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| {{#Wiki_filter:REGULAYINFORMATIONDISTRIBUTIOYSTEM(RIDS)ACCESSIONNBR:8804120332DOC.DATE:88/04/ObNOTARIZED:NOFACIL:50-335-St.LuciePlantiUnitiiFloridaPower5LightCo.AUTH.NAMEAUTHORAFFIL1ATIONCONMAY>W.F.FloridaPower5LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET005000335 | | {{#Wiki_filter:REGULAYINFORMATION DISTRIBUTIO YSTEM(RIDS)ACCESSION NBR:8804120332 DOC.DATE:88/04/ObNOTARIZED: |
| | NOFACIL:50-335-St. |
| | LuciePlantiUnitiiFloridaPower5LightCo.AUTH.NAMEAUTHORAFFIL1ATIONCONMAY>W.F.FloridaPower5LightCo.RECIP.NAMERECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET005000335 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsaddiinfoonproposedlicenseamendreboricacidconcentrationreductionsperNRC880310request.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRiENCLISIZE:TITLE:ORSubmittal:GeneralDistributionRECIPIENTIDCODE/NAMEPD2-2LATOURIGNY>EINTERNAL:ACRSNRR/DEBT/ADS7ENRR/DEST/ESB8DNRR/DEST/RSB8EILRB1201EXTERNAL:LPDRNSICCOPIESLTTRENCL101166111111111111RECIPIENTIDCODE/NAMEPD2-2PDARM/DAF/LFMBNRR/DEST/CEB8HNRR/DEST/MTB9HNRR/DOEA/TSB11OQC15-B-18RES/DE/EIBNRCPDRCOPIESLTTRENCL5510111111101TOTALNUMBEROFCOPIESREQUIRED:LTTR27ENCL24 JtI!)<i/'Pt1]V~I4fV P.O.14000,JUNOBEACH,FL33408.0420@Llky~'APRIB061988L-88-168U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnit1DocketNo.50-335RequestforAdditionalInformation-BoricAcidConcentrationReductionPerletterL-88-37datedJanuary22,1988,FloridaPowerLightCompany(FPL)submittedaproposedlicenseamendmentconcerningboricacidconcentrationreductionatSt.LucieUnitl.AtelephoneconferencecallwasheldbetweenFPLandtheSt.LucieNRCProjectManageronMarch10,1988todiscussquestionsrelatingtothissubmittal.ThepurposeofthisletteristoprovideFPL'sresponsetocertainofthesequestionsasdiscussedduringtheconferencecall.Shouldtherebefurtherquestions,pleasecontactus.Verytrulyyours,W.F.ConyActingGroupVicePresidentNuclearEnergyWFC/MSD/gpAttachmentcc:Dr.J.NelsonGrace,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlantMSD.RAISSO4>~0~~OPPg3588Omb~PDRADOCH.0pjanFPLGroupcompany
| | Forwardsaddiinfoonproposedlicenseamendreboricacidconcentration reductions perNRC880310request.DISTRIBUTION CODE:A001DCOPIESRECEIVED: |
| | LTRiENCLISIZE:TITLE:ORSubmittal: |
| | GeneralDistribution RECIPIENTIDCODE/NAME PD2-2LATOURIGNY> |
| | EINTERNAL: |
| | ACRSNRR/DEBT/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8EILRB1201EXTERNAL: |
| | LPDRNSICCOPIESLTTRENCL101166111111111111RECIPIENT IDCODE/NAME PD2-2PDARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DOEA/TSB 11OQC15-B-18RES/DE/EIB NRCPDRCOPIESLTTRENCL5510111111101TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR27ENCL24 JtI!)<i/'Pt1]V~I4fV P.O.14000,JUNOBEACH,FL33408.0420 |
| | @Llky~'APRIB061988L-88-168U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | Re:St.LucieUnit1DocketNo.50-335RequestforAdditional Information-BoricAcidConcentration Reduction PerletterL-88-37datedJanuary22,1988,FloridaPowerLightCompany(FPL)submitted aproposedlicenseamendment concerning boricacidconcentration reduction atSt.LucieUnitl.Atelephone conference callwasheldbetweenFPLandtheSt.LucieNRCProjectManageronMarch10,1988todiscussquestions relatingtothissubmittal. |
| | ThepurposeofthisletteristoprovideFPL'sresponsetocertainofthesequestions asdiscussed duringtheconference call.Shouldtherebefurtherquestions, pleasecontactus.Verytrulyyours,W.F.ConyActingGroupVicePresident NuclearEnergyWFC/MSD/gp Attachment cc:Dr.J.NelsonGrace,RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlantMSD.RAISSO4>~0~~ |
| | OPPg3588Omb~PDRADOCH.0pjanFPLGroupcompany |
| ~c~~ | | ~c~~ |
| ST.LUCIEUNITIrcAcrocoNcErrrorrrrorrREovcrrOFPLRESPONSETONRCRE(VESTFORADDITIONALINFORMATIONI.ContainmentSumandSraHEvaluationThefollowingabstractisprovidedtodelineatethemethodologyemployedtoevaluatetheeffectthatreducedboricacidconcentrationswouldhaveontheContainmentSumpandSpraypH:Aspartoftheboricacidconcentrationreductionprogram,theexistingFloridaPower&LightContainmentSumpandSpraypHcalculationwasrevisedtoreflectthenewoperatingparametersfortheBoricAcidMakeup(BAN)TanksasspecifiedbyCombustionEngineering(ReferenceCELetterNo.F-CE-10325datedOctober27,1987).Basedontheresultsoftherevisedcalculation,theoperatingconcentrationrangeforSodiumHydroxide(NaOH)intheChemicalStorageTank(CHST)isamendedtoreflectlowerboricacidconcentrationsasdelineatedinproposedTechnicalSpecification3.6.2.2.ToanalyzetheworstcasepHconditions,thecalculationinvolvedaniterativeprocesswherebythemaximumandminimumboricacidconcentrationsandwatervolumesforallavailableboratedwaterinventorieswereconsidered.Thecalculationwasseparatedintotwoparts:1.ContainmentSumppHEvaluation;and2.ContainmentSpraypHEvaluation.TheContainmentSumppHEvaluationdeterminedthehighandlowsumppHconsideringworstcasemixingofavailableboratedwaterinventories.TheContainmentSpraypHEvaluationdeterminedthehighandlowcontainmentspraynozzlepHduringbothinjectionandrecirculationmodes.TheContainmentSpraypHEvaluationrequiredtheanalysisofthefollowingconditions:off-site,poweravailable,nofailures;off-sitepoweravailable,singlecontainmentspraypumpavailable;andlossofoff-sitepower,singledieselgeneratoravailable.Whenthecalculationwasrevisedforthistask,allpartswerereworkedtodeterminepotentialimpactontheoperatingpHlimits.BasedontheresultsoftheContainmentSpraypHEvaluation,thepHatthecontainmentspraynozzleswasfoundtoexceedthemaximumallowedpHof11.0.Thisconditionwasfoundtoexistduringthebeginningofrecirculationforeachofthethreecasesidentifiedabove.InordertomaintaincontainmentspraypHwithintheallowablerangeof8.5-11.0,theCHSTNaOHconcentrationswereadjustedanditerationsperformeduntiltankconcentrationswereconsistentwiththerequiredpHvaluesatthespraynozzles.TheproposedmodificationtoTechnicalSpecification3.6.2.2,ChemicalStorageTankNaOHconcentrations,(from30%-32%to28.5%-30.5%byweight)reflectthecalculationresults.II.ReactorAuxiliarBuildinTemeratureMeasurementQUESTION:InregardstothesurveillancerequiredwhentheReactorAuxiliaryBuildingairtemperatureisless-than55Fandconsideringthephysicalsizeofthemulti-levelbuilding,pleasediscussthelocation(s)wheretheairtemperature(s)willbetakenandtherelationshipbetweenthelocation(s)andthelocation(s)ofallcomponentsoftheBAMUsystem.RESPONSE:AsdelineatedinFigure1,theaffectedheattracedpiping/componentswhichcomprisetheBoricAcidMakeupsystem(i.e.theboricacidmakeuptanks,boricacidmakeup p>pingandpipingtoth~uctionofthechargingpumps~relocatedinrelatively'loseproximityontheminM0.5ft.elevationoftheReaCWIAuxiliaryBuilding.Theexceptionistheboricacidmakeuptanks,whichhavetanktopsatelevation32.75ft.asshownonFigure2.Inaddition,theReactorAuxiliaryBuildingVentilationSystemisdesignedtomaintainauniformtemperaturethroughoutthebuilding( | | ST.LUCIEUNITIrcAcrocoNcErrrorrrrorr REovcrrOFPLRESPONSETONRCRE(VESTFORADDITIONAL INFORMATION I.Containment SumandSraHEvaluation Thefollowing abstractisprovidedtodelineate themethodology employedtoevaluatetheeffectthatreducedboricacidconcentrations wouldhaveontheContainment SumpandSpraypH:Aspartoftheboricacidconcentration reduction program,theexistingFloridaPower&LightContainment SumpandSpraypHcalculation wasrevisedtoreflectthenewoperating parameters fortheBoricAcidMakeup(BAN)Tanksasspecified byCombustion Engineering (Reference CELetterNo.F-CE-10325 datedOctober27,1987).Basedontheresultsoftherevisedcalculation, theoperating concentration rangeforSodiumHydroxide (NaOH)intheChemicalStorageTank(CHST)isamendedtoreflectlowerboricacidconcentrations asdelineated inproposedTechnical Specification 3.6.2.2.ToanalyzetheworstcasepHconditions, thecalculation involvedaniterative processwherebythemaximumandminimumboricacidconcentrations andwatervolumesforallavailable boratedwaterinventories wereconsidered. |
| | Thecalculation wasseparated intotwoparts:1.Containment SumppHEvaluation; and2.Containment SpraypHEvaluation. |
| | TheContainment SumppHEvaluation determined thehighandlowsumppHconsidering worstcasemixingofavailable boratedwaterinventories. |
| | TheContainment SpraypHEvaluation determined thehighandlowcontainment spraynozzlepHduringbothinjection andrecirculation modes.TheContainment SpraypHEvaluation requiredtheanalysisofthefollowing conditions: |
| | off-site, poweravailable, nofailures; off-sitepoweravailable, singlecontainment spraypumpavailable; andlossofoff-sitepower,singledieselgenerator available. |
| | Whenthecalculation wasrevisedforthistask,allpartswerereworkedtodetermine potential impactontheoperating pHlimits.BasedontheresultsoftheContainment SpraypHEvaluation, thepHatthecontainment spraynozzleswasfoundtoexceedthemaximumallowedpHof11.0.Thiscondition wasfoundtoexistduringthebeginning ofrecirculation foreachofthethreecasesidentified above.Inordertomaintaincontainment spraypHwithintheallowable rangeof8.5-11.0,theCHSTNaOHconcentrations wereadjustedanditerations performed untiltankconcentrations wereconsistent withtherequiredpHvaluesatthespraynozzles.Theproposedmodification toTechnical Specification 3.6.2.2,ChemicalStorageTankNaOHconcentrations, (from30%-32%to28.5%-30.5%byweight)reflectthecalculation results.II.ReactorAuxiliarBuildinTemeratureMeasurement QUESTION: |
| | Inregardstothesurveillance requiredwhentheReactorAuxiliary Buildingairtemperature isless-than55Fandconsidering thephysicalsizeofthemulti-level |
| | : building, pleasediscussthelocation(s) wheretheairtemperature(s) willbetakenandtherelationship betweenthelocation(s) andthelocation(s) ofallcomponents oftheBAMUsystem.RESPONSE: |
| | Asdelineated inFigure1,theaffectedheattracedpiping/components whichcomprisetheBoricAcidMakeupsystem(i.e.theboricacidmakeuptanks,boricacidmakeup p>pingandpipingtoth~uction ofthechargingpumps~relocatedinrelatively'loseproximity ontheminM0.5ft.elevation oftheReaCWIAuxiliary Building. |
| | Theexception istheboricacidmakeuptanks,whichhavetanktopsatelevation 32.75ft.asshownonFigure2.Inaddition, theReactorAuxiliary BuildingVentilation Systemisdesignedtomaintainauniformtemperature throughout thebuilding( |
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| ==Reference:== | | ==Reference:== |
| FinalSafetyAnalysisReportSection9.4.2.2.1).Basedupontheabove,theReactorAuxiliaryBuildingairtemperaturemeasurementwillbetakenattheBoricAcidMakeupStationasshownonFigure1.III.BoricAcidMakeuTankConcentrationQUESTION:ProposedTechnicalSpecification3.1.2.8.a.requiresaboricacidweightpercentrangeof3.2/to3.5/.ProposedT.S.3.1.2.8.b.requiresasimilarrange.PleaseexplainthesetwoproposedTechnicalSpecificationsinrelationshipto(1)theproposedbasesstatementspertheproposedPage63/41-2Insert,(2)proposedFigure3.1-1,(3)FPL'sboricacidconcentrationreductionsafetyevaluation,and(4)CombustionEngineeringReportCEN-353.RESPONSE:AsdelineatedinproposedTechnicalSpecificationFigure3.1-1,proposedPageB3/41-2Insert,andtheCombustionEngineeringReportCEN-353,thereductionofboricacidconcentrationto2.5/oto3.5%%ubyweightrequiresboratedwatervolumesof13,300(2.5/owt.)to8350(3.5/.wt.)gallons.Theboricacidmakeuptanksarecapableofholding9450gallonseach(thehighlevelalarmissetat97.5/ofthe9700gallontankcapacity).InordertomaintaintherequiredboratedwaterinventoryinoneboricacidmakeuptankandcomplywiththeproposedTechnicalSpecifications,theboricacidconcentrationmustbenolowerthan3.2Xbyweight.TechnicalSpecifications3.1.2.8.a.and3.1.2.8.b.arewrittentodelineatetheboricacidconcentrationrequirements(3.2/.to3.5/)whenonlyoneboricacidmakeuptankiscreditedwithbeinginservice.IV.BoricAcidConcentrationReductionUncertaintiesQUESTION:Page3oftheFloridaPower&Lightboricacidreductionsafetyevaluationspecifiestheuncertaintiesconsidered.Pleaseprovide:1)abriefdiscussionoftheuncertaintiesutilizedforscramworth,moderatortemperaturecoefficientandOopplercoefficient;and2)anexplanationfortheomissionofboronmeasurementuncertaintiesfromtheanalysis.RESPONSE:Acombinedbiasanduncertaintyof10%wasappliedto'hescramworthdatasuppliedtoCombustionEngineeringfromFloridaPower5Light.Thiscombinedbiasanduncertaintyis,consistentwiththelicensingmethodologyusedbyFloridaPower5Light'sUnit'fuelvendor(ANF)tocalculateshutdownmargin.Thescramworthisadditionallyconservativebecauseitisassumedtnattnemostworthycontrolelementassemblyisstuckoutofthecoreduringthescram.AconservativecorrectionwasappliedtothemoderatorcooldowncurvesuppliedtoCombustionEngineeringfromFloridaPower8Light.SinceCombustionEngineeringdid notgeneratethemodera~temperaturecoefficient(~curve,aconservativecorrectionwasappliedto~iscurvetomakeitconsiste~withthemethodsusedbyCombustionEngineeringwhengeneratingacooldowncurveforthemostnegativetechnicalspecificationMTClimitof-0.00028deltarho/F.Theapplicationofabiasof15/oandanuncertaintyof151totheDopplercoefficientsisconsistentwiththelicensingmethodologyusedforanalogplants.Thesefactorswereusedintheanalysis.AboronmeasurementuncertaintywasincludedintheLouisianaPower&Lightphysicsdatawhenthenaturalcirculationscenarioassumedthattheboronometerconcentrationwouldbeusedtoverifyreactorcoolantsystem(RCS)boronconcentration.Averyconservativeboronometermeasurementuncertainty(50ppm)wasaddedtotheRCSboronrequirements.AreviewofthecooldownscenarioshowsthattheadditionofaboronometermeasurementuncertaintytotheRCSboronrequirementsisunnecessary.ThecooldownscenarioinCEN353(F)identifiestheminimumvolumeofboricacidmakeuptankwaterwillensurethattheRCSisadequatelyborated.TheboronometerreadingswillnotbeusedduringthecooldownasacriteriatoreducetheamountofboricacidmakeuptankwaterdeliveredtotheRCSduringthiscooldown.Inconclusion,boronometermeasurementuncertaintiesneednotbeincludedintheborationrequirementcurvesforeitherplant.V.FIGURE3.1-1QUESTION:InregardtoproposedFigure3.1-1,pleaseexplainwhyitisnecessarytohaveatthebottomofthefiguretheexpression"1720ppmintheRWT."RESPONSE:WehavereviewedFigure3.1-1andhavedeterminedthattheexpression"1720ppmintheRWT"atthebottomofthefigureis'otnecessary.Therefore,weproposetoremovethisexpression(SeeattachedrevisedFigure3.1-1).rVI.BorationSstemBasesOuringatelephonecallonMarch16,1988betweentheNuclearRegulatoryCommissionSt.LucieProjectManagerandFloridaPower&Light,afollowupquestionwasdiscussedregardingboricacidadditionvolumesasdelineatedinTechnicalSpecificationBasesPagesB3/41-2andB3/41-3.TheboronadditioncapabilityforModes5and6,asdiscussedonBasesPageB3/41-3,includedconservatismsoutlinedinCEN-353(F),"BoricAcidConcentrationReductionEffort."However,theboronadditioncapabilityforModes1-4,discussedonBasesPageB3/41-2,donotincludetheconservatismsoutlinedinCEN-353(F).InordertoprovideconsistencyintheBasesdiscussion,weproposetorevisetheboronrangesforModes1-4toincludetheappropriateconservatisms.(SeeattachedrevisedinsertPageB3/41-2). | | |
| ISICIOIOIOPVCCI~VCCLCttr~<<aaI~PV~atatCIOraCC.OV/'PP~lateal~wa411~Iapraar~CCOI~tIIPIPwl~IIV4~~~P'CatlC~IIr~~PI\tlrltp\VIS~aIV0Ar41144411\'P'acaretI'II~W~~I~alta4PP~arwelI~I~rwaraa111114PPPCttrataPICOIVacr~pe44paawptel>>ISO,4av~h4paWl~'I~~weaLV~rWhaeavepwcatwIaaIp~IVWIIICV~CSapatpprwaaLi+I4~IPCCICp~~4Iawwpa~IVI'X.4~~IP1,41If7T'teI!65t.IRAN~ISIII.patap~CStra4~It~PreClaerlCatCa'I~t~CatIIRPI.EI.050CalralREFEROKECRAOTIOCSwtrrrappee~k4114CartacEac34OIaoraaap~~II:".Ct0HKW0C0WQtIIo5xMW4OWHCRR~r~ClaI$1lail141~~tal'CattaCPaRtOCAIIRIll.gttt.'0UlHwnx~VO0Hnu:RgCaH'0II6ICP~ItltaplaaapeaIW~PIW~PMeant4waaaa~rpIp~~<<crw4captrIw\IpwepwpaptIwepastw\peappapaa4p~awpperpwrap>>aepwwwtIPPIa~OOM~LNNTCCMCOrOTCOCOtlJOT~tei%wecrtpatcvIplcaIMklsMvpaltprvoMO FLOORIIIIPA'bSACsf.IEWTCOgFI.d'ON74VI%P<Ou~II.PiPETLNNEi-~Cu%bDuRiJ)CATsOg$<TCRISACID~~OlPIACNI4tCsl~Pvo+MPIPE7ijNOELdIIQvgRA4REACTORAUXILIARYBUILDING-SECTIONSFIGURE2R4bgSEGT10l4E.-f,QNG8170G070'-a)0-07IOCi4aQgtON31UJll04-'vavaRQO-reify FGURE4.1-1ST.LUCEIMNCkAMTYOLUME6EfMB9ÃCtIMNWIN13sC12000vns$Cgois11os)Vl0X(13I300)UNCETAOPRATACC(>>,0)LEQN~BEtTIO(9(835)36"Q(4196PPN)(4546PPN)(4895PPN)(5245PPH)(5595PPM)(5944PPN)(6294PPM)SI0IBMIXC(ltIhakaN)ST.LUCIE-UNIT13/41-17AanendttM.ntNo.M hcMO>carArnaofaon'CAf;co,o'tfn.)3o~sAc'J/YOJcc'PG~W~(l38Af~clg<gc(,Q,Pi<<g(I?ur).Tl'ZrnyC,'oEa.dolan//o>>$OF3soucg(fPOAcevfc5I(fggnfSodom~zn,g~~QADI~aJ/Yafoofolio~@oP/72~S...~~,lk.~i2~i+8,gaOoC4scucjjf.parcmk(vier/faunaCoro~)oor.cnc'48ABPsn.d9soaa(Alloc*4o7ll2MT.A,,ofgafooo~//~cogiu.O<~~Lou6iSrefIuirf.dgumtLfa!~7~gU~4.:4,7l.rQ.cS'/oc.}} | | FinalSafetyAnalysisReportSection9.4.2.2.1).Basedupontheabove,theReactorAuxiliary Buildingairtemperature measurement willbetakenattheBoricAcidMakeupStationasshownonFigure1.III.BoricAcidMakeuTankConcentration QUESTION: |
| | ProposedTechnical Specification 3.1.2.8.a.requiresaboricacidweightpercentrangeof3.2/to3.5/.ProposedT.S.3.1.2.8.b.requiresasimilarrange.PleaseexplainthesetwoproposedTechnical Specifications inrelationship to(1)theproposedbasesstatements pertheproposedPage63/41-2Insert,(2)proposedFigure3.1-1,(3)FPL'sboricacidconcentration reduction safetyevaluation, and(4)Combustion Engineering ReportCEN-353.RESPONSE: |
| | Asdelineated inproposedTechnical Specification Figure3.1-1,proposedPageB3/41-2Insert,andtheCombustion Engineering ReportCEN-353,thereduction ofboricacidconcentration to2.5/oto3.5%%ubyweightrequiresboratedwatervolumesof13,300(2.5/owt.)to8350(3.5/.wt.)gallons.Theboricacidmakeuptanksarecapableofholding9450gallonseach(thehighlevelalarmissetat97.5/ofthe9700gallontankcapacity). |
| | Inordertomaintaintherequiredboratedwaterinventory inoneboricacidmakeuptankandcomplywiththeproposedTechnical Specifications, theboricacidconcentration mustbenolowerthan3.2Xbyweight.Technical Specifications 3.1.2.8.a.and3.1.2.8.b.arewrittentodelineate theboricacidconcentration requirements (3.2/.to3.5/)whenonlyoneboricacidmakeuptankiscreditedwithbeinginservice.IV.BoricAcidConcentration Reduction Uncertainties QUESTION: |
| | Page3oftheFloridaPower&Lightboricacidreduction safetyevaluation specifies theuncertainties considered. |
| | Pleaseprovide:1)abriefdiscussion oftheuncertainties utilizedforscramworth,moderator temperature coefficient andOopplercoefficient; and2)anexplanation fortheomissionofboronmeasurement uncertainties fromtheanalysis. |
| | |
| | ===RESPONSE=== |
| | Acombinedbiasanduncertainty of10%wasappliedto'hescramworthdatasuppliedtoCombustion Engineering fromFloridaPower5Light.Thiscombinedbiasanduncertainty is,consistent withthelicensing methodology usedbyFloridaPower5Light'sUnit'fuelvendor(ANF)tocalculate shutdownmargin.Thescramworthisadditionally conservative becauseitisassumedtnattnemostworthycontrolelementassemblyisstuckoutofthecoreduringthescram.Aconservative correction wasappliedtothemoderator cooldowncurvesuppliedtoCombustion Engineering fromFloridaPower8Light.SinceCombustion Engineering did notgeneratethemodera~temperature coefficient |
| | (~curve,aconservative correction wasappliedto~iscurvetomakeitconsiste~with themethodsusedbyCombustion Engineering whengenerating acooldowncurveforthemostnegativetechnical specification MTClimitof-0.00028deltarho/F.Theapplication ofabiasof15/oandanuncertainty of151totheDopplercoefficients isconsistent withthelicensing methodology usedforanalogplants.Thesefactorswereusedintheanalysis. |
| | Aboronmeasurement uncertainty wasincludedintheLouisiana Power&Lightphysicsdatawhenthenaturalcirculation scenarioassumedthattheboronometer concentration wouldbeusedtoverifyreactorcoolantsystem(RCS)boronconcentration. |
| | Averyconservative boronometer measurement uncertainty (50ppm)wasaddedtotheRCSboronrequirements. |
| | Areviewofthecooldownscenarioshowsthattheadditionofaboronometer measurement uncertainty totheRCSboronrequirements isunnecessary. |
| | ThecooldownscenarioinCEN353(F)identifies theminimumvolumeofboricacidmakeuptankwaterwillensurethattheRCSisadequately borated.Theboronometer readingswillnotbeusedduringthecooldownasacriteriatoreducetheamountofboricacidmakeuptankwaterdelivered totheRCSduringthiscooldown. |
| | Inconclusion, boronometer measurement uncertainties neednotbeincludedintheborationrequirement curvesforeitherplant.V.FIGURE3.1-1QUESTION: |
| | InregardtoproposedFigure3.1-1,pleaseexplainwhyitisnecessary tohaveatthebottomofthefiguretheexpression" 1720ppmintheRWT."RESPONSE: |
| | WehavereviewedFigure3.1-1andhavedetermined thattheexpression "1720ppmintheRWT"atthebottomofthefigureis'otnecessary. |
| | Therefore, weproposetoremovethisexpression (SeeattachedrevisedFigure3.1-1).rVI.BorationSstemBasesOuringatelephone callonMarch16,1988betweentheNuclearRegulatory Commission St.LucieProjectManagerandFloridaPower&Light,afollowupquestionwasdiscussed regarding boricacidadditionvolumesasdelineated inTechnical Specification BasesPagesB3/41-2andB3/41-3.Theboronadditioncapability forModes5and6,asdiscussed onBasesPageB3/41-3,includedconservatisms outlinedinCEN-353(F), |
| | "BoricAcidConcentration Reduction Effort."However,theboronadditioncapability forModes1-4,discussed onBasesPageB3/41-2,donotincludetheconservatisms outlinedinCEN-353(F). |
| | Inordertoprovideconsistency intheBasesdiscussion, weproposetorevisetheboronrangesforModes1-4toincludetheappropriate conservatisms.(See attachedrevisedinsertPageB3/41-2). |
| | ISICIOIOIOPVCCI~VCCLCttr~<<aaI~PV~atatCIOraCC.OV/'PP~lateal~wa411~Iapraar~CCOI~tIIPIPwl~IIV4~~~P'CatlC~IIr~~PI\tlrltp\VIS~aIV0Ar41144411\'P'acaretI'II~W~~I~alta4PP~arwelI~I~rwaraa111114PPPCttrataPICOIVacr~pe44paawptel>>ISO,4av~h4paWl~'I~~weaLV~rWhaeavepwcatwIaaIp~IVWIIICV~CSapatpprwaaLi+I4~IPCCICp~~4Iawwpa~IVI'X.4~~IP1,41If7T'teI!65t.IRAN~ISIII.patap~CStra4~It~PreClaerlCatCa'I~t~CatIIRPI.EI.050CalralREFEROKECRAOTIOCS wtrrrappee~k4114CartacEac34OIaoraaap~~II:".Ct0HKW0C0WQtIIo5xMW4OWHCRR~r~ClaI$1lail141~~tal'CattaCPaRtOCAIIRIll.gttt.'0UlHwnx~VO0Hnu:RgCaH'0II6ICP~ItltaplaaapeaIW~PIW~PMeant4waaaa~rpIp~~<<crw4captrIw\IpwepwpaptIwepastw\peappapaa4p~awpperpwrap>>aepwwwtIPPIa~OOM~LNNTCCMCOrOTCOCOtlJOT~tei%wecrtpatcvIplcaIMklsMvpaltprvoMO FLOORIIIIPA'bSACsf. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML20217F6171999-10-0808 October 1999
Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML20212M1601999-09-28028 September 1999
Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML20209F1541999-07-0606 July 1999
Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
ML20195F3871999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML20207C7531999-05-17017 May 1999
Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML20205M0431999-04-13013 April 1999
Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
1999-09-28
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
ML17229B0851999-04-0505 April 1999
Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999
ML17309A9791999-03-31031 March 1999
Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed
ML17309A9761999-03-23023 March 1999
Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed
ML17229B0691999-03-19019 March 1999
Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit
ML17229B0721999-03-16016 March 1999
Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17355A2631999-03-12012 March 1999
Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit
ML17229B0481999-03-10010 March 1999
Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218
1999-09-25
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17223A9401990-09-13013 September 1990
Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility
ML17223A9341990-09-10010 September 1990
Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl
L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990
Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8
ML17223A9201990-08-28028 August 1990
Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr
ML17223A8911990-08-20020 August 1990
Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience
ML17348A5041990-08-17017 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990
L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990
Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant
ML17223A8751990-08-0909 August 1990
Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor
IR 05000335/19900141990-08-0909 August 1990
Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor
ML17348A4701990-07-27027 July 1990
Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing
ML17223A8621990-07-25025 July 1990
Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831
ML17348A4281990-07-25025 July 1990
Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b)
ML17223A8631990-07-25025 July 1990
Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage
L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990
Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders
ML17223A8581990-07-19019 July 1990
Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants
ML17223A8491990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor
ML17223A8521990-07-17017 July 1990
Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program
IR 05000335/19900131990-07-0909 July 1990
Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements
ML17223A8421990-07-0909 July 1990
Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements
ML17348A3881990-07-0505 July 1990
Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs
ML17223A8391990-07-0303 July 1990
Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3
ML17223A8381990-07-0202 July 1990
Requests Termination of Operator License for s Lavelle.Util Also Requests That Ltr Be Withheld (Ref 10CFR2.790)
L-90-239, Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990
Forwards Rev 6 to Guard Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)
ML17223A8371990-06-27027 June 1990
Provides Details of Implementation Plan Re Recommendations & Schedular Requirements in Generic Ltr 89-10,per 891228 Ltr.Design Basis Review of safety-related motor-operated Valves & Determination of Switch Settings in Progress
ML17308A4981990-06-27027 June 1990
Responds to Generic Ltr 90-04 Re Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
ML17223A8341990-06-19019 June 1990
Forwards Corrected Proposed Tech Spec Figure 3.4-2 Per 900207 Application for Amend to License NPF-16,incorporating Revised Pressure/Temp Limits & Results of Revised Low Temp Overpressure Protection Analysis Into Tech Specs
ML17223A8241990-06-18018 June 1990
Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988.
ML17223A8271990-06-18018 June 1990
Forwards Ma Smith 900601 Ltr to WR Cunningham of EPA Requesting Mod to Plant NPDES Permit to Permit Cleaning of Facility & to Establish Discharge Limits for Chemical Cleaning Wastes
ML17348A2981990-06-12012 June 1990
Forwards Rev 16 to Topical QA Rept.
ML17223A6761990-05-31031 May 1990
Advises That Air Operated safety-related Components Will Perform All Design Basis Events,Per 881227 Ltr.All Actions Required by Generic Ltr 88-14 Complete for Plant
ML17348A2651990-05-29029 May 1990
Submits Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per 10CFR26,App A.2.8(e)(4)
ML17223A6741990-05-22022 May 1990
Forwards Info Re Status of 10CFR50.62 Mods to Meet ATWS Requirements as of 900515.Plant Change/Mod Package Necessary for Installing ATWS Will Be Issued by 900630.Hardware Procurement for Diverse Scram Sys Approx 90% Complete
ML17223A6361990-05-0808 May 1990
Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker
ML17223A6281990-04-21021 April 1990
Forwards St Lucie Unit 2 Annual Environ Operating Rept, Vol 1 1989.
ML17223A6081990-04-13013 April 1990
Responds to Violations Noted in Insp Repts 50-335/90-02 & 50-389/90-02.Corrective Actions:Nuclear Plant Supervisor Required to Remain in Control Room During Significant Changes in Power Operation & Preventive Maint Upgraded
ML17223A6071990-04-0505 April 1990
Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Removal & Replacement of Cold Leg Side Plugs of Heat Number 3513 for Unit 1 Completed During Refueling Outage
ML17308A4911990-04-0202 April 1990
Forwards Description & Summary of Safety Evaluations of Plant Changes/Mods Reportable Per 10CFR50.59.Repair &/Or Replacement of Protective Coatings on Surfaces Inside Bldg Pose No Unreviewed Safety Question
ML17223A5931990-03-30030 March 1990
Forwards Status of 10CFR50.62, Requirements for Reduction of Risk from ATWS Mods at Plant as of 900315.Diverse Scram Sys Module Prototype Fabrication in Progress
ML17223A5921990-03-27027 March 1990
Forwards Addl Info on Proposed License Amend Re Increased Max Allowable Resistance Temp Detector Delay Time,Per 891219 Telcon & Advises That Util Request to Increase Plant Resistance Temp Detector Response Time Remain Unchanged
ML17223A5831990-03-19019 March 1990
Forwards Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implications of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f)
ML17347B6191990-03-13013 March 1990
Provides Listing of Property Insurance Programs
ML17223A5531990-03-0909 March 1990
Submits Results of Investigation of Error Detected in Dose Assessment During 900124 NRC Evaluated Exercise at Plant. Operator Error Caused Keyboard Hangup Requiring Computer Restart
ML17223A5451990-03-0808 March 1990
Forwards Revised Tech Specs Re Steam Generator Tube Repairs, Per 890602 Telcon & Subsequent Discussions W/Nrc
ML17308A4871990-03-0707 March 1990
Forwards Response to Eight Audit Questions & Licensing Bases Criteria to Resolve Station Blackout Issue.Util Currently Has Procedures to Mitigate Effects of Hurricanes & Tornados Which Meet or Exceed NUMARC 87-00 Guidelines
ML17347B5881990-03-0101 March 1990
Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits
ML17347B6031990-02-27027 February 1990
Requests Approval to Use Code Case N-468 at Plants
ML17223A5321990-02-26026 February 1990
Forwards CEN-396 (L)-NP, Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2.
ML20012A0011990-02-26026 February 1990
Notifies That Followup Actions Completed on Schedule & Incorporated Into Rev 25 to Plant Physical Security Plan,Per NRC 890605 Request
ML17223A5411990-02-26026 February 1990
Provides Addl Info Re Proposed License Amends Re Moderator Temp Coefficient Surveillance Requirements,Per 891026 & 900109 Telcons
IR 05000335/19890241990-02-22022 February 1990
Responds to Violations Noted in Insp Repts 50-335/89-24 & 50-389/89-24.Corrective Actions:Applicable Procedures Changed to Clarify Which Spaces & Blocks Required to Be Completed on Plant Work Order & QC Supervisor Counseled
1990-09-13
[Table view] |
Text
REGULAYINFORMATION DISTRIBUTIO YSTEM(RIDS)ACCESSION NBR:8804120332 DOC.DATE:88/04/ObNOTARIZED:
NOFACIL:50-335-St.
LuciePlantiUnitiiFloridaPower5LightCo.AUTH.NAMEAUTHORAFFIL1ATIONCONMAY>W.F.FloridaPower5LightCo.RECIP.NAMERECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET005000335
SUBJECT:
Forwardsaddiinfoonproposedlicenseamendreboricacidconcentration reductions perNRC880310request.DISTRIBUTION CODE:A001DCOPIESRECEIVED:
LTRiENCLISIZE:TITLE:ORSubmittal:
GeneralDistribution RECIPIENTIDCODE/NAME PD2-2LATOURIGNY>
EINTERNAL:
ACRSNRR/DEBT/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8EILRB1201EXTERNAL:
LPDRNSICCOPIESLTTRENCL101166111111111111RECIPIENT IDCODE/NAME PD2-2PDARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DOEA/TSB 11OQC15-B-18RES/DE/EIB NRCPDRCOPIESLTTRENCL5510111111101TOTALNUMBEROFCOPIESREQUIRED:
LTTR27ENCL24 JtI!)~0~~
OPPg3588Omb~PDRADOCH.0pjanFPLGroupcompany
~c~~
ST.LUCIEUNITIrcAcrocoNcErrrorrrrorr REovcrrOFPLRESPONSETONRCRE(VESTFORADDITIONAL INFORMATION I.Containment SumandSraHEvaluation Thefollowing abstractisprovidedtodelineate themethodology employedtoevaluatetheeffectthatreducedboricacidconcentrations wouldhaveontheContainment SumpandSpraypH:Aspartoftheboricacidconcentration reduction program,theexistingFloridaPower&LightContainment SumpandSpraypHcalculation wasrevisedtoreflectthenewoperating parameters fortheBoricAcidMakeup(BAN)Tanksasspecified byCombustion Engineering (Reference CELetterNo.F-CE-10325 datedOctober27,1987).Basedontheresultsoftherevisedcalculation, theoperating concentration rangeforSodiumHydroxide (NaOH)intheChemicalStorageTank(CHST)isamendedtoreflectlowerboricacidconcentrations asdelineated inproposedTechnical Specification 3.6.2.2.ToanalyzetheworstcasepHconditions, thecalculation involvedaniterative processwherebythemaximumandminimumboricacidconcentrations andwatervolumesforallavailable boratedwaterinventories wereconsidered.
Thecalculation wasseparated intotwoparts:1.Containment SumppHEvaluation; and2.Containment SpraypHEvaluation.
TheContainment SumppHEvaluation determined thehighandlowsumppHconsidering worstcasemixingofavailable boratedwaterinventories.
TheContainment SpraypHEvaluation determined thehighandlowcontainment spraynozzlepHduringbothinjection andrecirculation modes.TheContainment SpraypHEvaluation requiredtheanalysisofthefollowing conditions:
off-site, poweravailable, nofailures; off-sitepoweravailable, singlecontainment spraypumpavailable; andlossofoff-sitepower,singledieselgenerator available.
Whenthecalculation wasrevisedforthistask,allpartswerereworkedtodetermine potential impactontheoperating pHlimits.BasedontheresultsoftheContainment SpraypHEvaluation, thepHatthecontainment spraynozzleswasfoundtoexceedthemaximumallowedpHof11.0.Thiscondition wasfoundtoexistduringthebeginning ofrecirculation foreachofthethreecasesidentified above.Inordertomaintaincontainment spraypHwithintheallowable rangeof8.5-11.0,theCHSTNaOHconcentrations wereadjustedanditerations performed untiltankconcentrations wereconsistent withtherequiredpHvaluesatthespraynozzles.Theproposedmodification toTechnical Specification 3.6.2.2,ChemicalStorageTankNaOHconcentrations, (from30%-32%to28.5%-30.5%byweight)reflectthecalculation results.II.ReactorAuxiliarBuildinTemeratureMeasurement QUESTION:
Inregardstothesurveillance requiredwhentheReactorAuxiliary Buildingairtemperature isless-than55Fandconsidering thephysicalsizeofthemulti-level
- building, pleasediscussthelocation(s) wheretheairtemperature(s) willbetakenandtherelationship betweenthelocation(s) andthelocation(s) ofallcomponents oftheBAMUsystem.RESPONSE:
Asdelineated inFigure1,theaffectedheattracedpiping/components whichcomprisetheBoricAcidMakeupsystem(i.e.theboricacidmakeuptanks,boricacidmakeup p>pingandpipingtoth~uction ofthechargingpumps~relocatedinrelatively'loseproximity ontheminM0.5ft.elevation oftheReaCWIAuxiliary Building.
Theexception istheboricacidmakeuptanks,whichhavetanktopsatelevation 32.75ft.asshownonFigure2.Inaddition, theReactorAuxiliary BuildingVentilation Systemisdesignedtomaintainauniformtemperature throughout thebuilding(
Reference:
FinalSafetyAnalysisReportSection9.4.2.2.1).Basedupontheabove,theReactorAuxiliary Buildingairtemperature measurement willbetakenattheBoricAcidMakeupStationasshownonFigure1.III.BoricAcidMakeuTankConcentration QUESTION:
ProposedTechnical Specification 3.1.2.8.a.requiresaboricacidweightpercentrangeof3.2/to3.5/.ProposedT.S.3.1.2.8.b.requiresasimilarrange.PleaseexplainthesetwoproposedTechnical Specifications inrelationship to(1)theproposedbasesstatements pertheproposedPage63/41-2Insert,(2)proposedFigure3.1-1,(3)FPL'sboricacidconcentration reduction safetyevaluation, and(4)Combustion Engineering ReportCEN-353.RESPONSE:
Asdelineated inproposedTechnical Specification Figure3.1-1,proposedPageB3/41-2Insert,andtheCombustion Engineering ReportCEN-353,thereduction ofboricacidconcentration to2.5/oto3.5%%ubyweightrequiresboratedwatervolumesof13,300(2.5/owt.)to8350(3.5/.wt.)gallons.Theboricacidmakeuptanksarecapableofholding9450gallonseach(thehighlevelalarmissetat97.5/ofthe9700gallontankcapacity).
Inordertomaintaintherequiredboratedwaterinventory inoneboricacidmakeuptankandcomplywiththeproposedTechnical Specifications, theboricacidconcentration mustbenolowerthan3.2Xbyweight.Technical Specifications 3.1.2.8.a.and3.1.2.8.b.arewrittentodelineate theboricacidconcentration requirements (3.2/.to3.5/)whenonlyoneboricacidmakeuptankiscreditedwithbeinginservice.IV.BoricAcidConcentration Reduction Uncertainties QUESTION:
Page3oftheFloridaPower&Lightboricacidreduction safetyevaluation specifies theuncertainties considered.
Pleaseprovide:1)abriefdiscussion oftheuncertainties utilizedforscramworth,moderator temperature coefficient andOopplercoefficient; and2)anexplanation fortheomissionofboronmeasurement uncertainties fromtheanalysis.
RESPONSE
Acombinedbiasanduncertainty of10%wasappliedto'hescramworthdatasuppliedtoCombustion Engineering fromFloridaPower5Light.Thiscombinedbiasanduncertainty is,consistent withthelicensing methodology usedbyFloridaPower5Light'sUnit'fuelvendor(ANF)tocalculate shutdownmargin.Thescramworthisadditionally conservative becauseitisassumedtnattnemostworthycontrolelementassemblyisstuckoutofthecoreduringthescram.Aconservative correction wasappliedtothemoderator cooldowncurvesuppliedtoCombustion Engineering fromFloridaPower8Light.SinceCombustion Engineering did notgeneratethemodera~temperature coefficient
(~curve,aconservative correction wasappliedto~iscurvetomakeitconsiste~with themethodsusedbyCombustion Engineering whengenerating acooldowncurveforthemostnegativetechnical specification MTClimitof-0.00028deltarho/F.Theapplication ofabiasof15/oandanuncertainty of151totheDopplercoefficients isconsistent withthelicensing methodology usedforanalogplants.Thesefactorswereusedintheanalysis.
Aboronmeasurement uncertainty wasincludedintheLouisiana Power&Lightphysicsdatawhenthenaturalcirculation scenarioassumedthattheboronometer concentration wouldbeusedtoverifyreactorcoolantsystem(RCS)boronconcentration.
Averyconservative boronometer measurement uncertainty (50ppm)wasaddedtotheRCSboronrequirements.
Areviewofthecooldownscenarioshowsthattheadditionofaboronometer measurement uncertainty totheRCSboronrequirements isunnecessary.
ThecooldownscenarioinCEN353(F)identifies theminimumvolumeofboricacidmakeuptankwaterwillensurethattheRCSisadequately borated.Theboronometer readingswillnotbeusedduringthecooldownasacriteriatoreducetheamountofboricacidmakeuptankwaterdelivered totheRCSduringthiscooldown.
Inconclusion, boronometer measurement uncertainties neednotbeincludedintheborationrequirement curvesforeitherplant.V.FIGURE3.1-1QUESTION:
InregardtoproposedFigure3.1-1,pleaseexplainwhyitisnecessary tohaveatthebottomofthefiguretheexpression" 1720ppmintheRWT."RESPONSE:
WehavereviewedFigure3.1-1andhavedetermined thattheexpression "1720ppmintheRWT"atthebottomofthefigureis'otnecessary.
Therefore, weproposetoremovethisexpression (SeeattachedrevisedFigure3.1-1).rVI.BorationSstemBasesOuringatelephone callonMarch16,1988betweentheNuclearRegulatory Commission St.LucieProjectManagerandFloridaPower&Light,afollowupquestionwasdiscussed regarding boricacidadditionvolumesasdelineated inTechnical Specification BasesPagesB3/41-2andB3/41-3.Theboronadditioncapability forModes5and6,asdiscussed onBasesPageB3/41-3,includedconservatisms outlinedinCEN-353(F),
"BoricAcidConcentration Reduction Effort."However,theboronadditioncapability forModes1-4,discussed onBasesPageB3/41-2,donotincludetheconservatisms outlinedinCEN-353(F).
Inordertoprovideconsistency intheBasesdiscussion, weproposetorevisetheboronrangesforModes1-4toincludetheappropriate conservatisms.(See attachedrevisedinsertPageB3/41-2).
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'vavaRQO-reify FGURE4.1-1 ST.LUCEIMNCkAMTYOLUME6EfMB9ÃCtIMNWIN13sC12000vns$Cgois11os)Vl0X(13I300)UNCETAOPRATACC(>>,0)LEQN~BEtTIO(9(835)36"Q(4196PPN)(4546PPN)(4895PPN)(5245PPH)(5595PPM)(5944PPN)(6294PPM)SI0IBMIXC(ltIhakaN)ST.LUCIE-UNIT13/41-17AanendttM.nt No.M hcMO>carArnaofaon'CAf;co,o'tfn.)3o~sAc'J/YOJcc'PG~W~(l38Af~clg<gc(,Q,Pi<<g(I?ur).Tl'ZrnyC,'oEa.dolan//o>>$OF3soucg(fPOAcevfc5I(fggnfSodom~zn,g~~QADI~aJ/Yafoofolio~@oP/72~S...~~,lk.~i2~i+8,gaOoC4scucjjf.parcmk(vier/faunaCoro~)oor.cnc'48ABPsn.d9soaa(Alloc*4o7ll2MT.A,,ofgafooo~//~cogiu.O<~~Lou6iSrefIuirf.d gumtLfa!~7~gU~4.:4,7l.rQ.cS'/oc.
