3'.4.l.bbutislessthantheallowablelimitshownonFigure3.1.4-1,operationmaycontinueforupto48hoursprovidedthatthecumulativeoperatingtimeunderthesecircumstancesdoesnotexceed800hoursinanyconsecutive12-monthperiod.IftheI-131equivalentactivityinthereactorcoolantexceedsthelimitof3.1.4'.bformorethan500hoursinanyconsecutive6-monthperiod,3'-21AmendmentNo~8,rX8 thenprepareandsubmitaSpecialReporttotheCommissionpursuanttoSpecification6.9.2within30daysindicatingthenumberofhoursabovethislimit.Thereactormaybetakencriticalorreactorcoolantaveragetemperaturemaybeincreasedabovea500FwiththeI-131equivalentactivitygreaterthanthelimitof3.1.4.l.baslongastheprovisionsofthisparagrapharemet.b.IftheI-131equivalentactivityexceedsthe'limitof3.1.4.1.bformorethan48hoursduringonecontinuoustimeintervalorexceedsthelimitshownonFigure3.1.4-1,besubcriticalwithc~reactorcoolantaveragetemperaturelessthan500oFwithin8hours.IftheI-131equivalentactivityexceedsthelimitof3.1.4.l.b,thenperformsamplingandanalysisasrequiredbyTable4.1-4,item4a,untiltheactivityisreducedtolessthanthelimitof3.1~4-1.b.3-1.4.4Ifthelimitof3.1.4.1."cisexceeded,thenbeathotshutdownwithin8hoursandincoldshutdownwithinthefollowing32hours.Basis:Thetotalactivitylimitfortheprimarysystemcorrespondstooperationwiththeplantdesignbasisof1%fueldefects.Radiationshieldingandtheradioactivewastedisposalsystems3'-22AmendmentNo.g5 weredesignedforoperationwith1%defects.Thelimitforsecondaryiodineactivityisconservativelyestablishedwith,respecttothelimitsonprimarysystemiodineactivityandprimary-to-secondaryleakage(Specification3.1.5.2).Iftheactivityshouldexceedthespecifiedlimitsfollowingapowertransientthemajorconcernwouldbewhetheradditionalfueldefectshaddevelopedbringingthetotaltoabove1%defects.Appropriateactiontobetakentobringtheactivitywithinspecificationincludeoneormoreofthefollowing:gradualdecreaseinpowertoalowerbasepower,increaseinletdownflowrate,andventingofthevolumecontroltankgasestothegasdecaytanks.Thespecifiedactivitylimitsprovideprotectiontothepublicagainstthepotentialreleaseofreactorcoolantactivitytotheatmosphere,asdemonstratedbytheanalysisofasteamgeneratortube'uptureaccident.(3)The500Ftemperatureinthespecificationcorrespondsatsaturationto681psia,whichisbelowthesetpointofthesecondarysidereliefvalves.Therefore,potentialprimarytosecondaryleakageatatemperaturebelow500Fcanbecontainedbyclosingthesteamlineisolationvalves. | | holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhatSections3.1.4and4.1berevisedintheTechnical Specifications setforthinAppendixAtothatlicense.ThisrequestforachangeinTechnical Specifications issubmitted inresponsetoaletterdatedSeptember 24,1981fromMr.DennisM.Crutchfield, Chief,Operating ReactorsBranchNo.5regarding reactorcoolantsystemiodineactivityTheproposedtechnical specification changeissetforthinAttachment AtothisApplication. |
| | Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility. |
| | Theproposedchangeshavebeenclearlyidentified asanNRCpositionintheNRC'sStandardTechnical Specifications forWestinghouse plants.Therefore afeeof$4,000isrequired. |
| | >>ooososo6 |
| | >>o>~>'PDR.'ADQCK 05000244.P-'~'":PDR'' |
| | fFrIFIttt WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.Whie,Jr.Executive VicePresident Subscribed andsworntobeforemeonthisl7dayofMay,1982.GARYL.EISSNRYPUBLIC,StateofN.Y.MonroeCo.hfyCommfssfon ExpfresMarsh30,19~ |
| | Iireg~-,~p)t~s.~',"3N0~4 Attachment A1~RevisetheTechnical Specifications byreplacing thefollowing pages:3.1-21,'.1-22, 3.1-23,3.1-24,4.1-8,4.1-9,4.1-10-2.Addpage4.1-12. |
| | MaximumCoolantActivitSecifications: |
| | Wheneverthereactoriscriticalorthereactorcoolantaveragetemperature isgreaterthan500oF:a.Thetotalspecificactivityofthereactorcoolantshallnotexceed84/EpCi/gm, whereEistheaveragebetaandgammaenergiesperdisintegration inMev.b.TheI-131equivalent oftheiodineactivityinthereactorcoolantshallnotexceed1.0ju:i/gm. |
| | cdTheI-131equivalent oftheiodineactivityonthesecondary sideofasteamgenerator shallnotexceed0~l~Ci/gm.Ifthelimitof3.1.4.l.a isexceeded, thenbesubcritical withreactorcoolantaveragetemperature lessthan500Fwithin8hours.a~IftheI-131equivalent activityinthereactorcoolantexceedsthelimitof3'.4.l.bbutislessthantheallowable limitshownonFigure3.1.4-1,operation maycontinueforupto48hoursprovidedthatthecumulative operating timeunderthesecircumstances doesnotexceed800hoursinanyconsecutive 12-monthperiod.IftheI-131equivalent activityinthereactorcoolantexceedsthelimitof3.1.4'.bformorethan500hoursinanyconsecutive 6-monthperiod,3'-21Amendment No~8,rX8 thenprepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2within30daysindicating thenumberofhoursabovethislimit.Thereactormaybetakencriticalorreactorcoolantaveragetemperature maybeincreased abovea500FwiththeI-131equivalent activitygreaterthanthelimitof3.1.4.l.b aslongastheprovisions ofthisparagraph aremet.b.IftheI-131equivalent activityexceedsthe'limitof3.1.4.1.b formorethan48hoursduringonecontinuous timeintervalorexceedsthelimitshownonFigure3.1.4-1,besubcritical withc~reactorcoolantaveragetemperature lessthan500oFwithin8hours.IftheI-131equivalent activityexceedsthelimitof3.1.4.l.b, thenperformsamplingandanalysisasrequiredbyTable4.1-4,item4a,untiltheactivityisreducedtolessthanthelimitof3.1~4-1.b.3-1.4.4Ifthelimitof3.1.4.1."c isexceeded, thenbeathotshutdownwithin8hoursandincoldshutdownwithinthefollowing 32hours.Basis:Thetotalactivitylimitfortheprimarysystemcorresponds tooperation withtheplantdesignbasisof1%fueldefects.Radiation shielding andtheradioactive wastedisposalsystems3'-22Amendment No.g5 weredesignedforoperation with1%defects.Thelimitforsecondary iodineactivityisconservatively established with,respecttothelimitsonprimarysystemiodineactivityandprimary-to-secondary leakage(Specification 3.1.5.2). |
| | Iftheactivityshouldexceedthespecified limitsfollowing apowertransient themajorconcernwouldbewhetheradditional fueldefectshaddeveloped bringingthetotaltoabove1%defects.Appropriate actiontobetakentobringtheactivitywithinspecification includeoneormoreofthefollowing: |
| | gradualdecreaseinpowertoalowerbasepower,increaseinletdownflowrate,andventingofthevolumecontroltankgasestothegasdecaytanks.Thespecified activitylimitsprovideprotection tothepublicagainstthepotential releaseofreactorcoolantactivitytotheatmosphere, asdemonstrated bytheanalysisofasteamgenerator tube'upture accident. |
| | (3)The500Ftemperature inthespecification corresponds atsaturation to681psia,whichisbelowthesetpointofthesecondary sidereliefvalves.Therefore, potential primarytosecondary leakageatatemperature below500Fcanbecontained byclosingthesteamlineisolation valves. |
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| ==References:== | | ==References:== |
| (1)FSARTable9.2-5(2)FSARSection11.1.3(3)LetterdatedSeptember24,1981fromDennisM.Crutchfield,USNRC,toJohnE.Maier,RGSE.3.1-23 25O~.~l~ftfI'1~jl~LLLfpHMOOHHO200150'jUNACCEPl"ABlEOPERATIONOOOIX0OC4RHCX10050P-;CCf=PYAOLEOPCPiAfIONIH0,J..2030405060708090100PERCENTOFRATEDTHERMALPOWERFigure3.1.4-1I-131Equivalent,ReactorCoolantSpecificActivityLimitVersusPercentofRatedThermalPowerwiththeReactorCoolantSpecificActivity1.0pCi/gramI-131Equivalent3.1-24 TABLE4.1-2'MINIMUMFREQUENCIESPOREQUIPMENTANDSAMPLINGTESTSFSARSectionReference1.ReactorCoolantChemistrySamplesTestChlorideandFluorideFree@en~3times/weekandatleasteverythirdday5times/weekandatleast.everyseconddayexceptwhenbelow250oF2.ReactorCoolantBoronBoronconcentrationWeekly3.RefuelingWaterStorageTankWaterSample4.BoricAcidTank5.ControlRodsBoronconcentrationBoronconcentrationRoddroptimesofallfulllengthrodsIWeeklyTwice/weekAftervesselheadremovalandatleastonceper18months(1)6.FullLengthControlRod7.PressurizerSafetyValves8.MainSteamSafetyValves9.ContainmentIsolationTripMvementofatleast10stepsinanyonedirec-tionforanyrodnotfullyinsertedSetpointSetpointFunctioningMonthlyEachRefuelingshutdawnEachRefuelingshutdawnEachRefuelingShutdawn1010.RefuelingSystemInterlocksFunctioningPriortoRefuelingOperations9.4.5ll.ServiceWat,erSystemFunctioningEachRefuelingShutdawn9.5.5,12.FireProtectionPumpAuctioningandPawerSupplyMonthly9.5.54.1-8AmendmentNo.p,pp,yy,yp FSARSectionReference14.Accumulator15.PrimarySystem~geBoronConcentrationEvaluateTest13.SprayAdditiveTankNaOHConcent.Fre~en~cmonthlyBi-MonthlyDaily17.SpentFuelPit18.SecondaryCoolantSamplesBoronConcentrationGrossactivity16.DieselFuelSupplyFuelInventoryDailymonthly72hours(2)(3)8.2.39.5.519.CirculatingWaterFloodProtectionEquignentCalibrateEachRefuelingShutdownNotes:(1)Alsorequiredforspecificallyaffectedindividualrodsfollowinganymaintenanceonormodificationtothecontrolroddrivesystemwhichcouldaffectthedroptimeofthosespecificrods.(2)Notrequiredduringacoldorrefuelingshutdown.(3)AnisotopicanalysisforI-131equivalentactivityisrequiredatleastmonthlywheneverthegrossactivitydeterminationindicatesiodineconcentrationgreaterthanlOSoftheallowablelimitbutonlyonceper6rmnthswheneverthegrossactivitydeterminationindicatesiodineconcentrationbelow10%oftheallmrhlelimit.4.1-9AmendmentNo.Q,gg,/gal INTENTIONALLYBLANK4.1-10 AttachmentBTheTechnicalSpecificationlimitsforreactorcoolantsystemI-131equivalentactivityandforcoolantactivitysamplinghavebeenrevisedtobeconsistentwiththeNRC'sStandardTechnicalSpecificationsforWestinghouse-designedplants.Theactivitylimitsare.conservativewithrespecttotheassumptionsusedintheNRC'sanalysisofasteamgeneratortuberuptureeventwhichwasprovidedtoRGGEbyletterdatedSeptember24,1981. | | |
| TABLE4.1-4.i'v'Ti0REACTORCOOLANTSPECIFICACTIVITYSAMPLETYPEOFMEASUREMENTANDANALYSISANDANALYSISPROGRAMSAMPLEANDANALYSISFREQUENCYMODESINWHICHSAMPLEANDANALYSISREQUIREDGrossActivityDeterminationAtleastonceper72hours(beta-gamma)(1)Abovecoldshutdown2~3IsotopicAnalysisforDoseEquivalentI-131Concentra-tionRadiochemicalforEDetermination(2)IsotopicAnalysisforIodineIncludingI-131,I-133,andI-1351per14days1per6months(3)a)Onceper4hours,whenevertheI-131equivalentactivityexceedsthelimitof3.1~4.l.bAbove5treactorpowerAbove5%reactorpowerAsrequiredbySpecificati'on3.1.4.3.c*b)Onesamplebetween2and6hoursfollowingareactorpowerchangeexceeding15per-centwithina1-hourperiodHotshutdownorabove(1)Agrossradioactivityanalysisshallconsistofthequantitativemeasurementofthetotalradio-activityoftheprimarycoolantinunits~i/gm.Thetotalprimarycoolantactivityshallbethesumofthedegassedbeta-gammaactivityandthetotalofallidentifiedgaseousactivit'5minutesaftertheprimarysystemissampled.(2)Aradiochemicalanalysisshallconsistofthequantitativemeasurementoftheactivityforeachradionuclidewhichisidentifiedintheprimarycoolant15minutesaftertheprimarysystemissampled.TheactivitiesfortheindividualisotopesshallbeusedinthedeterminationofE.(3)Sampletobetakenafteraminimumof2EFPDand20daysofpoweroperationhaveelapsedsincereactorwaslastsubcriticalfor48hoursorlonger.*Exceptatrefuelingshutdown,samplingshallbecontinueduntiltheactivityofthereactorcoolantsystemisrestoredtowithinitslimits. | | (1)FSARTable9.2-5(2)FSARSection11.1.3(3)LetterdatedSeptember 24,1981fromDennisM.Crutchfield, USNRC,toJohnE.Maier,RGSE.3.1-23 25O~.~l~ftfI'1~jl~LLLfpHMOOHHO200150'jUNACCEPl"ABl EOPERATION OOOIX0OC4RHCX10050P-;CCf=PYAOLE OPCPiAfIONIH0,J..2030405060708090100PERCENTOFRATEDTHERMALPOWERFigure3.1.4-1I-131Equivalent, ReactorCoolantSpecificActivityLimitVersusPercentofRatedThermalPowerwiththeReactorCoolantSpecificActivity1.0pCi/gram I-131Equivalent 3.1-24 TABLE4.1-2'MINIMUMFREQUENCIES POREQUIPMENT ANDSAMPLINGTESTSFSARSectionReference 1.ReactorCoolantChemistry SamplesTestChlorideandFluorideFree@en~3times/week andatleasteverythirdday5times/week andatleast.everyseconddayexceptwhenbelow250oF2.ReactorCoolantBoronBoronconcentration Weekly3.Refueling WaterStorageTankWaterSample4.BoricAcidTank5.ControlRodsBoronconcentration Boronconcentration RoddroptimesofallfulllengthrodsIWeeklyTwice/week Aftervesselheadremovalandatleastonceper18months(1)6.FullLengthControlRod7.Pressurizer SafetyValves8.MainSteamSafetyValves9.Containment Isolation TripMvementofatleast10stepsinanyonedirec-tionforanyrodnotfullyinsertedSetpointSetpointFunctioning MonthlyEachRefueling shutdawnEachRefuelingshutdawnEachRefueling Shutdawn1010.Refueling SystemInterlocks Functioning PriortoRefueling Operations 9.4.5ll.ServiceWat,erSystemFunctioning EachRefueling Shutdawn9.5.5,12.FireProtection PumpAuctioning andPawerSupplyMonthly9.5.54.1-8Amendment No.p,pp,yy,yp FSARSectionReference 14.Accumulator 15.PrimarySystem~geBoronConcentration EvaluateTest13.SprayAdditiveTankNaOHConcent.Fre~en~cmonthlyBi-Monthly Daily17.SpentFuelPit18.Secondary CoolantSamplesBoronConcentration Grossactivity16.DieselFuelSupplyFuelInventory Dailymonthly72hours(2)(3)8.2.39.5.519.Circulating WaterFloodProtection Equignent Calibrate EachRefueling ShutdownNotes:(1)Alsorequiredforspecifically affectedindividual rodsfollowing anymaintenance onormodification tothecontrolroddrivesystemwhichcouldaffectthedroptimeofthosespecificrods.(2)Notrequiredduringacoldorrefueling shutdown. |
| | (3)AnisotopicanalysisforI-131equivalent activityisrequiredatleastmonthlywheneverthegrossactivitydetermination indicates iodineconcentration greaterthanlOSoftheallowable limitbutonlyonceper6rmnthswheneverthegrossactivitydetermination indicates iodineconcentration below10%oftheallmrhlelimit.4.1-9Amendment No.Q,gg,/gal INTENTIONALLY BLANK4.1-10 Attachment BTheTechnical Specification limitsforreactorcoolantsystemI-131equivalent activityandforcoolantactivitysamplinghavebeenrevisedtobeconsistent withtheNRC'sStandardTechnical Specifications forWestinghouse-designed plants.Theactivitylimitsare.conservative withrespecttotheassumptions usedintheNRC'sanalysisofasteamgenerator tuberuptureeventwhichwasprovidedtoRGGEbyletterdatedSeptember 24,1981. |
| | TABLE4.1-4.i'v'Ti0REACTORCOOLANTSPECIFICACTIVITYSAMPLETYPEOFMEASUREMENT ANDANALYSISANDANALYSISPROGRAMSAMPLEANDANALYSISFREQUENCY MODESINWHICHSAMPLEANDANALYSISREQUIREDGrossActivityDetermination Atleastonceper72hours(beta-gamma) |
| | (1)Abovecoldshutdown2~3IsotopicAnalysisforDoseEquivalent I-131Concentra-tionRadiochemical forEDetermination (2)IsotopicAnalysisforIodineIncluding I-131,I-133,andI-1351per14days1per6months(3)a)Onceper4hours,whenevertheI-131equivalent activityexceedsthelimitof3.1~4.l.bAbove5treactorpowerAbove5%reactorpowerAsrequiredbySpecificati'on 3.1.4.3.c* |
| | b)Onesamplebetween2and6hoursfollowing areactorpowerchangeexceeding 15per-centwithina1-hourperiodHotshutdownorabove(1)Agrossradioactivity analysisshallconsistofthequantitative measurement ofthetotalradio-activityoftheprimarycoolantinunits~i/gm. |
| | Thetotalprimarycoolantactivityshallbethesumofthedegassedbeta-gamma activityandthetotalofallidentified gaseousactivit'5 minutesaftertheprimarysystemissampled.(2)Aradiochemical analysisshallconsistofthequantitative measurement oftheactivityforeachradionuclide whichisidentified intheprimarycoolant15minutesaftertheprimarysystemissampled.Theactivities fortheindividual isotopesshallbeusedinthedetermination ofE.(3)Sampletobetakenafteraminimumof2EFPDand20daysofpoweroperation haveelapsedsincereactorwaslastsubcritical for48hoursorlonger.*Exceptatrefueling |
| | : shutdown, samplingshallbecontinued untiltheactivityofthereactorcoolantsystemisrestoredtowithinitslimits. |
| 0e}} | | 0e}} |
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High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re 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 Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION, IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.1))))DocketNo))50244APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
),Rochester GasandElectricCorporation
("RG&E"),
holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhatSections3.1.4and4.1berevisedintheTechnical Specifications setforthinAppendixAtothatlicense.ThisrequestforachangeinTechnical Specifications issubmitted inresponsetoaletterdatedSeptember 24,1981fromMr.DennisM.Crutchfield, Chief,Operating ReactorsBranchNo.5regarding reactorcoolantsystemiodineactivityTheproposedtechnical specification changeissetforthinAttachment AtothisApplication.
Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
Theproposedchangeshavebeenclearlyidentified asanNRCpositionintheNRC'sStandardTechnical Specifications forWestinghouse plants.Therefore afeeof$4,000isrequired.
>>ooososo6
>>o>~>'PDR.'ADQCK 05000244.P-'~'":PDR
fFrIFIttt WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.Whie,Jr.Executive VicePresident Subscribed andsworntobeforemeonthisl7dayofMay,1982.GARYL.EISSNRYPUBLIC,StateofN.Y.MonroeCo.hfyCommfssfon ExpfresMarsh30,19~
Iireg~-,~p)t~s.~',"3N0~4 Attachment A1~RevisetheTechnical Specifications byreplacing thefollowing pages:3.1-21,'.1-22, 3.1-23,3.1-24,4.1-8,4.1-9,4.1-10-2.Addpage4.1-12.
MaximumCoolantActivitSecifications:
Wheneverthereactoriscriticalorthereactorcoolantaveragetemperature isgreaterthan500oF:a.Thetotalspecificactivityofthereactorcoolantshallnotexceed84/EpCi/gm, whereEistheaveragebetaandgammaenergiesperdisintegration inMev.b.TheI-131equivalent oftheiodineactivityinthereactorcoolantshallnotexceed1.0ju:i/gm.
cdTheI-131equivalent oftheiodineactivityonthesecondary sideofasteamgenerator shallnotexceed0~l~Ci/gm.Ifthelimitof3.1.4.l.a isexceeded, thenbesubcritical withreactorcoolantaveragetemperature lessthan500Fwithin8hours.a~IftheI-131equivalent activityinthereactorcoolantexceedsthelimitof3'.4.l.bbutislessthantheallowable limitshownonFigure3.1.4-1,operation maycontinueforupto48hoursprovidedthatthecumulative operating timeunderthesecircumstances doesnotexceed800hoursinanyconsecutive 12-monthperiod.IftheI-131equivalent activityinthereactorcoolantexceedsthelimitof3.1.4'.bformorethan500hoursinanyconsecutive 6-monthperiod,3'-21Amendment No~8,rX8 thenprepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2within30daysindicating thenumberofhoursabovethislimit.Thereactormaybetakencriticalorreactorcoolantaveragetemperature maybeincreased abovea500FwiththeI-131equivalent activitygreaterthanthelimitof3.1.4.l.b aslongastheprovisions ofthisparagraph aremet.b.IftheI-131equivalent activityexceedsthe'limitof3.1.4.1.b formorethan48hoursduringonecontinuous timeintervalorexceedsthelimitshownonFigure3.1.4-1,besubcritical withc~reactorcoolantaveragetemperature lessthan500oFwithin8hours.IftheI-131equivalent activityexceedsthelimitof3.1.4.l.b, thenperformsamplingandanalysisasrequiredbyTable4.1-4,item4a,untiltheactivityisreducedtolessthanthelimitof3.1~4-1.b.3-1.4.4Ifthelimitof3.1.4.1."c isexceeded, thenbeathotshutdownwithin8hoursandincoldshutdownwithinthefollowing 32hours.Basis:Thetotalactivitylimitfortheprimarysystemcorresponds tooperation withtheplantdesignbasisof1%fueldefects.Radiation shielding andtheradioactive wastedisposalsystems3'-22Amendment No.g5 weredesignedforoperation with1%defects.Thelimitforsecondary iodineactivityisconservatively established with,respecttothelimitsonprimarysystemiodineactivityandprimary-to-secondary leakage(Specification 3.1.5.2).
Iftheactivityshouldexceedthespecified limitsfollowing apowertransient themajorconcernwouldbewhetheradditional fueldefectshaddeveloped bringingthetotaltoabove1%defects.Appropriate actiontobetakentobringtheactivitywithinspecification includeoneormoreofthefollowing:
gradualdecreaseinpowertoalowerbasepower,increaseinletdownflowrate,andventingofthevolumecontroltankgasestothegasdecaytanks.Thespecified activitylimitsprovideprotection tothepublicagainstthepotential releaseofreactorcoolantactivitytotheatmosphere, asdemonstrated bytheanalysisofasteamgenerator tube'upture accident.
(3)The500Ftemperature inthespecification corresponds atsaturation to681psia,whichisbelowthesetpointofthesecondary sidereliefvalves.Therefore, potential primarytosecondary leakageatatemperature below500Fcanbecontained byclosingthesteamlineisolation valves.
References:
(1)FSARTable9.2-5(2)FSARSection11.1.3(3)LetterdatedSeptember 24,1981fromDennisM.Crutchfield, USNRC,toJohnE.Maier,RGSE.3.1-23 25O~.~l~ftfI'1~jl~LLLfpHMOOHHO200150'jUNACCEPl"ABl EOPERATION OOOIX0OC4RHCX10050P-;CCf=PYAOLE OPCPiAfIONIH0,J..2030405060708090100PERCENTOFRATEDTHERMALPOWERFigure3.1.4-1I-131Equivalent, ReactorCoolantSpecificActivityLimitVersusPercentofRatedThermalPowerwiththeReactorCoolantSpecificActivity1.0pCi/gram I-131Equivalent 3.1-24 TABLE4.1-2'MINIMUMFREQUENCIES POREQUIPMENT ANDSAMPLINGTESTSFSARSectionReference 1.ReactorCoolantChemistry SamplesTestChlorideandFluorideFree@en~3times/week andatleasteverythirdday5times/week andatleast.everyseconddayexceptwhenbelow250oF2.ReactorCoolantBoronBoronconcentration Weekly3.Refueling WaterStorageTankWaterSample4.BoricAcidTank5.ControlRodsBoronconcentration Boronconcentration RoddroptimesofallfulllengthrodsIWeeklyTwice/week Aftervesselheadremovalandatleastonceper18months(1)6.FullLengthControlRod7.Pressurizer SafetyValves8.MainSteamSafetyValves9.Containment Isolation TripMvementofatleast10stepsinanyonedirec-tionforanyrodnotfullyinsertedSetpointSetpointFunctioning MonthlyEachRefueling shutdawnEachRefuelingshutdawnEachRefueling Shutdawn1010.Refueling SystemInterlocks Functioning PriortoRefueling Operations 9.4.5ll.ServiceWat,erSystemFunctioning EachRefueling Shutdawn9.5.5,12.FireProtection PumpAuctioning andPawerSupplyMonthly9.5.54.1-8Amendment No.p,pp,yy,yp FSARSectionReference 14.Accumulator 15.PrimarySystem~geBoronConcentration EvaluateTest13.SprayAdditiveTankNaOHConcent.Fre~en~cmonthlyBi-Monthly Daily17.SpentFuelPit18.Secondary CoolantSamplesBoronConcentration Grossactivity16.DieselFuelSupplyFuelInventory Dailymonthly72hours(2)(3)8.2.39.5.519.Circulating WaterFloodProtection Equignent Calibrate EachRefueling ShutdownNotes:(1)Alsorequiredforspecifically affectedindividual rodsfollowing anymaintenance onormodification tothecontrolroddrivesystemwhichcouldaffectthedroptimeofthosespecificrods.(2)Notrequiredduringacoldorrefueling shutdown.
(3)AnisotopicanalysisforI-131equivalent activityisrequiredatleastmonthlywheneverthegrossactivitydetermination indicates iodineconcentration greaterthanlOSoftheallowable limitbutonlyonceper6rmnthswheneverthegrossactivitydetermination indicates iodineconcentration below10%oftheallmrhlelimit.4.1-9Amendment No.Q,gg,/gal INTENTIONALLY BLANK4.1-10 Attachment BTheTechnical Specification limitsforreactorcoolantsystemI-131equivalent activityandforcoolantactivitysamplinghavebeenrevisedtobeconsistent withtheNRC'sStandardTechnical Specifications forWestinghouse-designed plants.Theactivitylimitsare.conservative withrespecttotheassumptions usedintheNRC'sanalysisofasteamgenerator tuberuptureeventwhichwasprovidedtoRGGEbyletterdatedSeptember 24,1981.
TABLE4.1-4.i'v'Ti0REACTORCOOLANTSPECIFICACTIVITYSAMPLETYPEOFMEASUREMENT ANDANALYSISANDANALYSISPROGRAMSAMPLEANDANALYSISFREQUENCY MODESINWHICHSAMPLEANDANALYSISREQUIREDGrossActivityDetermination Atleastonceper72hours(beta-gamma)
(1)Abovecoldshutdown2~3IsotopicAnalysisforDoseEquivalent I-131Concentra-tionRadiochemical forEDetermination (2)IsotopicAnalysisforIodineIncluding I-131,I-133,andI-1351per14days1per6months(3)a)Onceper4hours,whenevertheI-131equivalent activityexceedsthelimitof3.1~4.l.bAbove5treactorpowerAbove5%reactorpowerAsrequiredbySpecificati'on 3.1.4.3.c*
b)Onesamplebetween2and6hoursfollowing areactorpowerchangeexceeding 15per-centwithina1-hourperiodHotshutdownorabove(1)Agrossradioactivity analysisshallconsistofthequantitative measurement ofthetotalradio-activityoftheprimarycoolantinunits~i/gm.
Thetotalprimarycoolantactivityshallbethesumofthedegassedbeta-gamma activityandthetotalofallidentified gaseousactivit'5 minutesaftertheprimarysystemissampled.(2)Aradiochemical analysisshallconsistofthequantitative measurement oftheactivityforeachradionuclide whichisidentified intheprimarycoolant15minutesaftertheprimarysystemissampled.Theactivities fortheindividual isotopesshallbeusedinthedetermination ofE.(3)Sampletobetakenafteraminimumof2EFPDand20daysofpoweroperation haveelapsedsincereactorwaslastsubcritical for48hoursorlonger.*Exceptatrefueling
- shutdown, samplingshallbecontinued untiltheactivityofthereactorcoolantsystemisrestoredtowithinitslimits.
0e