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{{#Wiki_filter:4EGG-EA-6432OCTOBER1983CONFORMANCETONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeekIdahoNationalEngineeringLaboratoryOperatedbytheU.S.DepartmentofEnergyljfzj.ragaeahsAnmvI'!',Iv!~'rdV-addaaaaada~ov~'-'""h"=oaves';.,g-"-.L..rr'~ottv'.W.Ca4~~4hThisisaninformalreportintendedforuseasapreliminaryorworkingdocument0402130407840($0~;.PDR,ADOCK05000335,',',,',P''PDR'reparedrortheU,S,NUCLEARREGULATORYCOMMISSIONUnderDOEContractNo.DE-AC07-76ID01570FINNo.A6600~~E&Z&IdahoI1  
{{#Wiki_filter:4EGG-EA-6432 OCTOBER1983CONFORMANCE TONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeek IdahoNationalEngineering Laboratory OperatedbytheU.S.Department ofEnergyljfzj.ragaeahsAnmvI'!',Iv!~'rdV-addaaaaada~ov~'-'""h"=oaves';.,g-"-.L..rr'~ottv'.W
'tv'!r EGG-EA-6432CONFORMANCETONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeekPublishedOctober1983EGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatoryCommissionAtlanta,Georgia30303UnderDOEContractNo.DE-AC07-76ID01570FINNo.A6600 ABSTRACTThisEGKGIdaho,Inc.,reportevaluatesthesubmittalprovidedbyFloridaPowerandLightCompany(FPL)forSt.LuciePlantUnitNos.1and2.ThesubmittalisinresponsetoGenericLetterNo.82-16,"NUREG-0737TechnicalSpecifications.(TS)".Applicablesectionsoftheplants'Sareevaluatedtodeterminecompliancetotheguidelinesestablishedinthegenericletter.FOREWORDThisreportissuppliedaspartofhe"TechnicalAssistanceforOperatingReactorsLicensingActions"beingconductedfortheU.S.NuclearRegulatoryCommissionRegionIIbyEG5GIdaho,Inc.,NRCLicensingSupportSection.TheU.S.NuclearRegulatoryCommissionFundedtheworkunderauthorizationBAR92-19-20-10,FINNo.A6600;DocketNos.50-335and50-389TACNos.49760andR2X162 CONTENTSABSTRACT...............FOREWORD,.INTRODUCTION2.'.REVIEWREQUIREMENTS~~~~~0~~~~2.1STATraining(I.A.1.1.3)t2.2ShiftManning-OvertimeLimits(I.A.1.3.1)2.3ShortTermAuxiliaryFeedwaterSystem(ARlS)Evaluation(II.E.1.1)2.42.5SafetyGradeAFWInitiationandFlowIndication(II.E.1.2)DedicatedHydrogenPenetr'ations(II.E.4.))~~~~~32.6ContainmentPressureSetpoint(II.E.4.2.5)2.7ContainmentPurgeValves(II.E.4.2.6)2.8RadiationSignalonPurgeValves(II.E.4.2.7)...........'...42.9UpgradeBabcockandWil'cox(B&W)AFWS(II.K.2.8)2.10B&WSafety-GradeAnticipatoryReactorTrip(II.K.2.10)2.11B&WThermal-MechanicalReport(II.K.2.13)2.12ReportingSafetyandReliefValveFailuresandChallenges(II.K.3.3)2.13AnticipatoryTriponTurbineTrip(II.K.3~12)3.EVALUATION3.1STATraining(I.A.1.1.3)3.2ShiftManning-OvertimeLimits(I.A.1.3.1)3.3ShortTermAuxiliaryFeedwaterSystem(AFWS)Evaluation(II.E.1.1)3.4SafetyGradeAuxiliaryFeedwater(AFW)InitiationandFlowIndication(II.E.1.2)3.5DedicatedHydrogenPenetrations(II.E.4.1)55 3.6ContainmentPressureSetpoint(II.E.4.2.5)3.7ContainmentPurgeValves(II.E.4.2.6)3.8RadiationSignalonPurgeValves(II.E.4.2.7)3.9"UpgradeBabcockandWilcox(B&W)AFWS(II.K.2.8)3~10B&WSafety-GradeAnticipatoryReactorTrip(II.K.2.10)3.11B&WThermal-MechanicalReport(II.K.2.13)10103~12ReportingSafetyandReliefValveFailuresandChallenges(II.K.3.3)123.13AnticipatoryTriponTurbineTrip(II.K.3.12)..............124.CONCLUSIONS5.REFERENCES1314 CONFORMANCETONRRGENERICLETTER82"16ST.LUCIEPLANTUNITNOS1AND21.INTRODUCTIONOnSeptember20,1982,GenericLetter82-16wasissuedby1D.G.Eisenhut,DirectorofLicensing,OfficeofNuclearReactorRegula'tion(NRR),toallpressurizedpowerreactorlicensees.Thisletteridentified'numberofitemsrequiredbyNUREG-0737tobeimplementedinthe2licensee'sTechnicalSpecifications(TS)byDecember31,1981.Eachlicenseewasrequestedtoreviewtheirfacility'sTS,toaddressareasofcompliance.,andtoidentifydeviationsorabsenceofaspecificationfortheitemsidentifiedin.thegenericletterwithin90daysofreceiptoftheletter.TheFloridaPowerandLightCompany..(FPL),thelicenseeforSt.LuciePlantUnitNos.1and2,providedaresponsetothegenericletteronDecember22,1982,forSt.LuciePlant.UnitNo.1.TheNUREG-0737items3forSt.'LuciePlantUnitNo.2werecoveredinAmendment5totheFinalSafetyAnalysisReport(FSAR)forSt.LuciePlantUnitNo.2.Thisinterimreportprovidesanevaluationofthelicensee'sTSandNuclearRegulatoryCommission(NRC)correspondencewiththelicenseepertainingtothoseitemsidentifiedinthegenericletter.
.Ca4~~4hThisisaninformalreportintendedforuseasapreliminary orworkingdocument0402130407 840($0~;.PDR,ADOCK05000335,',',,',
2.REVIEWREQUIREMENTSThereviewconsistsofevaluating<helicensee'sresponse,currentlyapprovedTS,andotherNRRapprovalsagains.thecriteriasetforthinGenericLetter82-16.TheNUREG-0737itemsandthecriteriaestablishedareasfollows:2.1STATraininI.A.1.1.3ThelicenseeistoaddresswithintheirTSthatashift,technicaladvisor(STA)totheshiftsupervisorisp0ovided.Inaddition,thequalifications,training,.andon-dutyrequirementsfortheSTAshouldbestated.2.2Sh-iftMannin-Ov'ertimeLimi'tsI.A.1.3.1Thelicenseeistoprovidechanaesto.heirTSprovidingovertimeadministrativeprocedureandstaffingrequirements.Thefollowing'guidelineswereestablishedforthelicenseebytheNRC."a~Anindividualshouldnotbepermittedtoworkmorethan16hoursstraight(excludingshiftturnovertime).b.Anindividualshouldnotbepermittedtoworkmorethan16hoursinany24-hourperiod,normorethan24hoursinany48-hourperiod,normorethan72hoursinanysevendayperiod(allexcludingshiftturnovertime).c.Abreakofatleasteighthoursshouldbeallowedbetweenworkperiods(includingshiftturnovertime).d.Exceptduringextendedshutdownperiods,theuseofovertimeshouldbeconsideredonanindividualbasisandno.fortheentiresaffonashift.Recognizingthatveryunusualcircumstancesmayariserequi~ingdeviationfromtheaboveguidelines,suchdeviationshallbeauthorizedbytheplantmanagerorhisdeputy,orhigherlevelsofmanaoement.Theparamountconsiderationinsuchauthorizationshallbethatsignificantreductionsintheeffectivenessofoperatingpersonnelwouldbehighlyun1ike1y.
P''PDR'reparedrortheU,S,NUCLEARREGULATORY COMMISSION UnderDOEContractNo.DE-AC07-76ID01570 FINNo.A6600~~E&Z&IdahoI1  
Inaddition,proceduresareencouraoedthatwouldallowlicensed'operatorsatthecontrolstobeperiodicallyrelievedandassignedtoothe'rdutiesawayfromthecontrolboardduringtheirtourofduty."52.3ShortTermAuxiliarFeedwaterSstemAFWSEvaluationII.E.1.1Theobjectiveofthisitemistoimprovethereliabilityandperformanceoftheauxiliaryfeedwater(AFW)system.TSdependontheresultsofthelicensee'sevaluationandthestaffreview,andarebeingdevelopedseparatelyforeachplant.Thelimitingconditionsofoperation(LCO's)andsurveillancerequirementsfortheAFWsystemshouldbesimilar1toothersafety-relatedsystems.2.4SafetGradeAFWInitiationandFlowIndicationII.E.1.2TheAFWsystemautomaticinitiationsystemwastohavebeencontrolgrade'byJune1,1980,andsafetygradebyJuly1,1981;theAFWsystemflowindicationwastohavebeencontrolgradebyJanuary1,1980,andsafetygradebyJuly1,1981.2.5DedicatedHdroaenPenetrationsII.E.4.1Plantsthatuseexterna1'recombikersorpurgesys.emsforfpost-accidentcombustiblegascontrolofthecontainmentatmosphereshouldprovidecontainment'penetrationsdedicatedtothatservice.Insatisfyinghisitem,someplantsmayhavetoaddsomeadditionalpipingandvalves.Ifso,theseval.vesshouldbesubjectedtotherequirementsofAppendixJof10CFR50,andtheTSshouldbemodifi'edaccordingly.2.6ContainmentPressureSetoointII.E.4.2.5Thecontainmentpressuresetpointthat.initiatescontainmentisolationmustbereducedto'theminimumcompatiblewithnormaloperatingconditions.Hostplantsprovidedj.ustificationfornotchangingtheirsetpointandtheNRChasapprovedtheirjustificationbyseparatecorrespondence.The.remainingplantsmustsubmitachangetotheTSwith the.lowercontainmentpressuresetpointandprovidejustificationifthissetpointismorethan1psiabovemaximumexpectedcontainmentpressureduringnormaloperation.12.7ContainmentPuraeValvesII.E.4.2.6ModelTSweresentseparatelytoeachplantaspartoftheoverallcontainmentpurgereview.TheseTSincludetherequirementthatthecontainmentpurgevalvesbelockedclosedexceptforsafetyrelatedac.ivities,verifiedclosedatleastevery31days,and.besubjectedtole'akageratelimits.2.8RadiationSianalonPuroeValvesII.E.4.2.7Thecontainmentpurgevalvesmustclosepromptlytoreducetheamountofradiationreleasedoutsidecontainmentfollowingareleaseofradioactivematerialstocontainment.TSshouldincludetherequirementthataleastoneradiationmonitorthatautomaticallyclosesthepurgevalvesuponsensinghighradiationinthecontainmentatmospherebeoperableatalltimesexceptcoldshutdownsandrefuelingoutaoes.Ifnot0operable,ei.hertheplantshouldbeginproceeding'ocoldshutdownwithin24hoursorthepurgevalvesshouldbeclosedwithin24hours.ModelTSwereprovidedinStandardTechnicalSpecificationsformatforthoseplantsthatareusingsafety-gradecomponentstosatisfytherequirement.12.9UradeBabcockandWi1coxB8WAFWSII.K.2.8Additionallong-termAFWSmodificationsweretobeperformedinconjuctionwithGenericLetter82-l6Items3and4(Items2.3and2.4above).TheTSimplementedforItems3and4wi1.1alsoaddresstheupgradeof'theBEWAFWS;thereforenoseparateTSwouldberequiredforthisitemfortheBKWPlants.
'tv'!r EGG-EA-6432 CONFORMANCE TONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeek Published October1983EGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatory Commission Atlanta,Georgia30303UnderDOEContractNo.DE-AC07-76ID01570 FINNo.A6600 ABSTRACTThisEGKGIdaho,Inc.,reportevaluates thesubmittal providedbyFloridaPowerandLightCompany(FPL)forSt.LuciePlantUnitNos.1and2.Thesubmittal isinresponsetoGenericLetterNo.82-16,"NUREG-0737 Technical Specifications
2.10BEWSafet-GradeAnicioa.orReactorTriII.K.2.10Safety-gradeturbinetripequipmentinitiatingareactortripwastobeimplementedbytheBEWdesignedplantsaspartoftheTMIlessonslearned.ThelicenseeistoimplementintheTSthetripsetpoint,numberofchannels,tripconditions,minimalchannelsrequiredforoperation,applicableoperatingmodes,actionstobetaken,surveillancerequiredandanyotherrequirementsforsafety-gradeequipment.2.11BEWThermal-MechanicalReportII.~.13LicenseesofMWoperatingreactorswererequiredtosubmit,byJanuary1,1981,ananalysisofthethermal-,mechanicalconditionsinthereactorvesselduringrecoveryfromsmallbreakswithanextendedlossofallfeedwater.TS,ifrequired,willbedeterminedfollowingNRCstaffreview.12.12ReoortinSafestandRelief.ValveFailuresand.ChallenoesII.K.3.3NUREG-0660statedthatsafetyandrelief.valvefailuresbereportedpromptlyandchallengesbereportedannually.ThesectionsoftheTSthatdiscussreportingrequirementsshouldbeaccordinglychanged.TheNRChasnotedthatanacceptablealternativewouldbetoreportchallengesmonthly.12.13AnticioatorTrioonTurbineTriII.K.3.12LicenseeswithWestinghouse-designedoperatingplantshaveconfirmedthattheirplantshaveananticipatoryreactortripuponturbinetrip.ManyoftheseplantsalreadyhavethistripintheTS.Forthosethatdonot,theanticipatorytripshouldbeaddedtotheTS.1FortheSt.LuciePlantUnit1and2,theaboveItems2.9,2.10,and2.11arenotbeingevaluated.BeingaCombustionEngineeringdesign, Items2.9and2.10arenotapplicableforSt.LuciePlantUnit1and2.ForItem2.11,FPL'sThermal-MechanicalReportisbeinohandledasanactiveThreeNileIsland(TMI)actioni.emunderTAGnumber46905forSt.LuciePlantUnit1.
.(TS)".Applicable sectionsoftheplants'Sareevaluated todetermine compliance totheguidelines established inthegenericletter.FOREWORDThisreportissuppliedaspartofhe"Technical Assistance forOperating ReactorsLicensing Actions"beingconducted fortheU.S.NuclearRegulatory Commission RegionIIbyEG5GIdaho,Inc.,NRCLicensing SupportSection.TheU.S.NuclearRegulatory Commission Fundedtheworkunderauthorization BAR92-19-20-10, FINNo.A6600;DocketNos.50-335and50-389TACNos.49760andR2X162 CONTENTSABSTRACT...............
3.EVALUATIONTheevaluationsofGenericLetter82-16Itemsareasfollows:3.1STATraininI.A.1.1.3ThelicenseehasstatedinhisresponseforSt~LucieUnit1thatthisitemwasaddressedbyTSAmendmentNo.37.InTable6.2-1ofbothSt.LuciePlantUnit1and2TS,'heSTAisdesignatedasbeingrequired6,7intheminimalshiftcrewcompositionforoperationalmodes1,2,3,or4.Section6.3.1specifies"heShiftTechnicalAdvisorwhoshallhaveabachelor'sdegreeorequivalentinascientificorengineeringdisciplinewithspecifictraininginplantdesignandintheresponseandanalysisoftheplantfortransientsandaccidents."Theretrainingandreplacement)i6trainingprogramforthefacilitystaffisstatedinSection6.4.1oftheTS.TheexacttrainingprogramfortheSTAisnotintheTS.InAmendment5totheSt.LuciePlantUnit2FSARAppendix1.9A,the4NUREG-0737'itemsareaddressed.TnelicenseestatesthatChapter13oftheFSARhasbeenrevisedtoaddresstherequiremenofNUREG-0737ItemI.A.l.l.Subsection13.1.2.2specifiestheresponsibility,authority,phaseoWplans,andreportingrelationships;subsection13.1.3.1and13.2.1.1.2specifythetrainingrequirements.InaletterfromtheNRCtothelicensee,datedJanuary26,1982,8theNRCstatedthatItemI.A.1.1.3ofNUREG-0737isresolved.UntilfurherguidanceisissuedbytheCommission,nofurtherlicensingactionisrequiredforthisitem.3.2ShiftHannin-Over.imeLimitsI.A.1.3.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheovertimelimitationsareadequatelyenforcedbyadministrativeproceduresandthatnoamendmenttotheTSisnecessaryatthistime.This policywasacceptedbytheNRCintheletterfromR.A.ClarktoR.E.Uhrig,datedFebruary4,1982.TheTSforSt.LucieUnit1donotcontainanyshiftmanningovertimelimitationrequirements.Section6.2.2oftheSt.LucieUnit2TScontainstheovertimelimi'.sasspecifiedinGenericLetter82-12andisthereforeincompletecompliancewithNUREQ-0737ItemI.A.1.3.1.OnJune30,1983,anotegramfromD.C.Fischer,LeadProjecManager10forthemaintopicI.A~1.3wassenttotheoperatingreactorprojectmanagerforSt.LuciePlantUnit1requestingthattheTACnumberbeclosedou.forItemI.A.1.3.1onSt.LuciePlantUnit1.Nofurtherlicensingactionisrequiredforthisitem.3.3ShortTermAuxiliarFeedwaterSstemAFWSEvaluationII.E.1.1ThelicenseehasstatedinhisresponsethattheexistingSt.LuciePlantUnit1AFWSTSlimitingconditionsofoperationandsurveillance,requirementsaresimilarto.thatofothersafetyrelatedsystems.Section3.7,1.2and4.7.1.2oftheSt.LuciePlantUnits1and2TSprovidetheconditionforoperationandthesurveillancerequirements.Inenclosure2oftheFPLlettertotheNRC,datedJanuary2,111981,thelicenseeaddressesNUREG-0737ItemII.E.1.1forSt.LuciePlantUnit,1.-TheenclosureisareportwhichprovidesthedescriptionofAFWSmodificationstobeimplementedbyJanuary1,1982andthesafetyevaluaionofthesystem.Amendment5totheSt.LuciePlantUnit2FSARAppendix1.9AaddressesNUREG-0737ItemII.E.1.1.AreliabilityanalysiswasperformedtodeterminedominantfailuremodesandassessAFWSreliabilitylevels.TheresultsofthereliabilityevaluationareprovidedinAppendix10.4.9BoftheFSAR.AsafetyreviewwasalsoprovidedusingtheguidanceinStandardReview.Plan10.4.9.TheresultsareprovidedinAppendix10.4.9.AoftheFSAR.
: FOREWORD,
ReviewoftheTSforSt.LuciePlantUnits1and2indicatedthatthelimitingconditionsofoperationandsurveillancerequirementsaresimilartothoseothersafety-relatedsystemsidentifiedintheTS.Nofurtherlicensingactionisrequiredforthisitem.3.4SafetGradeAFWInitiationandFlowIndicationII.E.1.2ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatTSAmendmentNo.37,whi.chwasapprovedbytheNRCJanuary19,1981,containsalltheinformationpertainingtothesafetygradeAFWSysteminitiationandflowindication.Inenclosure2oftheFPLlettertotheNRC,datedJanuary2,1981,thelicenseeaddressesNUREG-0737ItemICE.1.2forSt.LuciePlantUnit1.ThisitemiscoveredforS.LuciePlantUnit2inAmendment5totheFSARinAppendix1.9A.ReviewoftheTSforSt.LuciePlantUnits1and2indicatesthattheAFWinitiationandflowindicationaresafetygrade.Nofurtherlicensingactionisrequiredforthisitem.3.5DedicatedHdrooenPenetrationsII.E.4.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheirhydrogenrecombinersareinternalbutthatahydrogenpurgesystemwasinstalledandtheSt.LuciePlantUnit1TSsubjectsthehydrogenpurgevalvestothecriteriaspecifiedinAppendixJof10CFR50.InAmendment5toSt.LuciePlantUnit2FSAR,thelicenseehasstatedthatredundantinternalhydrogenrecombinersareprovided.Therefore,NUREG-0737ItemI.E.4.1isnotapplicabletoSt.LuciePlantUnit2.AdiscussionoftheinternalhydrogenrecombinersisprovidedinSubsecion6.2.5oftheFSAR.ReviewoftheSt.LuciePlantUnit1TSindicatesthatthevalvesaresubjecttotherequirementsofAppendixJof10CFR50andsinceSt.LuciePlanUnit2utilizesinternalhydrogenrecombinersandapparentlyhasnot addedadditionalpipingandvalves,itisconcludedthatheNUREG-0737itemrequirementsaremet.Nofurtherlicensingactionisrequiredforthisitern.3.6ContainmentPressureSetoointII.E.4.2.5ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatanalysiswasprovidedtotheNRCjustifyingthepresentsetpointforcontainmentpressure.TheNRCacceptedthepresentsetpointiniheleterR.A:ClarkcoR.E.Uhrig,datedJanuary20,1982.12ReviewofTable2.2-1oftheTSforSt.LuciePlantUnit2indicatesthesetpointlimitsareinaccordance-'otherecommendedguidelinesofGenericLetter82-16.Nofur.herlicensingac.ionisrequiredforthisitem.3.7ContainmentPuroeValveII.E.4.2.6Thelicenseehas.statedinhisresponseforSt.LuciePlantUnit1t'hataresponsewasprovidedtotheNRCinFPLletterL-82-317,datedJuly30,1982.However,itisnotindicatedthatanNRCacceptancewasgiven.ReviewoftheTSforSt.LuciePlantUnit1indicaesthat~compliancetoGenericLetter82-16hasnotbeenmet..TheSt.LuciePlantUnit2TSSection3/4.6providestheinformationonthecontainmentpurgevalvelimitingconditionforoperation,surveillancerequirements,andthetestingtobeperformedonthevalves.TheTSSection3.6.1.7specifieshatthepurgevalvesbesealedclosedandverifiedatleastonceper31daysexceptforsafetyrelatedactivities.TheTSleaktestingistypeCwhichisperformedwithgasatintervalsnogreaterthan24mon.hs.St.Lucie'lantUnit2TSmeetstherecommendedguidanceofGenericLeter82"16.NofurtherlicensingactionisneededforUnit2.10  
.INTRODUCTION 2.'.REVIEWREQUIREMENTS
~~3.8RadiationSinalonPureValvesII.E.4.2.7ThelicenseehassatedinhisresponseforSt.LuciePlantUnit1thattheexistingTSrequiresthatwithin24hours,theplantbeginsproceedingtocoldshutdownshouldallcontainmentradiationmonitorsfail.Alsothecontainmentisolationisinitiatedbyhighradiation(andothersignals)closingthepurgevalves.ReviewoftheTSforSt.LuciePlantUnits1and2indicatethattherequirementsofNUREG-0737ItemII.E.4.2.7havebeenmet.Nofurtherlicensingactionisrequiredforthisitem.3.9UpgradeBabcockandWilcox.B8WAFWSII.K.2.8St.LuciePlantUnits1and2areaCombustionEngineeringdesignand,therefore,therequiremeRtsofthisitemarenotapplicable.Nolicensingactionisrequired.3.10B&WSafet-GradeAnticiatorReactorTriII.K,2.10~'t.LuciePlantUnits1and2areaCombustionEngineeringdesignand,therefore,therequiremen'tsofthisitemarenotapplicable.TheanticipatorytripisevaluatedunderNUREG-0737ItemII.K.3.3forthe'Westinghousedesign.Nolicensingactionisrequired.3.11BKWThermal-MechanicalReortII.K.2.13St.LuciePlantUnits1and2areaCombustionEngineeringdesignand,therefore',therequirementsofthisitemarenotapplicable.IthasbeennotedthatthereisanactiveTMIactionitemThermal-MechanicalReportforSt.LuciePlantUnit1underTACNumber46905.NolicensingactionisrequiredbyGenericLetter82-16forthisitem.11 3.12ReoortinoSafetandReliefValveFailuresandChallenaesII.K.3.3ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatacommitment.oreportsafetyandreliefvalvechallengesonanannualIbasiswasgivenintheirletterL-80-184,datedJuly13,'1980.ThelicenseealsocommittedtomakebothTScompatibletotherequirementsofGene.icLetter82-16followingfinalizationoftheSt.LuciePlantUnit2TS.ReviewoftheSt.LuciePlantUnit1TSindicatesthatSec.ion6.9.1.6hasnotbeenamendedyettoincludethereportingonamonthlybasisforall'challengestothevalves.St.LuciePlantUnit2TSSection6.9.1.6is'ncompliancewiththerequirementsoGenericLetter82-16.NofurtherlicensingactionisrequiredforS.LuciePlantUnit2.3.13AnticioatorTrioonTurbineTripII.K.3.12ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatalthoughnotaWestinghousedesign,theTSadequatelycovertheanticipatorytriponturbinetrip.ReviewoftheTSTables2.2-1,3.3-1and3.3-2indicatethattherequirementssetforthinGenericLetter82-16havebeenmet.Nofurtherlicensingactionisrequired.12 4.CONCLUSIONSBasedonourreview,wefindthelicenseeconformstothoseissuesaddressedinGenericLetter82-16onTS,exceptforthoseidentifiedasfollows:1.,Section3.1STATraining-UntilfurtherguidanceisprovidedbytheCommission,nofurtherlicensingactioncanbetakentodeterminewhethertheexacttrainingprogramfortheSTAisrequiredtobeintheTS.2.Section3.2Shif-Manning-OvertimeLimits-St.LuciePlantUnit1TSdonotcontainshift-manningovertimelimits,however,FPL'sovertimelimitspolicywasacceptedbytheNRC.3.Section3.7ContainmentPurgeValve-St.LuciePlantUnit1TSdanotcomplywiththe,requirementsofGenericLetter82-16.4.Section3.11Thermal-MechanicalReport-TheThermal-Mechanical,ReportforSt.LuciePlantUnitNo.1isbeinghandledasanactiveTMIactionitemunderTACnumber46905:Thereisnoidentified'TMIactionitemfortheSt.LuciePlantUnitNo.2Thermal-MechanicalReport.GenericLetter82-16doesnotrequireanylicensingactionforthisitem.5.Section3,.12ReportingSafetyandReliefValveFailuresandChallenges-ThepresentSt.LuciePlantUnit1TSdonotcomplywiththerequirementsofGenericLetter82-16.However,FPLispresentlyupdatingtheSt.LucieUnit1TStoconformwiththeSt.LucieUnit2TS.Whenthisi5completedandapprovedbytheNRC,theSt.LucieUnit1TSshouldbeincompliancewithiherequirementsofGenericLetter82-16.13 5.REFERENCESD.G.Eisenhut,NRClettertoAllPressurizedPowerReactorLicensees,"NUREG-0737TechnicalSpecifications(GenericLetter82-16),"September20,1982.NUREG-0737,ClarificationofTMIActionPlanRequirements,publishedbytheDivisionofLicensing,OfficeofNuclearReactorRegulation,U.S.NuclearRegulatoryCommission,November1980.R.E.Uhrig,FloridaPowerandLightlettertoD.G.Eisenhut;OfficeofNuclearReactorRegulation,"St.LucieUnit1,DocketNo.50-335,NUREG-0737TechnicalSpecifications,"December22,1982.R.E.Uhrig,FloridaPowerandLightCompanylettertoD.G.Eisenhut;OfficeofNuclearReactorRegulation,"St.LucieUnit2,DocketNo.50-389Amendment5totheFinalSafetyAnalysisReport,"L-81-351,August12',1981.D.G.Eisenhut,NRClettertoAllLicenseesofOperatingPlans,ApplicansforanOperatingLicense,andHoldersofConstructionPermits,"NuclearPowerPlantStaffWorkingHours(GenericLetterNo.82-12),"June15,1982.St.LuciePlantUnit1TechnicalSpecifications,AppendixAtoLicenseNo.DPR-67,March1,1976,AmendmentNo.58.TechnicalSpecifications,St.LuciePlantUnit2,DocketNo.50-389,AppendixAtoLicenseNo.NPF-16,April1983.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLighgCompany,"NUREG-0737ItemI.A.1.1ShiftTechnicalAdvisor(STA),"January26,1982.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"TMIActionPlantItemsI.A.1.3,I.C.5,andI.C.6asDescribedinNUREG-0737,"February4,1982..D.C.Fischer,LeadProjectManagerforI.A.1.3,notegramtoalloperatingreactorprojectmanaoers,"TACCloseout"June30,1983'.R.E.Uhrio,FlordiaPowerandLiohtCompanylet.ertoD.G.Eisenhut;OfficeofNuclearReactorRegulation,"St.LucieUnit1,DocketNo.50-335.PostTMIRequirements."L-81-4,January2,1981.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"NUREG-0737ItemII.E.4.2(5)forSt.LucieUnit1,"January20,1982.14 U.S.NUCLEARREGULATORYCOMMISSIONBIBLIOGRAPHICDATASHEET4.TITLEiANOSUBTITLECONFORMANCETONRRGENERICLETTER82-16.ST.LUCIEPLANTUNITNOS1AND21.REPORTNUMBER(Asssgned*yDOC/,EGG-EA-64322./Leeeedlenk/3.RECIPIENT'SACCESSIONNO.7.AUTHORIS)R.VanderBeek9.PERFORMINGORGANIZATIONNAMEANOMAILINGAOORESS/IncludeZipCode/EG8GIdaho,Inc.IdahoFalls,ID8341512.SPONSORINQORGANIZATIONNAMEANOMAILINQAOORESS/IncludeZipCods'IDivisionofPro'ectndidntP1U.S.Nuc',earReguatoryCommission101MariettaStreetSuite29005.OATEREPORTCOMPLETEOMONTHYEARDATEREPORTISSUEOMONTHOctober6./LeeeeolenklYEAR1983B./Leeeeolenkl11FINNo.10,PROJECT/TASK/WORKUNITNO,13TYPEOFREPORTuERIOOCOYERED/Inclusivedeses/15.SUPPLEMENTARYNOTES14/Leereormki16,ABSTRACTI200wordsorress/ThisEG8GIdaho,Inc.,reportevaluateswhetherthedesignatedOperatingReactorPlanthasconformedtotherequirementsoftheNRRGenericLetterNo.82-16,"NUREG-0737TechnicalSpecifications."17,KEYWOROS*NOOOCUMENTANALYSIS17s.OESCRIPTORSIjb,IOENTIFIERSI'OPENENOEOTFRMSIB.AVAILABILITYSTATEMENTUnlimitedNACFORM335sslSll'19.SECURITYCLASSIrnisreooislUnclassified20.SECURITYCLASS/TliSpete/Unclas'fi21O'OOFPAGES22PRICE5 hil'4ItI}}
~~~~~0~~~~2.1STATraining(I.A.1.1.3) t2.2ShiftManning-Overtime Limits(I.A.1.3.1)2.3ShortTermAuxiliary Feedwater System(ARlS)Evaluation (II.E.1.1)2.42.5SafetyGradeAFWInitiation andFlowIndication (II.E.1.2)Dedicated HydrogenPenetr'ations (II.E.4.))
~~~~~32.6Containment PressureSetpoint(II.E.4.2.5) 2.7Containment PurgeValves(II.E.4.2.6) 2.8Radiation SignalonPurgeValves(II.E.4.2.7)
...........'...
42.9UpgradeBabcockandWil'cox(B&W)AFWS(II.K.2.8) 2.10B&WSafety-Grade Anticipatory ReactorTrip(II.K.2.10)2.11B&WThermal-Mechanical Report(II.K.2.13)2.12Reporting SafetyandReliefValveFailuresandChallenges (II.K.3.3) 2.13Anticipatory TriponTurbineTrip(II.K.3~12)3.EVALUATION 3.1STATraining(I.A.1.1.3) 3.2ShiftManning-Overtime Limits(I.A.1.3.1) 3.3ShortTermAuxiliary Feedwater System(AFWS)Evaluation (II.E.1.1)3.4SafetyGradeAuxiliary Feedwater (AFW)Initiation andFlowIndication (II.E.1.2) 3.5Dedicated HydrogenPenetrations (II.E.4.1)55 3.6Containment PressureSetpoint(II.E.4.2.5) 3.7Containment PurgeValves(II.E.4.2.6) 3.8Radiation SignalonPurgeValves(II.E.4.2.7) 3.9"UpgradeBabcockandWilcox(B&W)AFWS(II.K.2.8) 3~10B&WSafety-Grade Anticipatory ReactorTrip(II.K.2.10) 3.11B&WThermal-Mechanical Report(II.K.2.13) 10103~12Reporting SafetyandReliefValveFailuresandChallenges (II.K.3.3)123.13Anticipatory TriponTurbineTrip(II.K.3.12)
..............
124.CONCLUSIONS 5.REFERENCES 1314 CONFORMANCE TONRRGENERICLETTER82"16ST.LUCIEPLANTUNITNOS1AND21.INTRODUCTION OnSeptember 20,1982,GenericLetter82-16wasissuedby1D.G.Eisenhut, DirectorofLicensing, OfficeofNuclearReactorRegula'tion (NRR),toallpressurized powerreactorlicensees.
Thisletteridentified' numberofitemsrequiredbyNUREG-0737 tobeimplemented inthe2licensee's Technical Specifications (TS)byDecember31,1981.Eachlicenseewasrequested toreviewtheirfacility's TS,toaddressareasofcompliance.,
andtoidentifydeviations orabsenceofaspecification fortheitemsidentified in.thegenericletterwithin90daysofreceiptoftheletter.TheFloridaPowerandLightCompany..(FPL),
thelicenseeforSt.LuciePlantUnitNos.1and2,providedaresponsetothegenericletteronDecember22,1982,forSt.LuciePlant.UnitNo.1.TheNUREG-0737 items3forSt.'LuciePlantUnitNo.2werecoveredinAmendment 5totheFinalSafetyAnalysisReport(FSAR)forSt.LuciePlantUnitNo.2.Thisinterimreportprovidesanevaluation ofthelicensee's TSandNuclearRegulatory Commission(NRC)correspondence withthelicenseepertaining tothoseitemsidentified inthegenericletter.
2.REVIEWREQUIREMENTS Thereviewconsistsofevaluating
<helicensee's
: response, currently approvedTS,andotherNRRapprovals agains.thecriteriasetforthinGenericLetter82-16.TheNUREG-0737 itemsandthecriteriaestablished areasfollows:2.1STATraininI.A.1.1.3 ThelicenseeistoaddresswithintheirTSthatashift,technical advisor(STA)totheshiftsupervisor isp0ovided.
Inaddition, thequalifications,
: training,
.andon-dutyrequirements fortheSTAshouldbestated.2.2Sh-iftMannin-Ov'ertime Limi'tsI.A.1.3.1Thelicenseeistoprovidechanaesto.heirTSproviding overtimeadministrative procedure andstaffingrequirements.
Thefollowing
'guidelines wereestablished forthelicenseebytheNRC."a~Anindividual shouldnotbepermitted toworkmorethan16hoursstraight(excluding shiftturnovertime).b.Anindividual shouldnotbepermitted toworkmorethan16hoursinany24-hourperiod,normorethan24hoursinany48-hourperiod,normorethan72hoursinanysevendayperiod(allexcluding shiftturnovertime).c.Abreakofatleasteighthoursshouldbeallowedbetweenworkperiods(including shiftturnovertime).d.Exceptduringextendedshutdownperiods,theuseofovertimeshouldbeconsidered onanindividual basisandno.fortheentiresaffonashift.Recognizing thatveryunusualcircumstances mayariserequi~ing deviation fromtheaboveguidelines, suchdeviation shallbeauthorized bytheplantmanagerorhisdeputy,orhigherlevelsofmanaoement.
Theparamount consideration insuchauthorization shallbethatsignificant reductions intheeffectiveness ofoperating personnel wouldbehighlyun1ike1y.
Inaddition, procedures areencouraoed thatwouldallowlicensed'operators atthecontrolstobeperiodically relievedandassignedtoothe'rdutiesawayfromthecontrolboardduringtheirtourofduty."52.3ShortTermAuxiliarFeedwater SstemAFWSEvaluation II.E.1.1Theobjective ofthisitemistoimprovethereliability andperformance oftheauxiliary feedwater (AFW)system.TSdependontheresultsofthelicensee's evaluation andthestaffreview,andarebeingdeveloped separately foreachplant.Thelimitingconditions ofoperation (LCO's)andsurveillance requirements fortheAFWsystemshouldbesimilar1toothersafety-related systems.2.4SafetGradeAFWInitiation andFlowIndication II.E.1.2TheAFWsystemautomatic initiation systemwastohavebeencontrolgrade'byJune1,1980,andsafetygradebyJuly1,1981;theAFWsystemflowindication wastohavebeencontrolgradebyJanuary1,1980,andsafetygradebyJuly1,1981.2.5Dedicated HdroaenPenetrations II.E.4.1Plantsthatuseexterna1'recombikers orpurgesys.emsforfpost-accident combustible gascontrolofthecontainment atmosphere shouldprovidecontainment
'penetrations dedicated tothatservice.Insatisfying hisitem,someplantsmayhavetoaddsomeadditional pipingandvalves.Ifso,theseval.vesshouldbesubjected totherequirements ofAppendixJof10CFR50,andtheTSshouldbemodifi'ed accordingly.
2.6Containment PressureSetoointII.E.4.2.5 Thecontainment pressuresetpointthat.initiates containment isolation mustbereducedto'theminimumcompatible withnormaloperating conditions.
Hostplantsprovidedj.ustification fornotchangingtheirsetpointandtheNRChasapprovedtheirjustification byseparatecorrespondence.
The.remaining plantsmustsubmitachangetotheTSwith the.lowercontainment pressuresetpointandprovidejustification ifthissetpointismorethan1psiabovemaximumexpectedcontainment pressureduringnormaloperation.
12.7Containment PuraeValvesII.E.4.2.6 ModelTSweresentseparately toeachplantaspartoftheoverallcontainment purgereview.TheseTSincludetherequirement thatthecontainment purgevalvesbelockedclosedexceptforsafetyrelatedac.ivities, verifiedclosedatleastevery31days,and.besubjected tole'akageratelimits.2.8Radiation SianalonPuroeValvesII.E.4.2.7 Thecontainment purgevalvesmustclosepromptlytoreducetheamountofradiation releasedoutsidecontainment following areleaseofradioactive materials tocontainment.
TSshouldincludetherequirement thataleastoneradiation monitorthatautomatically closesthepurgevalvesuponsensinghighradiation inthecontainment atmosphere beoperableatalltimesexceptcoldshutdowns andrefueling outaoes.Ifnot0operable, ei.hertheplantshouldbeginproceeding'o coldshutdownwithin24hoursorthepurgevalvesshouldbeclosedwithin24hours.ModelTSwereprovidedinStandardTechnical Specifications formatforthoseplantsthatareusingsafety-grade components tosatisfytherequirement.
12.9UradeBabcockandWi1coxB8WAFWSII.K.2.8Additional long-term AFWSmodifications weretobeperformed inconjuction withGenericLetter82-l6Items3and4(Items2.3and2.4above).TheTSimplemented forItems3and4wi1.1alsoaddresstheupgradeof'theBEWAFWS;therefore noseparateTSwouldberequiredforthisitemfortheBKWPlants.
2.10BEWSafet-GradeAnicioa.orReactorTriII.K.2.10 Safety-grade turbinetripequipment initiating areactortripwastobeimplemented bytheBEWdesignedplantsaspartoftheTMIlessonslearned.Thelicenseeistoimplement intheTSthetripsetpoint, numberofchannels, tripconditions, minimalchannelsrequiredforoperation, applicable operating modes,actionstobetaken,surveillance requiredandanyotherrequirements forsafety-grade equipment.
2.11BEWThermal-Mechanical ReportII.~.13Licensees ofMWoperating reactorswererequiredtosubmit,byJanuary1,1981,ananalysisofthethermal-,mechanical conditions inthereactorvesselduringrecoveryfromsmallbreakswithanextendedlossofallfeedwater.
TS,ifrequired, willbedetermined following NRCstaffreview.12.12ReoortinSafestandRelief.ValveFailuresand.ChallenoesII.K.3.3NUREG-0660 statedthatsafetyandrelief.valvefailuresbereportedpromptlyandchallenges bereportedannually.
ThesectionsoftheTSthatdiscussreporting requirements shouldbeaccordingly changed.TheNRChasnotedthatanacceptable alternative wouldbetoreportchallenges monthly.12.13Anticioator TrioonTurbineTriII.K.3.12 Licensees withWestinghouse-designed operating plantshaveconfirmed thattheirplantshaveananticipatory reactortripuponturbinetrip.ManyoftheseplantsalreadyhavethistripintheTS.Forthosethatdonot,theanticipatory tripshouldbeaddedtotheTS.1FortheSt.LuciePlantUnit1and2,theaboveItems2.9,2.10,and2.11arenotbeingevaluated.
BeingaCombustion Engineering
: design, Items2.9and2.10arenotapplicable forSt.LuciePlantUnit1and2.ForItem2.11,FPL'sThermal-Mechanical ReportisbeinohandledasanactiveThreeNileIsland(TMI)actioni.emunderTAGnumber46905forSt.LuciePlantUnit1.
3.EVALUATION Theevaluations ofGenericLetter82-16Itemsareasfollows:3.1STATraininI.A.1.1.3 ThelicenseehasstatedinhisresponseforSt~LucieUnit1thatthisitemwasaddressed byTSAmendment No.37.InTable6.2-1ofbothSt.LuciePlantUnit1and2TS,'heSTAisdesignated asbeingrequired6,7intheminimalshiftcrewcomposition foroperational modes1,2,3,or4.Section6.3.1specifies "heShiftTechnical Advisorwhoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesignandintheresponseandanalysisoftheplantfortransients andaccidents."
Theretraining andreplacement
)i6trainingprogramforthefacilitystaffisstatedinSection6.4.1oftheTS.TheexacttrainingprogramfortheSTAisnotintheTS.InAmendment 5totheSt.LuciePlantUnit2FSARAppendix1.9A,the4NUREG-0737
'itemsareaddressed.
TnelicenseestatesthatChapter13oftheFSARhasbeenrevisedtoaddresstherequiremen ofNUREG-0737 ItemI.A.l.l.Subsection 13.1.2.2specifies theresponsibility, authority, phaseoWplans,andreporting relationships; subsection 13.1.3.1and13.2.1.1.2specifythetrainingrequirements.
InaletterfromtheNRCtothelicensee, datedJanuary26,1982,8theNRCstatedthatItemI.A.1.1.3ofNUREG-0737 isresolved.
UntilfurherguidanceisissuedbytheCommission, nofurtherlicensing actionisrequiredforthisitem.3.2ShiftHannin-Over.imeLimitsI.A.1.3.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheovertimelimitations areadequately enforcedbyadministrative procedures andthatnoamendment totheTSisnecessary atthistime.This policywasacceptedbytheNRCintheletterfromR.A.ClarktoR.E.Uhrig,datedFebruary4,1982.TheTSforSt.LucieUnit1donotcontainanyshiftmanningovertimelimitation requirements.
Section6.2.2oftheSt.LucieUnit2TScontainstheovertimelimi'.sasspecified inGenericLetter82-12andistherefore incompletecompliance withNUREQ-0737 ItemI.A.1.3.1.OnJune30,1983,anotegramfromD.C.Fischer,LeadProjecManager10forthemaintopicI.A~1.3wassenttotheoperating reactorprojectmanagerforSt.LuciePlantUnit1requesting thattheTACnumberbeclosedou.forItemI.A.1.3.1onSt.LuciePlantUnit1.Nofurtherlicensing actionisrequiredforthisitem.3.3ShortTermAuxiliarFeedwater SstemAFWSEvaluation II.E.1.1ThelicenseehasstatedinhisresponsethattheexistingSt.LuciePlantUnit1AFWSTSlimitingconditions ofoperation andsurveillance, requirements aresimilarto.thatofothersafetyrelatedsystems.Section3.7,1.2and4.7.1.2oftheSt.LuciePlantUnits1and2TSprovidethecondition foroperation andthesurveillance requirements.
Inenclosure 2oftheFPLlettertotheNRC,datedJanuary2,111981,thelicenseeaddresses NUREG-0737 ItemII.E.1.1forSt.LuciePlantUnit,1.-Theenclosure isareportwhichprovidesthedescription ofAFWSmodifications tobeimplemented byJanuary1,1982andthesafetyevaluaionofthesystem.Amendment 5totheSt.LuciePlantUnit2FSARAppendix1.9Aaddresses NUREG-0737 ItemII.E.1.1.
Areliability analysiswasperformed todetermine dominantfailuremodesandassessAFWSreliability levels.Theresultsofthereliability evaluation areprovidedinAppendix10.4.9BoftheFSAR.AsafetyreviewwasalsoprovidedusingtheguidanceinStandardReview.Plan10.4.9.TheresultsareprovidedinAppendix10.4.9.AoftheFSAR.
ReviewoftheTSforSt.LuciePlantUnits1and2indicated thatthelimitingconditions ofoperation andsurveillance requirements aresimilartothoseothersafety-related systemsidentified intheTS.Nofurtherlicensing actionisrequiredforthisitem.3.4SafetGradeAFWInitiation andFlowIndication II.E.1.2ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatTSAmendment No.37,whi.chwasapprovedbytheNRCJanuary19,1981,containsalltheinformation pertaining tothesafetygradeAFWSysteminitiation andflowindication.
Inenclosure 2oftheFPLlettertotheNRC,datedJanuary2,1981,thelicenseeaddresses NUREG-0737 ItemICE.1.2forSt.LuciePlantUnit1.ThisitemiscoveredforS.LuciePlantUnit2inAmendment 5totheFSARinAppendix1.9A.ReviewoftheTSforSt.LuciePlantUnits1and2indicates thattheAFWinitiation andflowindication aresafetygrade.Nofurtherlicensing actionisrequiredforthisitem.3.5Dedicated HdrooenPenetrations II.E.4.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheirhydrogenrecombiners areinternalbutthatahydrogenpurgesystemwasinstalled andtheSt.LuciePlantUnit1TSsubjectsthehydrogenpurgevalvestothecriteriaspecified inAppendixJof10CFR50.InAmendment 5toSt.LuciePlantUnit2FSAR,thelicenseehasstatedthatredundant internalhydrogenrecombiners areprovided.
Therefore, NUREG-0737 ItemI.E.4.1isnotapplicable toSt.LuciePlantUnit2.Adiscussion oftheinternalhydrogenrecombiners isprovidedinSubsecion6.2.5oftheFSAR.ReviewoftheSt.LuciePlantUnit1TSindicates thatthevalvesaresubjecttotherequirements ofAppendixJof10CFR50andsinceSt.LuciePlanUnit2utilizesinternalhydrogenrecombiners andapparently hasnot addedadditional pipingandvalves,itisconcluded thatheNUREG-0737 itemrequirements aremet.Nofurtherlicensing actionisrequiredforthisitern.3.6Containment PressureSetoointII.E.4.2.5 ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatanalysiswasprovidedtotheNRCjustifying thepresentsetpointforcontainment pressure.
TheNRCacceptedthepresentsetpointiniheleterR.A:ClarkcoR.E.Uhrig,datedJanuary20,1982.12ReviewofTable2.2-1oftheTSforSt.LuciePlantUnit2indicates thesetpointlimitsareinaccordance
-'otherecommended guidelines ofGenericLetter82-16.Nofur.herlicensing ac.ionisrequiredforthisitem.3.7Containment PuroeValveII.E.4.2.6 Thelicenseehas.statedinhisresponseforSt.LuciePlantUnit1t'hataresponsewasprovidedtotheNRCinFPLletterL-82-317, datedJuly30,1982.However,itisnotindicated thatanNRCacceptance wasgiven.ReviewoftheTSforSt.LuciePlantUnit1indicaesthat~compliance toGenericLetter82-16hasnotbeenmet..TheSt.LuciePlantUnit2TSSection3/4.6providestheinformation onthecontainment purgevalvelimitingcondition foroperation, surveillance requirements,andthetestingtobeperformed onthevalves.TheTSSection3.6.1.7specifies hatthepurgevalvesbesealedclosedandverifiedatleastonceper31daysexceptforsafetyrelatedactivities.
TheTSleaktestingistypeCwhichisperformed withgasatintervals nogreaterthan24mon.hs.St.Lucie'lant Unit2TSmeetstherecommended guidanceofGenericLeter82"16.Nofurtherlicensing actionisneededforUnit2.10  
~~3.8Radiation SinalonPureValvesII.E.4.2.7 ThelicenseehassatedinhisresponseforSt.LuciePlantUnit1thattheexistingTSrequiresthatwithin24hours,theplantbeginsproceeding tocoldshutdownshouldallcontainment radiation monitorsfail.Alsothecontainment isolation isinitiated byhighradiation (andothersignals)closingthepurgevalves.ReviewoftheTSforSt.LuciePlantUnits1and2indicatethattherequirements ofNUREG-0737 ItemII.E.4.2.7 havebeenmet.Nofurtherlicensing actionisrequiredforthisitem.3.9UpgradeBabcockandWilcox.B8WAFWSII.K.2.8St.LuciePlantUnits1and2areaCombustion Engineering designand,therefore, therequiremeRtsofthisitemarenotapplicable.
Nolicensing actionisrequired.
3.10B&WSafet-GradeAnticiatorReactorTriII.K,2.10~'t.LuciePlantUnits1and2areaCombustion Engineering designand,therefore, therequiremen'ts ofthisitemarenotapplicable.
Theanticipatory tripisevaluated underNUREG-0737 ItemII.K.3.3forthe'Westinghouse design.Nolicensing actionisrequired.
3.11BKWThermal-Mechanical ReortII.K.2.13 St.LuciePlantUnits1and2areaCombustion Engineering designand,therefore',
therequirements ofthisitemarenotapplicable.
IthasbeennotedthatthereisanactiveTMIactionitemThermal-Mechanical ReportforSt.LuciePlantUnit1underTACNumber46905.Nolicensing actionisrequiredbyGenericLetter82-16forthisitem.11 3.12Reoortino SafetandReliefValveFailuresandChallenaes II.K.3.3ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatacommitment
.oreportsafetyandreliefvalvechallenges onanannualIbasiswasgivenintheirletterL-80-184, datedJuly13,'1980.Thelicenseealsocommitted tomakebothTScompatible totherequirements ofGene.icLetter82-16following finalization oftheSt.LuciePlantUnit2TS.ReviewoftheSt.LuciePlantUnit1TSindicates thatSec.ion6.9.1.6hasnotbeenamendedyettoincludethereporting onamonthlybasisforall'challenges tothevalves.St.LuciePlantUnit2TSSection6.9.1.6is'ncompliance withtherequirements oGenericLetter82-16.Nofurtherlicensing actionisrequiredforS.LuciePlantUnit2.3.13Anticioator TrioonTurbineTripII.K.3.12ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatalthoughnotaWestinghouse design,theTSadequately covertheanticipatory triponturbinetrip.ReviewoftheTSTables2.2-1,3.3-1and3.3-2indicatethattherequirements setforthinGenericLetter82-16havebeenmet.Nofurtherlicensing actionisrequired.
12 4.CONCLUSIONS Basedonourreview,wefindthelicenseeconformstothoseissuesaddressed inGenericLetter82-16onTS,exceptforthoseidentified asfollows:1.,Section3.1STATraining-UntilfurtherguidanceisprovidedbytheCommission, nofurtherlicensing actioncanbetakentodetermine whethertheexacttrainingprogramfortheSTAisrequiredtobeintheTS.2.Section3.2Shif-Manning-Overtime Limits-St.LuciePlantUnit1TSdonotcontainshift-manning overtimelimits,however,FPL'sovertimelimitspolicywasacceptedbytheNRC.3.Section3.7Containment PurgeValve-St.LuciePlantUnit1TSdanotcomplywiththe,requirements ofGenericLetter82-16.4.Section3.11Thermal-Mechanical Report-TheThermal-Mechanical
,ReportforSt.LuciePlantUnitNo.1isbeinghandledasanactiveTMIactionitemunderTACnumber46905:Thereisnoidentified
'TMIactionitemfortheSt.LuciePlantUnitNo.2Thermal-Mechanical Report.GenericLetter82-16doesnotrequireanylicensing actionforthisitem.5.Section3,.12 Reporting SafetyandReliefValveFailuresandChallenges
-ThepresentSt.LuciePlantUnit1TSdonotcomplywiththerequirements ofGenericLetter82-16.However,FPLispresently updatingtheSt.LucieUnit1TStoconformwiththeSt.LucieUnit2TS.Whenthisi5completed andapprovedbytheNRC,theSt.LucieUnit1TSshouldbeincompliance withiherequirements ofGenericLetter82-16.13 5.REFERENCES D.G.Eisenhut, NRClettertoAllPressurized PowerReactorLicensees, "NUREG-0737 Technical Specifications (GenericLetter82-16),"September 20,1982.NUREG-0737, Clarification ofTMIActionPlanRequirements, published bytheDivisionofLicensing, OfficeofNuclearReactorRegulation, U.S.NuclearRegulatory Commission, November1980.R.E.Uhrig,FloridaPowerandLightlettertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit1,DocketNo.50-335,NUREG-0737 Technical Specifications,"
December22,1982.R.E.Uhrig,FloridaPowerandLightCompanylettertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit2,DocketNo.50-389Amendment 5totheFinalSafetyAnalysisReport,"L-81-351, August12',1981.D.G.Eisenhut, NRClettertoAllLicensees ofOperating Plans,ApplicansforanOperating License,andHoldersofConstruction Permits,"NuclearPowerPlantStaffWorkingHours(GenericLetterNo.82-12),"June15,1982.St.LuciePlantUnit1Technical Specifications, AppendixAtoLicenseNo.DPR-67,March1,1976,Amendment No.58.Technical Specifications, St.LuciePlantUnit2,DocketNo.50-389,AppendixAtoLicenseNo.NPF-16,April1983.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLighgCompany,"NUREG-0737 ItemI.A.1.1ShiftTechnical Advisor(STA),"January26,1982.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"TMIActionPlantItemsI.A.1.3,I.C.5,andI.C.6asDescribed inNUREG-0737,"
February4,1982..D.C.Fischer,LeadProjectManagerforI.A.1.3,notegramtoalloperating reactorprojectmanaoers, "TACCloseout" June30,1983'.R.E.Uhrio,FlordiaPowerandLiohtCompanylet.ertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit1,DocketNo.50-335.Post TMIRequirements."
L-81-4,January2,1981.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"NUREG-0737 ItemII.E.4.2(5) forSt.LucieUnit1,"January20,1982.14 U.S.NUCLEARREGULATORY COMMISSION BIBLIOGRAPHIC DATASHEET4.TITLEiANOSUBTITLECONFORMANCE TONRRGENERICLETTER82-16.ST.LUCIEPLANTUNITNOS1AND21.REPORTNUMBER(Asssgned*y DOC/,EGG-EA-6432 2./Leeeedlenk/3.RECIPIENT'S ACCESSION NO.7.AUTHORIS)R.VanderBeek 9.PERFORMING ORGANIZATION NAMEANOMAILINGAOORESS/IncludeZipCode/EG8GIdaho,Inc.IdahoFalls,ID8341512.SPONSORINQ ORGANIZATION NAMEANOMAILINQAOORESS/IncludeZipCods'IDivisionofPro'ectndidntP1U.S.Nuc',earReguatoryCommission 101MariettaStreetSuite29005.OATEREPORTCOMPLETEO MONTHYEARDATEREPORTISSUEOMONTHOctober6./LeeeeolenklYEAR1983B./Leeeeolenkl11FINNo.10,PROJECT/TASK/WORK UNITNO,13TYPEOFREPORTuERIOOCOYERED/Inclusive deses/15.SUPPLEMENTARY NOTES14/Leereormki16,ABSTRACTI200wordsorress/ThisEG8GIdaho,Inc.,reportevaluates whetherthedesignated Operating ReactorPlanthasconformed totherequirements oftheNRRGenericLetterNo.82-16,"NUREG-0737 Technical Specifications."
17,KEYWOROS*NOOOCUMENTANALYSIS17s.OESCRIPTORS Ijb,IOENTIFIERSI'OPEN ENOEOTFRMSIB.AVAILABILITY STATEMENT UnlimitedNACFORM335sslSll'19.SECURITYCLASSIrnisreooislUnclassified 20.SECURITYCLASS/TliSpete/Unclas'fi21O'OOFPAGES22PRICE5 hil'4ItI}}

Revision as of 16:19, 29 June 2018

Conformance to NRR Generic Ltr 82-16,St Lucie Plant,Units 1 & 2, Preliminary Rept
ML17214A693
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 10/31/1983
From: VANDERBEEK R
EG&G, INC.
To:
NRC
Shared Package
ML17214A692 List:
References
CON-FIN-A-6600, RTR-NUREG-0737, RTR-NUREG-737 EGG-EA-6432-DRF, EGG-EA-6432-DRFT, GL-82-16, NUDOCS 8402130457
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4EGG-EA-6432 OCTOBER1983CONFORMANCE TONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeek IdahoNationalEngineering Laboratory OperatedbytheU.S.Department ofEnergyljfzj.ragaeahsAnmvI'!',Iv!~'rdV-addaaaaada~ov~'-'""h"=oaves';.,g-"-.L..rr'~ottv'.W

.Ca4~~4hThisisaninformalreportintendedforuseasapreliminary orworkingdocument0402130407 840($0~;.PDR,ADOCK05000335,',',,',

PPDR'reparedrortheU,S,NUCLEARREGULATORY COMMISSION UnderDOEContractNo.DE-AC07-76ID01570 FINNo.A6600~~E&Z&IdahoI1

'tv'!r EGG-EA-6432 CONFORMANCE TONRRGENERICLETTER82-16ST.LUCIEPLANTUNITNOS1AND2R.VanderBeek Published October1983EGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatory Commission Atlanta,Georgia30303UnderDOEContractNo.DE-AC07-76ID01570 FINNo.A6600 ABSTRACTThisEGKGIdaho,Inc.,reportevaluates thesubmittal providedbyFloridaPowerandLightCompany(FPL)forSt.LuciePlantUnitNos.1and2.Thesubmittal isinresponsetoGenericLetterNo.82-16,"NUREG-0737 Technical Specifications

.(TS)".Applicable sectionsoftheplants'Sareevaluated todetermine compliance totheguidelines established inthegenericletter.FOREWORDThisreportissuppliedaspartofhe"Technical Assistance forOperating ReactorsLicensing Actions"beingconducted fortheU.S.NuclearRegulatory Commission RegionIIbyEG5GIdaho,Inc.,NRCLicensing SupportSection.TheU.S.NuclearRegulatory Commission Fundedtheworkunderauthorization BAR92-19-20-10, FINNo.A6600;DocketNos.50-335and50-389TACNos.49760andR2X162 CONTENTSABSTRACT...............

FOREWORD,

.INTRODUCTION 2.'.REVIEWREQUIREMENTS

~~~~~0~~~~2.1STATraining(I.A.1.1.3) t2.2ShiftManning-Overtime Limits(I.A.1.3.1)2.3ShortTermAuxiliary Feedwater System(ARlS)Evaluation (II.E.1.1)2.42.5SafetyGradeAFWInitiation andFlowIndication (II.E.1.2)Dedicated HydrogenPenetr'ations (II.E.4.))

~~~~~32.6Containment PressureSetpoint(II.E.4.2.5) 2.7Containment PurgeValves(II.E.4.2.6) 2.8Radiation SignalonPurgeValves(II.E.4.2.7)

...........'...

42.9UpgradeBabcockandWil'cox(B&W)AFWS(II.K.2.8) 2.10B&WSafety-Grade Anticipatory ReactorTrip(II.K.2.10)2.11B&WThermal-Mechanical Report(II.K.2.13)2.12Reporting SafetyandReliefValveFailuresandChallenges (II.K.3.3) 2.13Anticipatory TriponTurbineTrip(II.K.3~12)3.EVALUATION 3.1STATraining(I.A.1.1.3) 3.2ShiftManning-Overtime Limits(I.A.1.3.1) 3.3ShortTermAuxiliary Feedwater System(AFWS)Evaluation (II.E.1.1)3.4SafetyGradeAuxiliary Feedwater (AFW)Initiation andFlowIndication (II.E.1.2) 3.5Dedicated HydrogenPenetrations (II.E.4.1)55 3.6Containment PressureSetpoint(II.E.4.2.5) 3.7Containment PurgeValves(II.E.4.2.6) 3.8Radiation SignalonPurgeValves(II.E.4.2.7) 3.9"UpgradeBabcockandWilcox(B&W)AFWS(II.K.2.8) 3~10B&WSafety-Grade Anticipatory ReactorTrip(II.K.2.10) 3.11B&WThermal-Mechanical Report(II.K.2.13) 10103~12Reporting SafetyandReliefValveFailuresandChallenges (II.K.3.3)123.13Anticipatory TriponTurbineTrip(II.K.3.12)

..............

124.CONCLUSIONS 5.REFERENCES 1314 CONFORMANCE TONRRGENERICLETTER82"16ST.LUCIEPLANTUNITNOS1AND21.INTRODUCTION OnSeptember 20,1982,GenericLetter82-16wasissuedby1D.G.Eisenhut, DirectorofLicensing, OfficeofNuclearReactorRegula'tion (NRR),toallpressurized powerreactorlicensees.

Thisletteridentified' numberofitemsrequiredbyNUREG-0737 tobeimplemented inthe2licensee's Technical Specifications (TS)byDecember31,1981.Eachlicenseewasrequested toreviewtheirfacility's TS,toaddressareasofcompliance.,

andtoidentifydeviations orabsenceofaspecification fortheitemsidentified in.thegenericletterwithin90daysofreceiptoftheletter.TheFloridaPowerandLightCompany..(FPL),

thelicenseeforSt.LuciePlantUnitNos.1and2,providedaresponsetothegenericletteronDecember22,1982,forSt.LuciePlant.UnitNo.1.TheNUREG-0737 items3forSt.'LuciePlantUnitNo.2werecoveredinAmendment 5totheFinalSafetyAnalysisReport(FSAR)forSt.LuciePlantUnitNo.2.Thisinterimreportprovidesanevaluation ofthelicensee's TSandNuclearRegulatory Commission(NRC)correspondence withthelicenseepertaining tothoseitemsidentified inthegenericletter.

2.REVIEWREQUIREMENTS Thereviewconsistsofevaluating

<helicensee's

response, currently approvedTS,andotherNRRapprovals agains.thecriteriasetforthinGenericLetter82-16.TheNUREG-0737 itemsandthecriteriaestablished areasfollows:2.1STATraininI.A.1.1.3 ThelicenseeistoaddresswithintheirTSthatashift,technical advisor(STA)totheshiftsupervisor isp0ovided.

Inaddition, thequalifications,

training,

.andon-dutyrequirements fortheSTAshouldbestated.2.2Sh-iftMannin-Ov'ertime Limi'tsI.A.1.3.1Thelicenseeistoprovidechanaesto.heirTSproviding overtimeadministrative procedure andstaffingrequirements.

Thefollowing

'guidelines wereestablished forthelicenseebytheNRC."a~Anindividual shouldnotbepermitted toworkmorethan16hoursstraight(excluding shiftturnovertime).b.Anindividual shouldnotbepermitted toworkmorethan16hoursinany24-hourperiod,normorethan24hoursinany48-hourperiod,normorethan72hoursinanysevendayperiod(allexcluding shiftturnovertime).c.Abreakofatleasteighthoursshouldbeallowedbetweenworkperiods(including shiftturnovertime).d.Exceptduringextendedshutdownperiods,theuseofovertimeshouldbeconsidered onanindividual basisandno.fortheentiresaffonashift.Recognizing thatveryunusualcircumstances mayariserequi~ing deviation fromtheaboveguidelines, suchdeviation shallbeauthorized bytheplantmanagerorhisdeputy,orhigherlevelsofmanaoement.

Theparamount consideration insuchauthorization shallbethatsignificant reductions intheeffectiveness ofoperating personnel wouldbehighlyun1ike1y.

Inaddition, procedures areencouraoed thatwouldallowlicensed'operators atthecontrolstobeperiodically relievedandassignedtoothe'rdutiesawayfromthecontrolboardduringtheirtourofduty."52.3ShortTermAuxiliarFeedwater SstemAFWSEvaluation II.E.1.1Theobjective ofthisitemistoimprovethereliability andperformance oftheauxiliary feedwater (AFW)system.TSdependontheresultsofthelicensee's evaluation andthestaffreview,andarebeingdeveloped separately foreachplant.Thelimitingconditions ofoperation (LCO's)andsurveillance requirements fortheAFWsystemshouldbesimilar1toothersafety-related systems.2.4SafetGradeAFWInitiation andFlowIndication II.E.1.2TheAFWsystemautomatic initiation systemwastohavebeencontrolgrade'byJune1,1980,andsafetygradebyJuly1,1981;theAFWsystemflowindication wastohavebeencontrolgradebyJanuary1,1980,andsafetygradebyJuly1,1981.2.5Dedicated HdroaenPenetrations II.E.4.1Plantsthatuseexterna1'recombikers orpurgesys.emsforfpost-accident combustible gascontrolofthecontainment atmosphere shouldprovidecontainment

'penetrations dedicated tothatservice.Insatisfying hisitem,someplantsmayhavetoaddsomeadditional pipingandvalves.Ifso,theseval.vesshouldbesubjected totherequirements ofAppendixJof10CFR50,andtheTSshouldbemodifi'ed accordingly.

2.6Containment PressureSetoointII.E.4.2.5 Thecontainment pressuresetpointthat.initiates containment isolation mustbereducedto'theminimumcompatible withnormaloperating conditions.

Hostplantsprovidedj.ustification fornotchangingtheirsetpointandtheNRChasapprovedtheirjustification byseparatecorrespondence.

The.remaining plantsmustsubmitachangetotheTSwith the.lowercontainment pressuresetpointandprovidejustification ifthissetpointismorethan1psiabovemaximumexpectedcontainment pressureduringnormaloperation.

12.7Containment PuraeValvesII.E.4.2.6 ModelTSweresentseparately toeachplantaspartoftheoverallcontainment purgereview.TheseTSincludetherequirement thatthecontainment purgevalvesbelockedclosedexceptforsafetyrelatedac.ivities, verifiedclosedatleastevery31days,and.besubjected tole'akageratelimits.2.8Radiation SianalonPuroeValvesII.E.4.2.7 Thecontainment purgevalvesmustclosepromptlytoreducetheamountofradiation releasedoutsidecontainment following areleaseofradioactive materials tocontainment.

TSshouldincludetherequirement thataleastoneradiation monitorthatautomatically closesthepurgevalvesuponsensinghighradiation inthecontainment atmosphere beoperableatalltimesexceptcoldshutdowns andrefueling outaoes.Ifnot0operable, ei.hertheplantshouldbeginproceeding'o coldshutdownwithin24hoursorthepurgevalvesshouldbeclosedwithin24hours.ModelTSwereprovidedinStandardTechnical Specifications formatforthoseplantsthatareusingsafety-grade components tosatisfytherequirement.

12.9UradeBabcockandWi1coxB8WAFWSII.K.2.8Additional long-term AFWSmodifications weretobeperformed inconjuction withGenericLetter82-l6Items3and4(Items2.3and2.4above).TheTSimplemented forItems3and4wi1.1alsoaddresstheupgradeof'theBEWAFWS;therefore noseparateTSwouldberequiredforthisitemfortheBKWPlants.

2.10BEWSafet-GradeAnicioa.orReactorTriII.K.2.10 Safety-grade turbinetripequipment initiating areactortripwastobeimplemented bytheBEWdesignedplantsaspartoftheTMIlessonslearned.Thelicenseeistoimplement intheTSthetripsetpoint, numberofchannels, tripconditions, minimalchannelsrequiredforoperation, applicable operating modes,actionstobetaken,surveillance requiredandanyotherrequirements forsafety-grade equipment.

2.11BEWThermal-Mechanical ReportII.~.13Licensees ofMWoperating reactorswererequiredtosubmit,byJanuary1,1981,ananalysisofthethermal-,mechanical conditions inthereactorvesselduringrecoveryfromsmallbreakswithanextendedlossofallfeedwater.

TS,ifrequired, willbedetermined following NRCstaffreview.12.12ReoortinSafestandRelief.ValveFailuresand.ChallenoesII.K.3.3NUREG-0660 statedthatsafetyandrelief.valvefailuresbereportedpromptlyandchallenges bereportedannually.

ThesectionsoftheTSthatdiscussreporting requirements shouldbeaccordingly changed.TheNRChasnotedthatanacceptable alternative wouldbetoreportchallenges monthly.12.13Anticioator TrioonTurbineTriII.K.3.12 Licensees withWestinghouse-designed operating plantshaveconfirmed thattheirplantshaveananticipatory reactortripuponturbinetrip.ManyoftheseplantsalreadyhavethistripintheTS.Forthosethatdonot,theanticipatory tripshouldbeaddedtotheTS.1FortheSt.LuciePlantUnit1and2,theaboveItems2.9,2.10,and2.11arenotbeingevaluated.

BeingaCombustion Engineering

design, Items2.9and2.10arenotapplicable forSt.LuciePlantUnit1and2.ForItem2.11,FPL'sThermal-Mechanical ReportisbeinohandledasanactiveThreeNileIsland(TMI)actioni.emunderTAGnumber46905forSt.LuciePlantUnit1.

3.EVALUATION Theevaluations ofGenericLetter82-16Itemsareasfollows:3.1STATraininI.A.1.1.3 ThelicenseehasstatedinhisresponseforSt~LucieUnit1thatthisitemwasaddressed byTSAmendment No.37.InTable6.2-1ofbothSt.LuciePlantUnit1and2TS,'heSTAisdesignated asbeingrequired6,7intheminimalshiftcrewcomposition foroperational modes1,2,3,or4.Section6.3.1specifies "heShiftTechnical Advisorwhoshallhaveabachelor's degreeorequivalent inascientific orengineering discipline withspecifictraininginplantdesignandintheresponseandanalysisoftheplantfortransients andaccidents."

Theretraining andreplacement

)i6trainingprogramforthefacilitystaffisstatedinSection6.4.1oftheTS.TheexacttrainingprogramfortheSTAisnotintheTS.InAmendment 5totheSt.LuciePlantUnit2FSARAppendix1.9A,the4NUREG-0737

'itemsareaddressed.

TnelicenseestatesthatChapter13oftheFSARhasbeenrevisedtoaddresstherequiremen ofNUREG-0737 ItemI.A.l.l.Subsection 13.1.2.2specifies theresponsibility, authority, phaseoWplans,andreporting relationships; subsection 13.1.3.1and13.2.1.1.2specifythetrainingrequirements.

InaletterfromtheNRCtothelicensee, datedJanuary26,1982,8theNRCstatedthatItemI.A.1.1.3ofNUREG-0737 isresolved.

UntilfurherguidanceisissuedbytheCommission, nofurtherlicensing actionisrequiredforthisitem.3.2ShiftHannin-Over.imeLimitsI.A.1.3.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheovertimelimitations areadequately enforcedbyadministrative procedures andthatnoamendment totheTSisnecessary atthistime.This policywasacceptedbytheNRCintheletterfromR.A.ClarktoR.E.Uhrig,datedFebruary4,1982.TheTSforSt.LucieUnit1donotcontainanyshiftmanningovertimelimitation requirements.

Section6.2.2oftheSt.LucieUnit2TScontainstheovertimelimi'.sasspecified inGenericLetter82-12andistherefore incompletecompliance withNUREQ-0737 ItemI.A.1.3.1.OnJune30,1983,anotegramfromD.C.Fischer,LeadProjecManager10forthemaintopicI.A~1.3wassenttotheoperating reactorprojectmanagerforSt.LuciePlantUnit1requesting thattheTACnumberbeclosedou.forItemI.A.1.3.1onSt.LuciePlantUnit1.Nofurtherlicensing actionisrequiredforthisitem.3.3ShortTermAuxiliarFeedwater SstemAFWSEvaluation II.E.1.1ThelicenseehasstatedinhisresponsethattheexistingSt.LuciePlantUnit1AFWSTSlimitingconditions ofoperation andsurveillance, requirements aresimilarto.thatofothersafetyrelatedsystems.Section3.7,1.2and4.7.1.2oftheSt.LuciePlantUnits1and2TSprovidethecondition foroperation andthesurveillance requirements.

Inenclosure 2oftheFPLlettertotheNRC,datedJanuary2,111981,thelicenseeaddresses NUREG-0737 ItemII.E.1.1forSt.LuciePlantUnit,1.-Theenclosure isareportwhichprovidesthedescription ofAFWSmodifications tobeimplemented byJanuary1,1982andthesafetyevaluaionofthesystem.Amendment 5totheSt.LuciePlantUnit2FSARAppendix1.9Aaddresses NUREG-0737 ItemII.E.1.1.

Areliability analysiswasperformed todetermine dominantfailuremodesandassessAFWSreliability levels.Theresultsofthereliability evaluation areprovidedinAppendix10.4.9BoftheFSAR.AsafetyreviewwasalsoprovidedusingtheguidanceinStandardReview.Plan10.4.9.TheresultsareprovidedinAppendix10.4.9.AoftheFSAR.

ReviewoftheTSforSt.LuciePlantUnits1and2indicated thatthelimitingconditions ofoperation andsurveillance requirements aresimilartothoseothersafety-related systemsidentified intheTS.Nofurtherlicensing actionisrequiredforthisitem.3.4SafetGradeAFWInitiation andFlowIndication II.E.1.2ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatTSAmendment No.37,whi.chwasapprovedbytheNRCJanuary19,1981,containsalltheinformation pertaining tothesafetygradeAFWSysteminitiation andflowindication.

Inenclosure 2oftheFPLlettertotheNRC,datedJanuary2,1981,thelicenseeaddresses NUREG-0737 ItemICE.1.2forSt.LuciePlantUnit1.ThisitemiscoveredforS.LuciePlantUnit2inAmendment 5totheFSARinAppendix1.9A.ReviewoftheTSforSt.LuciePlantUnits1and2indicates thattheAFWinitiation andflowindication aresafetygrade.Nofurtherlicensing actionisrequiredforthisitem.3.5Dedicated HdrooenPenetrations II.E.4.1ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thattheirhydrogenrecombiners areinternalbutthatahydrogenpurgesystemwasinstalled andtheSt.LuciePlantUnit1TSsubjectsthehydrogenpurgevalvestothecriteriaspecified inAppendixJof10CFR50.InAmendment 5toSt.LuciePlantUnit2FSAR,thelicenseehasstatedthatredundant internalhydrogenrecombiners areprovided.

Therefore, NUREG-0737 ItemI.E.4.1isnotapplicable toSt.LuciePlantUnit2.Adiscussion oftheinternalhydrogenrecombiners isprovidedinSubsecion6.2.5oftheFSAR.ReviewoftheSt.LuciePlantUnit1TSindicates thatthevalvesaresubjecttotherequirements ofAppendixJof10CFR50andsinceSt.LuciePlanUnit2utilizesinternalhydrogenrecombiners andapparently hasnot addedadditional pipingandvalves,itisconcluded thatheNUREG-0737 itemrequirements aremet.Nofurtherlicensing actionisrequiredforthisitern.3.6Containment PressureSetoointII.E.4.2.5 ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatanalysiswasprovidedtotheNRCjustifying thepresentsetpointforcontainment pressure.

TheNRCacceptedthepresentsetpointiniheleterR.A:ClarkcoR.E.Uhrig,datedJanuary20,1982.12ReviewofTable2.2-1oftheTSforSt.LuciePlantUnit2indicates thesetpointlimitsareinaccordance

-'otherecommended guidelines ofGenericLetter82-16.Nofur.herlicensing ac.ionisrequiredforthisitem.3.7Containment PuroeValveII.E.4.2.6 Thelicenseehas.statedinhisresponseforSt.LuciePlantUnit1t'hataresponsewasprovidedtotheNRCinFPLletterL-82-317, datedJuly30,1982.However,itisnotindicated thatanNRCacceptance wasgiven.ReviewoftheTSforSt.LuciePlantUnit1indicaesthat~compliance toGenericLetter82-16hasnotbeenmet..TheSt.LuciePlantUnit2TSSection3/4.6providestheinformation onthecontainment purgevalvelimitingcondition foroperation, surveillance requirements,andthetestingtobeperformed onthevalves.TheTSSection3.6.1.7specifies hatthepurgevalvesbesealedclosedandverifiedatleastonceper31daysexceptforsafetyrelatedactivities.

TheTSleaktestingistypeCwhichisperformed withgasatintervals nogreaterthan24mon.hs.St.Lucie'lant Unit2TSmeetstherecommended guidanceofGenericLeter82"16.Nofurtherlicensing actionisneededforUnit2.10

~~3.8Radiation SinalonPureValvesII.E.4.2.7 ThelicenseehassatedinhisresponseforSt.LuciePlantUnit1thattheexistingTSrequiresthatwithin24hours,theplantbeginsproceeding tocoldshutdownshouldallcontainment radiation monitorsfail.Alsothecontainment isolation isinitiated byhighradiation (andothersignals)closingthepurgevalves.ReviewoftheTSforSt.LuciePlantUnits1and2indicatethattherequirements ofNUREG-0737 ItemII.E.4.2.7 havebeenmet.Nofurtherlicensing actionisrequiredforthisitem.3.9UpgradeBabcockandWilcox.B8WAFWSII.K.2.8St.LuciePlantUnits1and2areaCombustion Engineering designand,therefore, therequiremeRtsofthisitemarenotapplicable.

Nolicensing actionisrequired.

3.10B&WSafet-GradeAnticiatorReactorTriII.K,2.10~'t.LuciePlantUnits1and2areaCombustion Engineering designand,therefore, therequiremen'ts ofthisitemarenotapplicable.

Theanticipatory tripisevaluated underNUREG-0737 ItemII.K.3.3forthe'Westinghouse design.Nolicensing actionisrequired.

3.11BKWThermal-Mechanical ReortII.K.2.13 St.LuciePlantUnits1and2areaCombustion Engineering designand,therefore',

therequirements ofthisitemarenotapplicable.

IthasbeennotedthatthereisanactiveTMIactionitemThermal-Mechanical ReportforSt.LuciePlantUnit1underTACNumber46905.Nolicensing actionisrequiredbyGenericLetter82-16forthisitem.11 3.12Reoortino SafetandReliefValveFailuresandChallenaes II.K.3.3ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatacommitment

.oreportsafetyandreliefvalvechallenges onanannualIbasiswasgivenintheirletterL-80-184, datedJuly13,'1980.Thelicenseealsocommitted tomakebothTScompatible totherequirements ofGene.icLetter82-16following finalization oftheSt.LuciePlantUnit2TS.ReviewoftheSt.LuciePlantUnit1TSindicates thatSec.ion6.9.1.6hasnotbeenamendedyettoincludethereporting onamonthlybasisforall'challenges tothevalves.St.LuciePlantUnit2TSSection6.9.1.6is'ncompliance withtherequirements oGenericLetter82-16.Nofurtherlicensing actionisrequiredforS.LuciePlantUnit2.3.13Anticioator TrioonTurbineTripII.K.3.12ThelicenseehasstatedinhisresponseforSt.LuciePlantUnit1thatalthoughnotaWestinghouse design,theTSadequately covertheanticipatory triponturbinetrip.ReviewoftheTSTables2.2-1,3.3-1and3.3-2indicatethattherequirements setforthinGenericLetter82-16havebeenmet.Nofurtherlicensing actionisrequired.

12 4.CONCLUSIONS Basedonourreview,wefindthelicenseeconformstothoseissuesaddressed inGenericLetter82-16onTS,exceptforthoseidentified asfollows:1.,Section3.1STATraining-UntilfurtherguidanceisprovidedbytheCommission, nofurtherlicensing actioncanbetakentodetermine whethertheexacttrainingprogramfortheSTAisrequiredtobeintheTS.2.Section3.2Shif-Manning-Overtime Limits-St.LuciePlantUnit1TSdonotcontainshift-manning overtimelimits,however,FPL'sovertimelimitspolicywasacceptedbytheNRC.3.Section3.7Containment PurgeValve-St.LuciePlantUnit1TSdanotcomplywiththe,requirements ofGenericLetter82-16.4.Section3.11Thermal-Mechanical Report-TheThermal-Mechanical

,ReportforSt.LuciePlantUnitNo.1isbeinghandledasanactiveTMIactionitemunderTACnumber46905:Thereisnoidentified

'TMIactionitemfortheSt.LuciePlantUnitNo.2Thermal-Mechanical Report.GenericLetter82-16doesnotrequireanylicensing actionforthisitem.5.Section3,.12 Reporting SafetyandReliefValveFailuresandChallenges

-ThepresentSt.LuciePlantUnit1TSdonotcomplywiththerequirements ofGenericLetter82-16.However,FPLispresently updatingtheSt.LucieUnit1TStoconformwiththeSt.LucieUnit2TS.Whenthisi5completed andapprovedbytheNRC,theSt.LucieUnit1TSshouldbeincompliance withiherequirements ofGenericLetter82-16.13 5.REFERENCES D.G.Eisenhut, NRClettertoAllPressurized PowerReactorLicensees, "NUREG-0737 Technical Specifications (GenericLetter82-16),"September 20,1982.NUREG-0737, Clarification ofTMIActionPlanRequirements, published bytheDivisionofLicensing, OfficeofNuclearReactorRegulation, U.S.NuclearRegulatory Commission, November1980.R.E.Uhrig,FloridaPowerandLightlettertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit1,DocketNo.50-335,NUREG-0737 Technical Specifications,"

December22,1982.R.E.Uhrig,FloridaPowerandLightCompanylettertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit2,DocketNo.50-389Amendment 5totheFinalSafetyAnalysisReport,"L-81-351, August12',1981.D.G.Eisenhut, NRClettertoAllLicensees ofOperating Plans,ApplicansforanOperating License,andHoldersofConstruction Permits,"NuclearPowerPlantStaffWorkingHours(GenericLetterNo.82-12),"June15,1982.St.LuciePlantUnit1Technical Specifications, AppendixAtoLicenseNo.DPR-67,March1,1976,Amendment No.58.Technical Specifications, St.LuciePlantUnit2,DocketNo.50-389,AppendixAtoLicenseNo.NPF-16,April1983.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLighgCompany,"NUREG-0737 ItemI.A.1.1ShiftTechnical Advisor(STA),"January26,1982.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"TMIActionPlantItemsI.A.1.3,I.C.5,andI.C.6asDescribed inNUREG-0737,"

February4,1982..D.C.Fischer,LeadProjectManagerforI.A.1.3,notegramtoalloperating reactorprojectmanaoers, "TACCloseout" June30,1983'.R.E.Uhrio,FlordiaPowerandLiohtCompanylet.ertoD.G.Eisenhut; OfficeofNuclearReactorRegulation, "St.LucieUnit1,DocketNo.50-335.Post TMIRequirements."

L-81-4,January2,1981.R.A.Clark,NRClettertoR.E.Uhrig,FloridaPowerandLightCompany,"NUREG-0737 ItemII.E.4.2(5) forSt.LucieUnit1,"January20,1982.14 U.S.NUCLEARREGULATORY COMMISSION BIBLIOGRAPHIC DATASHEET4.TITLEiANOSUBTITLECONFORMANCE TONRRGENERICLETTER82-16.ST.LUCIEPLANTUNITNOS1AND21.REPORTNUMBER(Asssgned*y DOC/,EGG-EA-6432 2./Leeeedlenk/3.RECIPIENT'S ACCESSION NO.7.AUTHORIS)R.VanderBeek 9.PERFORMING ORGANIZATION NAMEANOMAILINGAOORESS/IncludeZipCode/EG8GIdaho,Inc.IdahoFalls,ID8341512.SPONSORINQ ORGANIZATION NAMEANOMAILINQAOORESS/IncludeZipCods'IDivisionofPro'ectndidntP1U.S.Nuc',earReguatoryCommission 101MariettaStreetSuite29005.OATEREPORTCOMPLETEO MONTHYEARDATEREPORTISSUEOMONTHOctober6./LeeeeolenklYEAR1983B./Leeeeolenkl11FINNo.10,PROJECT/TASK/WORK UNITNO,13TYPEOFREPORTuERIOOCOYERED/Inclusive deses/15.SUPPLEMENTARY NOTES14/Leereormki16,ABSTRACTI200wordsorress/ThisEG8GIdaho,Inc.,reportevaluates whetherthedesignated Operating ReactorPlanthasconformed totherequirements oftheNRRGenericLetterNo.82-16,"NUREG-0737 Technical Specifications."

17,KEYWOROS*NOOOCUMENTANALYSIS17s.OESCRIPTORS Ijb,IOENTIFIERSI'OPEN ENOEOTFRMSIB.AVAILABILITY STATEMENT UnlimitedNACFORM335sslSll'19.SECURITYCLASSIrnisreooislUnclassified 20.SECURITYCLASS/TliSpete/Unclas'fi21O'OOFPAGES22PRICE5 hil'4ItI

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