ML17308A479

St Lucie Plant Unit 1 Rept of Changes Made Under Provision of 10CFR50.59 for Period Ending 890122. W/890720 Ltr

ML17308A479
Person / Time
Site:	Saint Lucie
Issue date:	01/22/1989
From:	WOODY C O FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-89-260, NUDOCS 8907250248
Download: ML17308A479 (171)

Text

WIRREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RZDS)ISSIONNBR8907250248DOC.DATE89/01/22NOTARIZED:NODOCKETNXL:50-'335.'St:.LuciePlant,:Unit1,FloridaPower&LightCo.05000335AUTH.NAMEAUTHORAFFILIATIONVOODY,C.O.:-.."-Florj.daPower:..;&..LightCo.RECIPNAME-.<;v<RECIPIENT'AFFILIATION~<~,'.>i""~~a"~~+"ri.",')'

SUBJECT:

"StLuciePlantUnit1ReptofChange'sMadeUnderProvisionDof10CFR50.59forPeriodEnding890122."W/890720ltr.DISTRIBUTIONCODE:XE47DCOPIESRECEIVED:LTRENCLSIZE-<'TITLE:50.59AnnualReportofChanges,TestsorExperimentsMadeW/outApprov,h~wINTERNAL:RECIPIENTIDCODE/NAMEPD2-2LANORRIS,JIACRS'EOD/DSP/TPABNRR/DOEA/EAB11'UDOCS-ABSTRACTRGN2FILE01LPDRNSICCOPIESLTTRENCL1010.loio11~1"11111RECIPIENTIDCODE/NAMEPD2-2PDAEOD/DOANRR/DLPQ/HFB10/E6+g/RPB10REGFILE02INRCPDRCOPIESLTTRECL11112211~T11DDRID5hNOTEToALLRIDS"EKCZPZENXS:OTALPLEASEHELPUSTOREDUCEKLSTB!CXWIRCZ'IHEDOCXIMEÃZCGNI.'ROLDESK,RXHPl-37(KCV.20079)TOEZiIKQRXBYOURMMEPKHDZSTBZBUTZCNLZ8TSH2tDOCUMENTSVXJDOHiTNEZD!NUMBEROFCOPIESREQUIRED:LTTR25ENCLIp4~.'f)r4~

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..Box14000,JunoBeach,FL33408.0420JULY20lS89L-89-26010CFR50.59U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnit1Docket,No.50-335Reortof10CFR50.59PlantChanesPursuantto10CFR50.59(b)(2),theenclosedreportcontainsabriefdescriptionofplantchanges/modifications(PCM)whichweremadeundertheprovisionsof10CFR50.59.IncludedwiththebriefdescriptionofeachPCMisasummaryofthesafetyevaluation.ThisreportincludesPCMscompletedbetweenJanuary23,1988andJanuary22,1989andcorrelateswiththeinformationincludedinRevision8oftheUpdatedFinalSafetyAnalysisReport.Verytrulyyours,C.O.ActineniorVicePresident-NuclearCOW/EJW/gpEnclosurecc:StewartD.Ebneter,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant~5'07250243PDRADDCI<ROSOOO335PDCanFPLGroupcompany 4(

StLucieP1antUnit1ReportofChangesMadeUndertheProvisionsof10CFR50.59fortheperiodendingJanuary22,19898907250248

PLANTCHAN6E/NODRFVIEMEDFORPSL1FSARAHENDHENT8NUtlBERREVISIONTITLE583-879875-882297-177889-182114-182355-183177-184839-185eee-18s892-185-1852e4-18s828-186858-186852-18e874-186877-186899-186114-186119-186128-186131-18633-186-186148-186e-18-38-58-38-1e-18-1,1,2ESFASPOMERSUPPLYDIESEL6ENERATORHI6HCAPACITYTURBOCHAR6ERINSTALLATIONREACTORCAVITYFILTRATIONSYSTEHREACTORVFSSELHEADSHIELDIN6TURBINESUPERVISORYINSTRUMENTATIONTHERHALSHIELDREMOVAL-PHASEIIIROSENOUNTTEtlPERATURETRANSMITTERREPLACEHENTED6SUBSYSTEHFLOMDIA6RAtlSREFUELIN6CFUELXFRMACHINEESFASPOMERSUPPLY.REPLACEMENTOFVALVESOLENOIDSICMBACKUPLUBEMATERBACKFLOMPREVENTERREPLACEMENTCCMPUNPJOURNALBEARIN6NATLCH6INSTRUMENTAIRUP6RADEUPPER6UIDESTRUCTURELIFTRI6REPAIRHEATERDRAINPvtlpDEHINERALIZEDMATERSUPPLY18CFR58.49EQLISTREVISIONU6SLIFTRI6LOADTESTFIXTURECONDENSATEPUMPSEXPANSIONJOINTREPLACENENT18CFR58.49EQLISTREVISIONS.U.TRANSFLOCKOUTDISCSMITCHAUTOLEAKRATETESTERFORPERSONNELAIRLOCKSQSPDSSOFTMARENODIFICATIONBECKHANMASTE6ASSYSTEMOXY6ENANALYZERREPLACEllENTANNUNCIATORNUISANCEALARMS PLANTCHAN6E/NODREVIEMEDFORPSL1FSARAHENDHENT8.NUNBERREVISIONTITLE147-186813-187816-187818-187834-187836-187839-187841-187854-187875-187-187878-187885-187888-187185-187116-187119-187123-187128-187141-187142-187143-1872-187-187881-1888-28-18-1IC'MDISCHPIPEZINCRIBBONSIHULATORTRAININ6FACILITY6AI-TRONICSCCM.TCMiOBCMVALVEACTVATORREPLACEHENTDRAINFORPIPELINER-MH-848CONDENSEROUTLETTUBESHEETANDMATERBOXCOATIN6SCONDENSERTUBIN6STRAIN6AUBEINSTALLATIONCONDENSERRECIRCTOCONDPNEUHATICSQRTEXTRREPLACENENTHAINFEEDMATERRE6VALVEPOSINDREHOVALCONDENSATEPOLISHERTIE-INSFIREDETECTORHODIFICATIONS-ERDADS/SASUP6RADEREPLOFF8PCONTROLLERSTURBINE6ENERATORSEALOILSYSTEHENHANCEHENTREMOTEREACTORVESSELLEVELINDICATIONCHAR6IN6PUNPBLOCKNATLCH6-REPLCHNTOFS.R.BATT1A4186ROUTIN6OFNASONRYBLOCKMALLSCEAN6SETSLOCK-OUTRELAYSITANK8CONTFANCOOLERINSTUP6RADE488VPCBTRANSFORHERREPLACEHENT488VLOADCNTR1A34183TRANSFORHERREPLACEHENT488VPCBTRANSFORHERREPLACEHENTSITSAMPLEVALVEASBUILDNODIFICATIONCEDSCOILPMRPR06PARTLEN6THREHOVALHOISTURESEPARATORREHEATERSHELLREPAIR PLANTCHANGE/NODREVIEMEDFORPSL1FSARAllENDtlENT8NUtlBERREVISIONTITLE883-188Dee5-1ss886-188887-188ee9-Iss818-188811-188812-188813-188815-188-188e19-1ss'28-188821-188822-188826-188829-188831-188.833-188835-188838-188843-les6-188-1880855-188D8-18-28-1e-1CONDENSEREXPANSIONJOINTIllPINGEllENTPLATEllODIFICATIONr"HETRASCOPEREPLACEHENThas'CPCOOLERHEATEXCHANGERTUBELEAKDETECTIONRCPVIBHONITEQUIPUP6RADEEQDOCPACK4DISCONNtlOVSPACEHTRSSTATIONAIR/INSTAIRPRESSINDRPLCHNTRAB/RCB'MALKMAY1B41DINSTRUHENTINVERTERDRAMINGCHAN6ESLIGHTIN6PANELRELAYICMLUBEMATERPIPERESTRAINTHODIFICATION'ONDENSATEPUllpDISCHAR6ESAtlPLINGLINESTURBINELUBEOILSYS/RESERVOIRPERNANENTFLUSHCONNECTIONSLP122CKTEXCHANGEDGBUILDIN6DELUGEVALVESCLAPPERLATCHASSEMBLYREPLACEMENTMIREDELETIONFROMSMI7CHSS-2/388FLOODPROTECTIONSTOPL06419B.A.CONCREDDOCPACUPDATERCBPROTECTIVECOATIN6SllAINTENANCEINSTRUMENTCHAN6ESFORHUllANFACTORSCONCERNSEXTRACTIONSTllPIPIN6NATLUP6RADEFDMTRRE6SYSCONTROLLERREPLACEllENTEQLISTREV-SPAREPARTSED6DMG8INSTRLISTCORRECTIONSREACTORHEAD0-RIN6RETAININ6RINGllODIFICATIONICM&CMPUllPPACKA6EREPLACEllENT PLANTCHAN6E/tlODREVIEMEDFORPSL1FSARAtlENDtlENT8NUtlBERREVISIONTITLEe59-1ssese-188864-188874-188875-188876-188D877-188D882-188893-188D894-188188187-188189-188111-188113-188D114-188115-188D117-188119-188122-188125-188127-188-188-188143-1888CONDENSERINLETTUBESHEETANDMATERBOXCOATIN6DIESEL6ENERATOR60VERNORINSTABILITYREACTORCAVITYINFLATABLESEALHAIN6ENLINKStlODPTINDICATIONENHANOENENTREPLACEMENTOFPRESSUREINDPI-18-3REPLACEtiENTOFFLOMTRANStlITTERFT-89-3B1REPLBLDMNCONTROLVLVPOSITIONERStlAIN6ENSUR6ECAPREPLACEtlENTBORICACIDCONCENTRATIONREDUCTS/UTRANSFtlR1A818DIFFRELAYREPLCtlTFUELPOOLPURIFSYSPUtlPStlECHSEALREPLACEtlENTCONDENSATERECOVERYSYSTEtlPUMPStlECHANICALSEALREPLACEtlENTTURBINE6LANDSEALSYSTEtlPUtlPStlECHANLCALSEALREPLACEtlENTSECONDARYSIDEMETLAYUPSYSPUtlPStlECHSEALREPLACEtlENTDUALCEAEXTSHAFTREPLACEtlENTCONDENSERINLETMATERBOXDRAINREACTORCOOLANTPUtlpCASETOCOVER6ASKETREPLACEtlENTSAFETYINJSYSBLANKFLAN6EREtlOVALICMPRESSUREINDICATORUP6RADECONTAINMENTFANCOOLERSHORTTERNRESTORATIONCONDENSATEPOLISHERSYSTEtlPUtlPS.tlECHANICALSEALREPLACEtlENTSTEAN6ENTUBEPLUSDESI6N688VTAPIN6PROCFIREPUtlpBKRO.L.TRIPDEV PLANTCHAN6E/NODREVIEWEDFORPSL1FSARAHENDHENT8NUHBERREVISIONTITLE158-1SS159-1880161-1880162-188165-188167-188178-188171-188175-1880177-188D-188D179-188D188-1880181-1880183-188D188-188D288-188D285-188D218-1880217-188228-1880221-188D/42-1880-188D246-188D8-1RCBEQUIPHATCHDOOROPERDM638INCHSTEAN6ENERATORNOZZLEDANSEALSHAINSTEANNOZZLEBLOCKDRAINPIPEREPLACEHENTTURBINEDRAINVLVREPLACEHENTITTBARTONTRANSHITTERREPLACEHENTHFMTRVLVSSPRIN6RETAINERIN-COREINSTRUHENTTHIHBLEFLANBEREPLACEHENTIN-COREINSTRUHENTTHIMBLEFLAN6EREPLACEHENTHISC.SNUBBERHODIFICATIONSHISC.SNUBBERUP6RADE.ICMLUBEMATERFLAN6E,REPLACEtlENTAFMPIPE8RESTRAINTCORROSIONFEEDMATERFLOMINSTLISTRAN6ECORRECTION.FMRVTECHHANUALUPDATETOREFLECTSNUBBERINSTALLRCPSEALCARTRID6E0-RIN6PARTNUHBERCHAN6ESS/996REPLACEHENTFOR18DIESEL6ENERATORTHROTTLEDVALVECMDLSDEVADDSETPOINTINFOORRPSTOSETPOINTINDEXICCVENDORHANUALUPDATE(1988)688VCABLESPLICESPACIFICVLV28"CHECKVLVHIN6ENATLCH6ZURNSTRAINERHODEL595APARTNUHBERCHAN6EVELANVALVEPARTSHATERIALCHAN6ESHCV3615CHECKVALVEFEEDFROHSHUTDOMNHTEXCH1A1BSEALHATCHN6PORVLOWERSEALBUSHIN66ASKFTV1482,,V1484 PLANTCHAN6E/NODREVIEMEDFORPSL1FSARAHENDHENT8NUNBERREVISIONTITLE285-1880338-1880335-1880eea-985887-985171-985199-985812-986828-986839-986-986832-988e9s-988186-988137-9881eo-9880298-988N/AN/A8-2e-1rPBETAANNUNCIATORINSTMANUALFT-3321CMDCHAN6ESASPOWERFEEDCMDCHAN6EUP6RADEOFNORTHMASTEMATERTREATHENTFACILITYHYPOCHLORITECELLFLUSHSYSTEHHYPOCHLORITESYSTEHINSTRUHENTENHANCEMENTMATERTRTHNTPLTRE6ENTNMSTENEUTRLZTNTANKNOD-BOOSTERPHPMPT6ROUNDEROSIONREPAIRSINTAKECANALDRED6IN6ANDSLOPERESTORATIONBLOMDOMNBUILDIN6RADIATIONHONITORIN6SYSTEH.SINULATORTRAININ6FACILITYPIPIN6TIE-INSSECURITYBLD6SENHANCEHENTSS6BTFMONITORSTORA6ETANKS-VENTSTACKREPLACEHENTS6BLOMDOMNTREATHENTFACILITYSYSTEHPUHPSHECHSEALRPLHT6ENERATORRETAININ6RIN6SREPLACEHENTREPAIROFFIREPROTLINE6"-FP-153REHOVALOFFORNSBL06FROHSECURITYPERIHETERRBfOVALOFGUIDETUBEPLUGGINGDEVICESRELOADSAFETYANALYSIS-CYCLE 8'

PCM583-079ESFASPOMERSUPPLYThischangerequestistocancelthereplacementandrelocationofanewATlpowersupply(ConsolidatedControlsCorporation(CCC))DeviceNo.PS105)proposedundertheoriginalPC/M.TheoriginalATlpowersupply(CCCPartNo.KDD1907(LambdaPartNo.LXs-C-15)willberetainedasintheMAESFAScabinetasaresultofthischangerequest.TheproposedreplacementATipowersupply(CCCPartNo.LXS-D-15-R))willnotbeutilized,asaresultofthischangerequest.ThelocationofthenewATIpowersupplyasproposedundertheoriginalPC/Mwillbecancelled.Therefore,theuseofthemountinghardwareforthenewATlproposedpowersupplywillbecancelledunderthischangerequest.TheoriginalATIpowersupplywillberelocatedunderapprovedPC/M92-185.

PCM583-079PC/M583-79CHANGEREQUEST1ThischangerequesttotheEngineeredSafeguardsFeaturesActuationSystemCabinets(ESFAS)hasnoeffectonnuclearsafetyanddoesnotalterthefntentoftheoriginalsafetyanalysfsforPC/M583-19.<<'"PTheexistingATIpowersupply(LambdaPartNo.LXS-C-15)willbemaintainedancfitslocationwillnotchangeasaresultofthischangerequest.PerformanceoftheexistingATIpowersupplyhasbeenreliableforatleasttenyearsofoperation.Thepowersupplyisusedfortestcircuitanddoesnotperformasafetyrelatedfunction.Thepowersupplyislocatedinamildenvironmentandthereforetherequirementsof10CFR50.49donotapply.TheATIpowersupplywillberelocatedunderapprovedPC/M92-185toimproveventilationwhichwillresultinloweroperatingtemperaturesandprovideimprovedperformance.sincetheESFASIsnotutilizedindeterminingtheprobabilitiesofaccidents.~thischangerequestdoesnotaffecttheavailability,redundancy,capacity,orfunctionofanyequipmentrequiredtomitigatetheeffectsofanaccident.Thischangerequestdoesnotaffectanyothersafetyrelatedequipment.Redundancy,function,orfailuremocfecapacityhavenotbeenchanged,Y"YfailurecoulddirectlyresultInano~ontrolledreleaseofradloactlvematerial.ThepossibilityofequipmentmalfunctionofadifferenttypethananalyzedlntheFSARhasnotbeenincreased.ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenchangedsincethischangerequestdoesnotchangetheperformance,capabilities,oroperatingcharacteristicsoftheESFAS.lnconclusionthischangerequesttoPC/M583-19doesnotInvolveanunrevlewedsafetyquestion.

PCM075-082DIESELGENERATORHIGHCAPACITYTURBOCHARGERINSTALLATIONSYSTEMDESCRIPTION1.0DesignDescriptionThedieselturbochargerssupplyco@pressedairtoboosttheperfor-manceofthedieselengines.Whentheenginesoperatingbelow50Xload,theturbochargersaregeardrivenfromthecrankshaft.TheSt.Luciedieselgeneratorshavebeenexperiencingnumerousturbo-charger'ailuresduetothegeartrain.Electro-motivedieselhasproducedanewhighcapacityturbochargerwithanew,strongergeartrainthatextendstimebetweenscheduledoverhaulsupto1500X.ThenewhighcapacityturbochargerisacommercialgradeitemmanufacturedbyEMDofGeneralMotorstothesamehighqualitystandardsastheoriginalassembly.2.0FunctionThedieselturbochargersuppliescompressedairtothedieselenginetoprovidemorepoweroutputpercubicinchofpistondisplacement.3.0OperationThismodificationwillnotaffectthedieselgenerators'oadcapabilitiesoroperatingcharacteristicsandthusdonotchangetheoperatingprocedures.

FCN075-082SAFETYAHALYSISThischangedoesnotinvolveanunreviewedsafetyquestionbecause:l.a)TheprobabilityofoccurrenceofanaccidentpreviouslyevaluatedintheFSARhasnotbeenaffectedsincethedieselgeneratorsarenotutilizedindeterminingtheprobabilitiesofaccidents.b)TheconsequencesofanaccidentpreviouslyevaluatedintheFSARhavenotbeenchangedsincethismodificationdoesnotaffecttheoperabilityofanyequipmentrequiredtomitigatetheeffectsofanaccident.c)TheProbabilityofmalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthePSARhasnotbeenadverselyaffectedsinceEHDstates,"leighcapacityturbochargershavenotexhibitedanyadverseeffectsfromtheheaviercomponentsevenwhenusedinlocomotiveswhichexperiencerelatively2~3~high"g"forcesduringhardcouplingsandhighspeedcrossovers.Inouropinion,itishighlyimprobablethattheslightturboweightincreasewouldsufficientlychangeresonantfrequenciestocreateseismicsensitivitywhereitdoesnotnowexist.Fromafunctionalstand-point,weexpectidenticalresponsefromthe17.9:1gearratiohighcapacityturboaswereceivedfromthe18:1ratiostandardturbo."I'naddition,thismodificationdoesnotaffectanyothersafetyrelatedequipment.d)Theconsequencesofthemalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthe-FSARhavenotbeenaffectedforthesamereasonsgivein1(c).a)ThepossibilityofanaccidentofadifferenttypethananalyzedintheFSARhasnotbeencreatedsincethismodificationdoesnotaffectanysystemsvitaltosafetyorwhosefailurecouldresultinanuncontrolledreleaseofradioactivematerial.b)Thepossibilityofequipmentmalfunctionofadifferent'ypethananalyzedintheFSARhasnotbeenincreasedforthesamereasonsgivenin1(c).ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenchangedsincethismodificationdoesnotchangetheperformance,loadcapabilities,oroperatingcharacteristicsofthedieselgenerators.0186L

PCM297-177REACTORCAVITYFILTRATIONSYSTEMDuringrefuelingoperations,therefuelingcavityisfilledwi.thwater.Thewaterprovidesprotectionfromradiationgivenoffbyindividualfuelbundlesinadditiontocoolingthemoffkhanthereactorheadisfirstx'emoved,radioactiveimpurities(crud)maybareleasedintothewaterAsaresult,refuelingcavitywaterbccomcsturbid,makingitdifficulttoobserveremovalandreplacementoffuelassembliesbelowthewatex'evel,Inordertoensurewaterclarityintherefuelingcavityduringrefuelingoperations,areactorcavityfiltrationsystemisneeded.Atpresent,thepurificationportionofthefuelpoolsystemperformsthisfunctionduringrefueling;however,itmaynothavesufficientcapacityforensuringthewaterclaritythatisneeded.Thefuelpoolpurificationsystem,locatedintheFHBmaintainsclarityandpuri.tyofwaterint:hefuelpool,refuelingwatertankandtherefuelingcavity.Thepurificationloopconsistsofthepurificationpump(150gpmcapacity),ionexchanger,filter,strainersandsurfaceskimmers,Fuelpoolwateriscirculatedbythepumpthroughafilterwhichremovesparticulateslargerthan5micronsizeandthroughanionexchangertozemoveionicmaterial~Duringrefuelingoperations,'hissamesystemisusedforpurificationoftherefuelingcavity.The3inchsuctionanddischargepipingaxeroutedfromtheFHB,throughthepenetrationroomintheRABandintotherefuelingcavityin-sidetheRCBThissamesystemisalsousedforfillinganddrainingthere-fuelingcavityTheexistingsuctionanddischargennzzlesinsidetherefuelingcavityare9inchesapartandarelocatedatthefarendoftherefuelingcavityawayfromthereactor'vessel.Inordertoprovidebetterfiltration,the"uctionanddischargelocationswouldrequiremoreseparationinorderthatfilte'a8waterhasachancetodispersebeforebeingsuckedbackthroughthefiltrationsystem.Also,thesuctionlinewouldneedtobeextendedtothevicinityofthereactorvesselwhereit<<andothemostgood.Itisatthereactorvesselheadthatwater'firstbecomescontaminatedrequiringremovalsItisalsowherewerequirevisuallyclearwaterThiscontaminatedwaterneedst:obedxawnoutbeforeithasachancetodriftintothefartherreachesof.therefuelingcavity.Sincewemustbeabletodraint:herefuelingcavityusingthefuelpoolpuri-ficationsystem,theexistingsuctionlocationatthebottomoftherefuelingcavitymustbemaintained;However,waalsoneedtohavesuctionatthevicinityofthereact:orvesselheadwhichexistsatahigherelevation.Thezeforc,addi-tionalsuctionlinemusttaaofftheexistingsuctionpipeandbaroutedt:othareactorvesselValveswouldneedtobeprovidedsothatthislinecouldbvalvedoutduringdrainingoperationsInadditiontoroutingadditional.,uctionpipingtothcvicinityofthareactorhead,t:hcwaterclari.tycanbcimprovedbyinstallingascpaxatercactoxcnvi.tyfilt'.rationsystem.Thissystemwouldhnntllcpurificationofthcrefuelingcavityalone,rclicvingt:hcfuelpoolp<<rifi.cat:ionsysteminthcFHBfromt:hisadditionalduty.Withascpar..t:crcactot,cnvt.t:yfiltrntionsyst:cm,wcwouldhavefulltimepurificat:ionofbltcrcfuclingcnvi,tyasopposed.tointcrmittant:purificat:ion<<ntlcrthcoldsystem.Also,ascpnrat:csy:;tomcouldbcinstalledhavinggrcatcrcapacitythant:hcprrscnt.-fuelpoolpurificat:ionsystem,Sincethefua1poolpurificationpumpisrequiredforfillinganddzaining,thereactorcavityfiltrationsystemwouldteaofftheexistingsuctionanddi.schargalinesandwewouldthusmai.ntainthecapabilityoffilteringtherefuelingcavitywiththepurificationportionofthefuelpoolsyst:cm, PCM297-177IThisPC/Hdoesnotconstituteanunreviewedsafetyquestionsorinvolveatech.spec.change.Thereactorcavityfiltrationsystemwilloperateonlyduringplantshutdownwhilerefueling.Theadditionofthissystemshouldreducethetimerequiredforremovalandreplacementofthefuelassemblies.0198L/

PCM089-182REACTORVESSELHEADSHIELDINGABSTRACTTHISREPORTDEMONSTRATESTHEACCEPTABILITYOFTHETEMPORARYR.V.HEADSHIELDANDITSPERMANENTLYATTACHEDSUPPORTSTRUCTURE,ASPROVIDEDBYNUCLEARPOMEROUTFITTERSOFCRYSTALLAKE,IL.,FORUSEINST.LUCIEUNIT1.ITALSOFULFILLSTHEREQUIREMENTFORSUBMITTALOFA"DESIGNPACKAGE"ASREQUIREDBYFLORIDAPOWERANDLIGHTSPECIFICATIONFORENGINEERINGPROCURMENT,ANDINSTALLATIONFORPC/M89-82,DATEDOCTOBER,1982.IY.SAFETYANALYSISThereactorvesselheadshieldingconsistsofleadwoolblanketshungaroundthereactorheadduringplantoutages.Theblanketsarehungfromasupportsystemwhichispermanentlyattachedtothereactorvesselheadliftrig.Theshieldingsystemdoesnotperformanuclearsafetyrelatedfunction.Ithasbeendesignedtowithstandallapplicableloadsspecifiedintheoriginalplantdesign.ANUREG0612analysishasbeenperformedtoincludetheadditionalloadingoftheshieldingsystemonthereactorheadliftrig.TheanalysisshowsthatallNUREG0612requirementsaresatisfied.ApropriateQAandQCrequirementshavebeenidentifiedaswellasprocedurestoassuretheinstallationandusewillconformtothedesigncriteria.Theprobabilityofoccurrenceortheconsequencesofadesignbasisaccidentormalfunctionofequipmentimportanttothesafetyoftheplant,previouslyevaluatedintheFSAR,hasnotbeenincreased.Thereisnopossibilityofaccidentormalfunctiondifferentthanthosepreviouslyevaluated.Also,therearenochangestothetechnicalspecificationoftheplant.Therefore,itcanbeconcludedthattheadditionofthereactorvesselheadshieldingsystemdoesnotposeanunreviewedsafetyquestionpursuantto10CFR50.59.~'~lqy~

PCM114-182STLUCIEPLANT-UNIT1TURBINESUPERVISORYINSTRUMENTATIONINTRODUCTIONTheturbineisaWestinghousetandemcompoundfour-flowexhaust1800RPMunitvithonehighpressureandtvolovpressureelements.TheACgeneratorandbrushless"typeexciteraredirectlyconnectedtotheturbinegeneratorshaft.Theunitisprovidedwiththrottlevalvesteamchestassemblieslocatedoneachsideofthehighpressureturbinecasing.Thestructuralshapesofthecasingsandtheirmethodsofsupportarecarefullydesignedtoobtainfreebutsymmetricalmovementsresultingfromthermalchanges.TurbineSupervisoryInstrumentation(TSI)isdesigaedtoprovideoptimuminsightintothemechanicalintegrityoftheturbinegenerator.Thissystemutilizesacombinationofmonitoring,recordingandloggingtocollectdataontheoperationoftheturbine.TheTSIsystemisusedtosensesubtlechangesintheoperationoftheturbinegenerator.Theitemslistedbelowareconsideredveryimportantinthecontrolofsafestarting,loadingandmonitoringoftheturbine:h.B.C.D.E.P.G.H~I.RadialVibrationandVibrationPhaseAngleRotorEccentricityDifferentialExpansionThrustBearingMonitorCaseExpansionTurbineSpeedandAccelerationInstrumentationRacksandCableTerminationsMimicDisplayaadAnnunciationLightsPRobes,CablesandConduitInstallationTheBentlyNevadaTSIsystemvillultimatelyreplacetheexistingWestinghouseTurbineSupervisoryequipmentsHowever,thereplacementvillbeaccomplishedintwo(2)stages.ThefirststageisdesignedtoinstalltheBentlyNevadasystemvithoutremovingtheexisitngWestinghouseequipment.WhilethesecondstagevillbetodisconnecttheWestinghouseequipmentandtocompletetheconnectionofthenewsystem.Includedinthefirstetageofimplementationaretheinstallationofthebrackets,theprobes,theconduits,theelectricalboxes,theTSIcabinet,andtheannunciatormimicdisplayfortheBentlyNevadasystem.TheexistingWestinghousethrustbearingprobelocatedatthecouplingepacerbetveeathejackshaftandthelovpressure(LP)turbine1BistobereplacedwithnevBentlyNevadaprobes.ThemountingbracketfortheWestinghouseprobevillbemodifiedtoacceptthenewBentlyNevadarobes.TheexistingBentlyNevadathrustbearingprobesatthealanceringbeinglonger,couldaotberelocatedandthereforevillberemoved.

PCM114-182SAFETYANALYSISWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.Theturbinesupervisoryinstrumentationisnon-safetyrelatedandnon-seismic.Themodificationisbeingimplementedforaddedprotectionoftheturbinegeneratorandtoreducepotentialunscheduleddowntime.Itimprovesplantreliabilitybutdoesnototherwiseaffecttheexistingturbinedesign.AnevaluationfortheimpactoftheaddedmassesontheRTGB-101andthechangeinthedynamiccharacteristicsoftheRTGBwillbemadebyCivilDept.Itwasfoundthattherequiredmodificationhasnosignificantimpactonthedynamiccharacteristicsoftheboard.TheTSIcabinetisnon-safetyrelatedbutislocatedontheRABelevation43.0levelinthevicinityofsafetyrelatedequipment.Thecabinetwasseismicallyanalyzedanditwasdeterminedthatitwillmaintainitsstructuralintegrityduringaseismicevent.Furthermorethedisplacementaresufficientlysmalltoprecludeinteractionwithad)scentequipment.TheimplementationofthisPCMdoesnotrequireachangetotheplanttechnicalspecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasisthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCNisnotrequired.0186L

THERMALSHIELDREMOVAL-PHASE3PCM355-183SYSTEMDESCRIPTION'.0FunctionInspectionofthecoresupportbarrel(CSB)andthermalshield(TS)revealeddamageattheCSBtoTSconnection.PhaseIIIoftheThermalShieldRemovalallovsthethermalshieldsegmentstoberemovedfromtheUnitflrefuelingcanalforeventualoffsiteshipment.2.0DesiDescritionRemovalof,.theTSfromtheUnit01refuelingpoolwillinvolvethefollovingstepsc1.Loading24"videx6'ongTSsegmentsintoth>>transfershieldintheUnittlrefuelingpool.2.TransportofthetransfershieldwithcontentsoutoftheUnitflcontainmentandontoatruckvhichwilltransporttheshieldtoUnitt2viaaprescribedroute.3.ThetransfershieldwillbeliftedfromthetruckandplacedintheUnitf2caskhandlingareawherethetransfershieldcontentsvillbeputintoa.shippingcaskforofisitetransport.3.0~OeraalanTheoperationofallequipmentutilisedinthiseffortshallbeperformedbyaqualifiedoperator.0186L

PCM355-183SAFETYANALYSISThe<<transportofthermalshieldsegmentsdoesnotinvolveanunreviewedsafetyquestionbecausecl.(a)TheprobabilityofoccurrenceofanaccidentpreviouslyevaluatedintheFSARhasnotbeenaffectedsinceUnit01willnotbeoperatingwhilethetransferistakingplaceandnoworkvillbeperformedinorovertheUnittlspentfuelpool.WorkbeingperformedinUnit02isinthecaskhandlingareaandvillnotaffectoperationofUnitf2aathereisnofuelintheUnitt2spentfuelpool.Thehaulroutehasalreadybeenevaluatedforheavierloadsthanafullyloadedshield.(b)TheconsequencesofanaccidentpreviouslyevaluatedintheFSARhavenotbeenaffectedsincetheshielddropaccidentwillnotresultinoffsitedosesinexcessofthoseaccidentspreviouslyevaluated.(c)Theprobabilityofamalfunctionofequipmentimportanttosafetyhasnotbeenaffectedsincethefailuremodesassumedasaresultofthetransferprocesswillnotimpactsafetyrelatedequipmentoperation.(d)TheconsequencesofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARremainunchangedbasedonitemla,lb,andlcabove.2.(a)ThepossibilityofanaccidentofadifferenttypethananyanalysedinthePSARhasnotbeencreated.Theresultsoftheanalysisforashielddropinexcessofllfeetshowedthatcorrectiveactioncouldbetakenwhilestillmaintainingoffsitedoseswithinafractionof10CFRNOlimits,thusremainingwithintheboundsofpreviousanalyses.(b)ThepossibilityofamalfunctionofequipmentimportanttosafetyofadifferenttypethananyanalyzedinthePSARremains,unchangedforthereasonsoutlinedabove.3.Thetransportofthethermalshieldhasnoeffectonthemarginofsafetyasdefinedinthebasisforanytechnicalspecification.0186L

PCM177-184ROSEMOUNTTEMPERATURETRANSMITTERREPLACEMENTINTRODUCTIONThisPC/Misfortheinstallationofnineteen(19)newRochestermodeltemperaturetransmitterstoreplacetheexistingRosemountmodels.TheexistingRosemountmodel442temperaturetransmittersarenolongeravailablefromRosemount.AcomparablemodelbyRochesterInstrumentSystemswillsatisfytheoperationalconditionsaswellasmeetthesafety/seismicrequirements.Thismodificationwillalsoincorporatetheimplementationoftwo(2)signaltransmitterstoincreasetheloadcapabilityoftwo(2)transmitterloopsmentionedinthesystemdescription.SAFETYANALYSISWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincrased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferentytypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationsisreduced.ThesenewRochestermodeltemperaturetransmittersarelocatedinamildenvironmentandareseismicallyqualifiedtoIEEE-344-1975.Inaddition,theseunitsaremanufacturedtotheRochesterQualityAssuranceProgramfornucleardevices;thereforemeetingtraceabilityandreportabilityrequirements.ThisPC/Misforreplacementofnineteen(19)transmitters,thusprovidingamoreaccurateandreliablemodel.Therefore,thismodificationwillnotincreasetheprobabilityoftheoccurenceofanyaccident,whetherpreviouslyevaluatedorofadifferenttypethanpreviouslyevaluatedandwillnotreducethesafetyoftheplant.ThisPC/Mdoesnotreducethemarginofsafetyasdefinedinthebasisofanytechnicalyspecification,nordoesitrequirearevis&nofatechnicalspecification.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasisthatthischangedoesnotinvolveanunreviewedsafetyquestion,thereforepriorCommissionapprovalisnotrequiredforimplementationofthisPC/M.

EDGSUBSYSTEMFLOWDIAGRAMSPCM039-185ModifioationD~eaoritionThisPC/MreleasesthenewDieselGeneratorSubsystemFlowDiagramstothesite.Thefollowingactivitiesmustbecompletedbeforethenewflowdiagramscanbeissuedaspermanentplantdrawings:1.)Allvalvesandinstrumentsmustbetaggedinthefieldasperthenewflowdiagrams.2.)Affectedoperatingproceduresmustbereviewedtodetermineifrevisionisrequiredtoreflectthenewtagnumbersorflowdiagramnumbers.SafetAnalsis1aWithrespecttotheprobabilityofoccurrenceofanaccidentpreviouslyevaluatedintheFSAR:PlowdiagramsarenotconsideredinevaluatingFSARaccidents.lb.WithrespecttotheconsequencesofanaccidentpreviouslyevaluatedintheFSAR:FlowdiagramsarenotconsideredinevaluatingFSARaccidents.,1c.Withrespecttotheprobabilityofmalfunctionofequipmentimportanttosafetypret!iouslyevaluatedinFSAR:Plowdiagramsarenotconsideredindeterminingtheprobabilitiesofsafetyrelatedequipmentmalfunctions.1d.WithrespecttotheconsequencesofmalfunctionofequipmentimportanttonuclearsafetypreviouslyevaluatedinthePSALM:Plowdiagramsarenotconsideredindeterminingtheprobabilitiesofsafetyrelatedequipmentmalfunctions.2e.WithrespecttothepossibilityofanaccidentofadifferenttypethananalyzedintheFSAR'-FlowdiagramsarenotconsideredinevaluatingFSARaccidents.2b.WithrespecttothepossibilityofamalfunctionofadifferenttypethananalyzedintheFSAR:Flowdiagramsarenotconsideredindeterminingtheprobabilitiesofsafetyrelatedequipmentmalfunctions.3.Withrespecttothemarginofsafetyasdefinedinthebasisforanytechnicalspecification:Flowdiagramsdonotimpacttechnicalspecificationsafetymargins.Basedontheabove,thenewflowdiagramsandthetagging/retaggingofdieselgeneratorvalvesandinstrumentsaredeterminednottoinvolveanunreviewedsafetyquestion.Therearenosystemmodificationsinvolved.

PCM090-185STLUCIEUNITIREPLACEMENTOFLOADWEIGHING.SYSTEMFORREFUELINGANDFUELTRANSFERMACHINEShBSTRACTThisengineeringdesignpackagecoversthereplacementoftheload~eigningsystemfortherefuelingandfueltransfermacnines.Theex>>tingsystemismanufacturedbyWCDillonwhichnolongerhavespare.partsavailable.Tneoriginalequipmentmanfacturer,PARSysemCorporation,'willdesign,supplyandinstallthenewloadweighingsystem.AsdiscussedinUFSARChapter9,thissystemisdesignedforsafehandlingandstorageoffueltoandfromthereactor.Tneequipmentisnormallyusedat18monthintervalsforaperiodofapproximatelythree(3)weeksduringwhichtimeitmustoperatecontinuouslywithoutmaintenanceorservice.Alsothissysemmustbeabletowithstandloadingsinducedbythedesignbaseearthquake.Therefore,thisPCMisclassifiedas"+alityRelated".Thisitemdoesnotrequirerevisiontotneplanttechnicalspe"ifications,nordoesitmeetthecriteriaforanunreviewedsafetyquestion.Tnerefore,pursuantto10CFR50.59thismodificationcanbemadewitnoutpriorcommissionapproval.0186L pCH090-185SAFETYEVE.UATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedxnthesafetyanalysisreportmaybeincreased;or(ii)ifapossiblilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.ThemodificationdescribedinthisPC/Mreplacesexistingcomponentsassociatedwiththerefuelingmachine.Tnerefuelingmachineisonlyrequiredtooperateforapproximatelythree(3)weeksateighteen(18)monthintervalsasperUFSARSection9.1.4.2.Thissystemisnotrequiredfornormaloperationoftheplant.Itisonlyrequiredforfuelingandremovaloffuelfromthereactor,thereforethisequipmentisnotrequiredforsafeshutdownoftheplant.WithregardtospentfuelhandlingaccidentsasdescribedinVFSARSection15.4.3,theresultsofthefuelhandlingaccidentarenotaffectedbythisequipmentchangeout.Thedigitalreadoutwillensurethatwhenremovingafuelassemblyitisnotdamagedbyexcessiveliftingforces.Thedigitalscaleshouldinfactprovidemoreaccurateinformationtotheoperatortobetterprecludethisevent.Thenewequipmenthasbeenseismicallyanalyzedtoprecludeitsdisalignmentduringaseismicevent.Therefore,thiswillnotimpa"tthe"lightloads"accidentanalysis.Thefailureofthiscomponent,nottofunction,wouldprecludefurtherfuelmovementuntilitsrepair.Redundancyofthissystemisnotrequired.Inassomuchthatthissystemisnotrequiredtoshutdownthereactor,coolthecoreorcoolanothersafetysystemorthereactorcontainment(afteranaccident),norisitpartofanysystemthatreducesradioactivityreleasedinanaccident.Note,onlytheseportionsofasystemthataredesignedprimarilytoaccomplishoneeftheabovefunctions,orthefailureofwhichcouldpreventaccomplishing,oneoftheabovefunctions,isdesignated'safetyrelated.Thesystemisrequiredtowithstandloadingsinducedbythedesignbasesearthquake.Therefore,thisPCMisclassified"QualityRelated".TnemodificationstotneloadcellsupportsshallbedesignedandanalyzedbyPARSystemsastomaintaintneseismicintegrityoftheequipment.TneresultsoftheiranalysiswillbereviewedbyEbasco.TneimplementationofthisPC/Mdoesnotrequireachangeoftheplantspe"ifications."Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired."0186L STLUCIEUNlT41ESFASPOWERSUPPLYPCM092-185ThismodlficatlonprovidesforthereplacementofESFASmeasurementcabinet'sInstrumentlooppowersupplieswhicharenolongeravailablefromtheorlglnalequipmentmanufacturer.Thesesuppliesfurnishthesensorcurrentforcontainmentpressure,andrefuelingwatertanklevel.,ThischangeperformsanuclearsafetyrelatedfunctionandispoweredfromClass1Esafetysources.ThisPC/Mdoesnotinvolveasunreviewedsafetyquestion.a.sincetheESFASisnotutilizedindeterminingtheprobabilitiesofaccidents.b.thismodificationdoesnotaffecttheavailability,redundancy,-capacity,orfunctionofanyequipmentrequiredtomitigatetheeffectsofanaccident.-cThismodificationdoesnotaffectanyothersafetyrelatedequipment.d.~~~Redundancy,function,orfailuremodecapacityhavenotbeenchanged.Bethismodificationdoesnotaffectanysystemsvitaltosafetyorwhosefailurecoulddirectlyresultinanuncontrolledreleaseofradioactivematerial.f.ThepossibilityofequipmentmalfunctionofadifferenttypethananalyzedintheFSARhasnotbeenincreased.ThemarginofsafetyasdefinedlnthebasisforanyTechnicalSpecificationhasnotbeenchangedsincethismodificatiodoesnotchangetheperformance,capabilities,oroperatingcharacteristicsoftheESFAS.InconclusionthischangedoesnotInvolveanunreviewedsafetyquestion.0186L REPLACEMENTOFVALVESOLENOIDSpCM177-185OeINTRODUCTIONThepurposeofthisPC/Mistoreplacetwelve(12)existingASCOandtwo(2)AVCOvalvesolenoids,nolongermanufactured,with"Qualified"ASCOsolenoidNP-8316Seriesonvariousvalves.ThereplacementsolenoidsareenvironmentallyqualifiedIEEE-323-1974,IEEE-344-1975,andIEEE-382-1972.Alsofour(4)oftheexistingASCOsolenoidvalveseatsaretoberebuilt,usingASCOsparepartskitcomponents(Elastomers)SAFETYANALYSISWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59Aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestionl(i)iftheprobabilityofoccurenceorortheconsequenceofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationisreduced.This.modificationdoesnotinvolveanunreviewedsafetyquestionandthefollowingprovidesthebasesforthisconclusion.ThereplacementofASCOvalvesolenoidshavebeenqualifiedtoIEEE-323-1974,andIEEE-383-1972requirements.ThequalificationdocumentationpackagehasbeenprovidedbyASCOviatheirreportAQS-21678/TRRevA.Thequalificationtestprogramsimulatedtheeffectsoflong-termoperationundernormaloperatingconditionsandtheeffectsofDesign'asisAccident.(DBA)theeffectsincludedexposuretotheenvironmentalextremesoftemperature,pressure,humidity,radiation,vibration,andchemicalspray.Withadequatemargin,thequalificationprogramdemonstratedthattheequipmentcanperformitsspecifiedfunctionundertheanticipatednormaloperatingandDBAconditions.ThereplacementofASCOvalvesolenoidsareone-for-onereplacementoftheexistingASCOsolenoids.FortheAVCOsolenoids,valvesFCV-25-2andFCV-25-5,theadditionoftubingfittingsfortheairsupplysystemisrequired.However,thereisnoeffectontheseismicqualificationofthosevalvesduetotheadditionalweightoftherequiredfittings.ThereplacementofASCOvalvesolenoidsfortheCCWisolationvalvesisalsoaone-for-onereplacementoftheexistingASCO.solenoids.There"placementofthesesolenoidsenhancetheexistingvalvesbyinstallingenvironmentallyqualifiedsolenoids.TheimplemetationofthisPC/Mdoesnot,requireachangetotheplantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevalua-tionwhichprovidesthebasesthat,thiscnangedoesnotinvolveanunre-viewedsafetyquestion,therefore,priorCommissionapprovalisnotre-quiredforimplementationofthePC/M.0186L STLUCIEUNITS1R2peg204-185ICWBACKUPLUBEWATERBACKFLOWPREVENTOR(REANLN<5<1)ABSTRACT'hisEngineeringPackagecoversreplacementoftheexistingICWservicewaterbackuplubewatersupplybackflowpreventorwithonethatiscurrentlymanufactured.Theexistingbackflowpreventorvendornolongermanufacturesthesethussparepartsaredifficulttoobtain.Thispackageisclassifiedasnon-seismic,nonnuclearsafetyrelated.SAFETYEVALUATIONWithrespecttoTitle10ofthecodeofFederalRegulations,Part50.59,aproposedchangeshaQbedeemedtoinvolveanunreviewedsafetyquestion:(1)iftheprobabilityofoccurenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iioifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationsisreducedThesubjectmodificationprovidesforreplacementoftheexistingbackflowpreventor.Thisbackflowpreventorensuresthatseawaterdoesnotbackflowintotheservicewatersystemthuscontaminatingthedomesticwatersupply.Withrespectto10CFR50.59,failureofthisbackflowpreventor:(1)doesnotincreasetheprobabilityofan'accidentormalfunctionofequipmentimportanttosafetysincethesupplyisseparatedfromailsafetyrelatedequipmentbyadoublecheckvalveclassbreakandislocatedremotelywithrespecttosuchsafetyrelatedequipmentandcannotfallonorhitsuchequipment;or(2)doesnotcreatepossibleaccidentscenariosnotpreviouslyaddressedbytheSafetyAnalysisReportsinceitfunctionsonlyasasystemenhancementanddoesnothavetofunctioninanypostulatedaccidentconditions;or(3)doesnotaffectorrequirechangestotheTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasisthatthischangedoesnotinvolveanunreviewedsafetyquestion.ThereforepriorcommissionapprovalisnotrequiredforimplementationofthisPC/5I.AdditionallypertheFSARSection9,thisbackuplubewatersupplyisnotrequiredtoperformanysafetyrelatedfunctionsnoristhemodificationwithinanysafetyrelatedorseismicboundaries.Thereforethemodificationisconsideredtobenonwafetyrelated,QualityGroupD.0186L PCM028-186ST.LUCIEUNXT1ComponentCoolingWaterPumpJournalBearhgShellMaterialClumge(REASLN-421-Ss-S)ThisengineeringpackagecoversreplacementoftheexistingcastIron'journalbearingshellsonthecomponentcoolingwaterpumps1A,1B81Cwithshellsmadeofcarbonsteel.Theexistingcastironshellsarenolongeravailableandthemanufacturer'sreplacementpartIsthecarbonsteelshell.AsaddressedintheSafetyEvaluation,thismodificationisconsiderednuclearsafetyrelated.Basedonthe10CFRSO.S9review,ithasbeendemonstratedthatthischangedoesnotinvolveanunreviewedsafetyquestion,andthechangewillnotaffectplantsafety.Additionally,nochangeisrequiredfotheTechnicalSpecifications.Accordingly,priorNRCapprovalisnotrequiredforimplementationofthisdesign.SAFETYEVALUATIONTheUnit1ComponentCoolingWaterpumpsarenuclearsafetyrelatedandareclassifiedasASMESectionIII,Class3QuaHtyGroupCcomponents.TheyarerequiredtoprovideaheatsinkforsafetyrelatedcomponentsassociatedwithreactordecayheatremovalforsafeshutdownorLOCAconditions.ThejournalbearingshellmaterialchangeaffectsbothjournalbearingsintheIA,1Band1Cpumps.Failureofthebearingshell(regardlessofmaterialutilized)andrespectivejournalbearingwillresultinfailureofthecomponentcooHngwaterpump.However,failureofasinglepumphasbeenpreviouslyevaluatedandhasbeenaccountedforintheComponentCooHngWaterSystemdesignbasesasidentifiedintheFSAR.MeasuresexisttoensureadequatedecayheatremovalforsafeshutdownorLOCAconditionsshouldasinglepumpfaILSincethenewshellpartsareinternaltothebearinghousing,failureofanadditionalcomponentcoolingwaterpumpsimultaneoustothefirstpumpfailureisnotpossiblebasedonsinglefailurecriteria.Inaddition,sincethenewshellmaterialisfunctionallyequalorbetterthantheexistingcastironmaterial,theprobabiHtyofpumpfailureremainsunchangedBasedontheaboveevaluationandinformationprovidedintheDesignAnalysis,itcanbedemonstratedthatanunreviewedsafetyquestionasdefinedby10CFR50.59isnotcreated.SincenootheraccidentbeyondwhathasbeenpreviouslyaddressedintheFSARhasbeenidentifiedandnoothersafetyrelatedequipmentorcomponentsareaffectedasaddressedinthefailuremodesanalysigtheprobabilityofoccurenceofanalyzedaccidentshasnotbeenincreased.Thereplacementisequalorbettertotheequipmentreplaced.Nonewaccidentsormalfunctionsareintroducedasaresultofthisdesignchange.Additionally,themarginofsafetyasdefinedin.theTechnicalSpecificationshasnotbeenreducedandnoTechnicalSpecificationchangesarerequIred.Thereforeanunreviewedsafetyquestiondoesnotexist.SincethismodificationdoesnotInvolveanunreviewedsafetyquestionanddoesnotchangeoraltertheTechnicalSpecifications,thischangeisacceptablewithrespectto10CFR50.59anddoesnotrequireNRCapprovalpriortoImplementation.

Qo'ABSTRACTSTLUCIEPLANT-UNITNO1INSTRUMENTAIRUPGRADEREA-SLN-481PCM050-186ThisEngineeringPackage(EP)isfortheinstallationof2newaircompressors,2newdesiccantairdryersandremovaloftheexistingdesiccantairdryer,afterfilterpackageandrefrigerantairdryerwhichdonothavesufficientcapacitytoaccomodatethenewcompressors.Oneofthetwonewaircompressorsandonenewairdryerwilloperateandtheotherwillserveasastandby.Theexistingcompressorswillremainasbackup,especiallyforlossofoffsitepower,sinceonlythesecompressorscanbeloadedonthedieselgenerator.Inaddition,thebackupairsupplytotheMSIVsandFCV9011andFCV9021willberemovedsincethenewcompressorswillbeabletosupplyadequateairflowattherequiredpressure.ThisEPisclassifiedasNon-SafetyRelatedsincetheinstrumentair(IA)systemcompressorsandassociatedequipmentperformsnosafetyfunction.ThesafetyevaluationhasdeterminedthatthisEPdoesnotconstituteanunreviewedsafetyquestionandimplementationoftheEPdoesnotrequireachangetothePlantTechnicalSpecification.Therefore,priorNRCnotificationforimplementationofthisEPisnotrequired.ThisEPhasnoimpactonplantsafetyandoperation.TheSupplement1providesreviseddesignbases/analysis,safetyevaluation,operationaaintenanceguidelinesandFSARchangepackage.Althoughthesafetyevaluationhasbeenrevised,theoriginalresultsofevaluationasstatedaboveremainunchanged.SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulation,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.ThisEPisfortheadditionoftwo100Xcapacitynewcompressors,twonewdesiccantairdryersandremovaloftheexistinglowcapacitydesiccantdryer,afterfilterpackage,refrigerantairdryerandsupplementalairbottleracksandassociatedpiping.0186L

PCM050-186afetyEvaluation(Continued)PailuzeoftheiastrumeataircompxessoreaadcomponentsresultinginlossofIAaadconsequentaffectsasstatedfathePShRSubsection9.3.1.3havebeenreviewed.Thfsmodificationdoesnotaddanynewfailuremodesforthesafetyrelatedairoperatedvalves.However,exlstfagsolenoidvalves,withoutregulators,whosemazimumoperatingpressuredifferentialcapacftyislessthanU.5psiwillbereplacedviaDesignEqufvalentEngineeringPackage(DEEP)No154-188D.Mal&mction,ifaay,ofthesesolenoidvalveswillleadtothePailSafemodeoftheprocessvalves.TheIhsystemdesignpressureandtempex'aturedownstreamoftheIhaftezcoolerremainunchanged,thereforethereisnoconcernforthevalveactuators.Thismodificationisthex'eforeclassifiedasnonnuclearSafetyQud.ftyGroupDandnonmlase1E.TheincreaseinZhrequirementsfrom155SCRMto400SCFMaadpressurefrom90-100peigto105-U.5psfg1sbasedonFPLstudiesfortlatrequixementoftheIA.RemovalofthesupplementalairbottlerackswhfcharctiedintotheaccummulatorstomaintaiatheMSIVsandfeedwaterPCVsairsystempressurebetween100-105psigisconsideredacceptable'becausethenew'ompressors(1CandlD)willbeabletopxovideadequateinstrumentaizflowattherequiredpressure.Basedontheabove'descriptioa,themodificatfonincludedfnthisEPieconsideredtobenon-safetyrelated.ThfsEPdoesnotinvolveanunreviewedsafetyquestion,aadfollowingarethebasesforthisJustification'.(1)Theprobabilityofoccurxenceortheconsequencesofanaccfdentormalfunctionofequipmentimportanttosafetypreviouslyevaluatediathcsafetyanalysisreportisnotincreased.Theinstrumentairsystemcompressorsandassociatedequipmentax'enotuseddirectlyinanysafetyanalysisforaccideatsozmalfunctionofequipmentandassuchazenoa-safetyrelatedandwillhavenoeffectonequipmeatvitaltopleatsafety.(ii)Thepossibilityforanaccidentormalfunctionofadifferent.typethananyevaluatedpreviouslyfnthesafetyanalysfsreportisnotcreated.Thecomponentsinvolvedinthismodificationhavenosafetyrelatedfunctionandnochangeshavebeenmadetotheaormaloperationaldesignofthesystemwiththecompressors1Cand1Dfaoperatfon.InthfsmodetheIAcompressozsXAand1BdischargevalvesV18109andV18119azeclosedtopreventIAlcakagcviathesecompressors.Similarly,whenevertheIkcompxessorsLLand1Barercquircdtooperate,valveV18586isclosedtopreventIhleakageviacompressors1Caad1D(iii)ThemarginofsafetyaedefinedinthebasesforanyTechnicalSpec1ficationisaotaffectedbythisPCM,sincethecomponentsfnvolvediathismodificationarenotincludedinthebasesofanyTcchnicalSpecfficatioa.

STLUCIEUNIT1pCM052-186UpperGuideStructure(UGQLiftRigRepairREA-SLN-86-010ABSTRACTThisengineeringpackagecoverstherepairsandmodificationtothedamagedUGSLiftRig.TheliftrigwasdamagedonNovember6,1935whenoneofitsattachmentpointsfailedduringaUGSliftoperation.AlthoughtheUGSLiftRigisnonsafety-related,itsfailurecouldresultindamagetonearbysafety-relatedequipment.Therefore,quality-relateddesignrequirementshavebeenimposedtoassureQCInspectionoftherepairsandmodification.TheimplementationofthisPCMdoesnotposeanyunreviewedsafetyquestionsnordoesitaffectanysafety-relatedequipment.Slement1Thissupplementdocumentsthe"as-built"configurationoftherepairedUGSliftrig.Itincludestheactualcolumnchorddimensionsandincorporatestheminordesign.changesthatweremadeinthefieldduringtherepaireffort.Theoriginalsafetyevaluationhasbeenreviewedfortheimpactofthechangesaddressedbythissupplementandithasbeendeterminedthatitremainsvalid.SafeEvaluationThisengineeringpackageprovidesfortherepairandmodificationoftheUGSliftrigtocomplywithitsoriginalfunctionalrequirements.TheUGSliftrigisnotasafety-relatedpieceofequipmentandisonlyusedduringrefuelingoperationswhentheplantIsinthecoldshutdownmode.SincefailureoftheliftrigwhileliftingtheUGScouldresultinaloaddropontothereactorandirradiatedfuelassemblies,thiscomponentisconsideredimportanttosafety.Forthisreason,quality-relateddesignrequirementshavebeenimposedtoassureQCinspectionoftherepairsandmodification.ThemodifiedliftrighasbeenstructurallyreanalyzedfordeadandseismicloadssubjecttotherequirementsofNUREG0612,ANSIN14.6,andtheapplicableASMEandASTMcodes.Theresultsofthisanalysisdemonstratesthatthenewandexistingcomponentsareallwithinallowablestresslevels.Thecontainmentheatsink,hydrogengeneratingsource,andfreevolumeanalysesdescribedInFSARSection6.2arenotaffectedbythismodification,sincetheliftrigreplacementpartsarethesameasorsimilartothoseinstalledoriginally.ThismodificationdoesnotchangeanyassumptionsmadeorconclusionsdrawnIntheSt.LucieFSAR,andthereisno'newfailuremodeintroducedthathasnotbeenpreviouslyevaluatedintheFSAR.However,FSARFigure9.1-8mustbeupdatedtoreflecttherepairsandmodificationtotheliftrig.Fortheabovereasons,therepairsandmodificationstotheUGSliftrigwillPotincteasetheprobabilityofoccurrencenortheconsequencesofadesignbasisaccidentormalfunctionofequipmentImportanttothesafetyoftheplant.Additionally,therewillcontinuetobenopossibilityofanaccidentormalfunctiondifferentthanthosealreadyevaluatedIntheFSAR.Finally,themarginofsafetyasdefinedinthePlantTechnicalSpecificationshasnotbeenreduced.ItIsthereforeconcludedthatthismodificationdoesnotposeanunreviewedsafetyquestionspursuantto10CFR50.59anddoesnotaffectanyTechnicalSpecifications.

PCM07I4-186msmACrHEATERDRAINPUMPDEMINERALIZEDWATERSUPPLYThisdesignpackageprovidestherequiredengineeringforaddingpermanentpipingfromthedemineralizedwatersystemtotheUnit1heaterdrainpumps'echanicalseals.Thepipingwillmakeavailabletothesealsthenecessarybackupflushingwatermeetingtheappropriatechemistryrequirements.Thebackupwatersourceisrequiredduringinitialplantstartupwheneverthepumpssitidle.Basedonthefailuremodesanalysisand10CFR50.59review,thismodificationdoesnotimpactanysafetyrelatedequipmentandisnotrelieduponforanyaccidentpreventionormitigation.ThusitdoesnotconstituteanunreviewedsafetyquestionandiscorrectlyclassifiedasNon-NuclearSafetyRelated.Implementationofthismodification,therefore,doesnotrequirepriorNRCapproyal.Sulement1ThispackagerevisionprovidesvalvedrawingsforvalvesaddedbythisFC/Mandmodifiestheexpirationdatetoreflectthecorrectformat.The.scopeofworkspecifiedbythisEngineeringPackagehasnotbeenaffectedbythisrevision.Thesafetyclassificationandthesafetyevaluationasstatediscorrectandisnotimpacted.ShFETYEVhLUhTIONTheUnit1HeaterDrainPumpsarelocatedinaNon-NuclearSafetyRelatedsystemandassucharenotrequiredtofunctionduringanyexistinganalyzedaccidentscenario.Therefore,modificationstothesepumpsaffectonlyNon-NuclearSafetyRelated,QualityGroupDequipment.Basedonthefailuremodeanalysis,failureofthedemineralizedwatersupplypipingcouldresultonlyinfailureoftheheaterdrainpumps.Sincethepipingandcomponentsarelocatedremotefromanysafetyrelatedequipmentorcomponents,failureofthisequipmentwillnotinhibitoperationofanysafetyrelatedequipmentorcornponents.iBasedontheaboveevaluationandinformationsuppliedinthedesignanalysisitcanbedemonstratedthatanunreviewedsafetyquestionasdefinedin10CPR50.59doesnotexist.oTheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.Sincethisdesignchangedoesnotalteroraffectequipmentusedtomitigateaccidents,theprobabilityofoccurrenceofanalyzedaccidentsremainsunchanged.oThepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreporthasnotbeencreated.ThereisnonewfailuremodeintroducedbythischangethathasnotbeenevaluatedpreviouslyintheFSAR.oThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationshasnotbeenreduced.ThischangehasnoaffectonanyexistingTechnicalSpecifications.

PCM077-18610CFR50.59EQLISTREVISIONABSTRACTThisengineeringdesignpackageprovidesthevehicleforupdatingseveralareasofequipmentqualification.Thispackageincludescorrectionstothe10CFR50.49list,changesinmaintenancerequirements,andvariousdocumentationcorrections.ThisdesignpackageisconsiderednuclearsafetyrelatedbecauseitaffectsequipmentfaDingunderthescopeof10CFR50.49.ThispackagedoesnotrepresentanunreviewedsafetyquestionsinceitdealsstrictlywithenhancingthepresentdocumentationusedtoqualifyequipmentatSt.Lucie.SafetEvaluationThisengineeringdesignpackageprovidesforseveraldocumentationchangestothepresentStLucieUnitNo.1'sequipmentquaHficationdocumentation.Thisdocumentationwillaffectthefutureprocurementofvarioussafetyrelatedcomponentsandassistinvalidatingthecomponents'bilitytofunctionduringadesignbasisaccident.Therefore,thisdesignpackageisconsideredsafetyrelate*Thedocumentationchangesaddressedin,thispackagerangefromcorrectionsoftypographical.errorsonthe10CFR50.49listtoreviewsofavendor'sequipmentqualificationtestreport.Noneofthechangesrequirephysicalmodificationtoanyplantsystem.Theydohowever,affectthefuturemaintenanceofvariousinstruments.Basedontheaboveandtheinformationsuppliedinthedesignanalysisitcanbedeomonstratedthatanunreviewedsafetyquestionasdefinedby10CFR50.59doesnotexist.Sincethischangedoesnotalteranyequipmentusedtomitigateaccidents,theprobabilityofoccurrenceofananalyzedaccidentremainsunaffected.Thisdesignpackageonlyenhancestheenvironmentaldocumentationofvariousinstrumentationandinnowayaffectstheplantdesign,thereforethepossibiHtyofanunanalyzedaccidentormalfunctionhasnotbeencreated.ThesurveiDancerequirementsoftheTechnicalSpecificationswererhviewedagainsttheequipmentqualificationmaintenancerequirementsaddressedinthispackageinthedesignanalysis.NoTechnicalSpecificationchangesarerequiredbythisdesignpackage.Inconclusion,thechangesproposedbythisdesignpackageareacceptablefromthestandpointofnuclearsafetybecausetheydonotinvolveanunreviewedsafetyquestionandnoTechnicalSpecificationchangesarerequired.SUPXramKHTflTherevisionsincorporatedbysappleaentfldonotaffecttheoriginalsafetyevaluation.

PCM099-186STLUCIEPLANT-UNITNO.1UPPERGUIDESTRUCTURELIFTRIGLOADTESTFIXTUREREASLN-86-010ABSTRACTThisPlantChange/Modification(PC/M)consistsofthefabricationandinstallationofatemporarystructurewhichwillbeusedtoload-testtheUpperGuideStructure(UGS)LiftRigafteritisrepairedandmodified.Thestructurewillbeattachedtothereactormissileshieldsintheirlaydownarea.Thestaticloadtestwillbeperformedbythereactorpolarcraneusingthemissileshieldsastestloads.Aftertheloadtest,thistemporarystructurewillberemovedfromthecontainment.ThisPC/Misnotclassifiedassafety-relatedsincetheloadteststructurewillnotperformoraffectanysafety-relatedfunction.Althoughfailureofthetestfizturewillnotresultinanyinteractionwithsafety-relatedequipmentorfunctions,QualityRelatedrequirementswillbeappliedtothedesignbecauseoftheimportanceofthdUGSLiftRigtoplantoperations.TheQualityRelateddesignrequirementsassureQ.C.inspectionoftheinstallationandindependentverificationofthedesignoftheloadteststructure.ThisPC/Mdoesnotconstituteanunreviewedsafetyquestion.TheonlyeffectonplantoperationswilloccurduringtherefuelingoutageUGSLiftRigloadtest.TheimplementationofthisPC/Mdoesnotaffect-anysafety-relatedequipment.0186L

PCM099-186SAFETYEVALUATIONWithrespecttotitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.Thismodificationisnotclassifiedassafetyrelatedsincetheloadteststructuredoesnotperformanysafetyfunction.Failureoftheloadteststructurebefore,during,oraftertheloadtestcouldnotaffectanysafety-relatedequipmentorfunctionsincethestructurewillbeinstalledinthecontainmentonlyduringtherefuelingoutageandislocatedawayfromanysafety-relatedcomponents.FailureoftheloadteststructureduringtheloadtestcoulddamagetheUGSLiftRig.TheUGSLiftRigisnotasafety-relatedcomponent,butitisimportantsinceitsfailureduringliftingoftheUGScouldresultinaloaddropontothereactorandirradiatedfuelassemblies.Forthisreason,theloadteststructurehasbeendesignedusingalityRelatedrequirements.ThecontainmentheatsinkanalysisinventoryofhydrogengeneratingitemsandfreevolumeassumptionsdescribedinFUSARSection6.2,arenotaffectedbythismodification,sincetheloadteststructureistemporaryandwillberemovedfromthecontainmentpriortoplantoperation.ThemodificationsincludedinthisPC/Mdonotinvolveanyunreviewedsafetyquestionsbecause:iTheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisnotincreasedsincethismodificationwillhavenoeffectonequipmentperformingasafetyfunction.iiThereisnopossibilityforanaccidentormalfunctionofadifferenttypethananypreviouslyevaluatedsincetheloadteststructureperformsnosafetyfunctionandnochanges,.havebeenmadetoanyoperationaldesign.Failureoftheloadteststructurewillhavenoeffectonanysafety-relatedequipmentorfunction.Thismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanytechnicalspecification.TheimplementationofthisPC/Mdoesnotrequireachangetotheplanttechnicalspecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafety.question;therefore,priorCommissionapprovalisnotrequiredforimplementationofthisPC/M.0186L

PCM114-186STLUCIEPLANT-UNITHO1CONDENSATEPUMPSEXPANSIONJOINTREPLACEMENTREA-SLN-85-153hBSTRACTTheexistingexpansion)ointsintheCondensatePumpssuctionaremadeofelastomericmaterialwhichhasdeterioratedduetoaging.ThedeteriorationissoseverethattheCondensateSystemissusceptibletoairpermeation.Tocorrectthisproblemtheexistingexpansion)ointswillbereplacedwithnewstainlesssteelexpansion)oints.TheCondensateSystemconsideredinthisEngineeringPackageisnon-safetyrelated.Accordingly,thisEngineeringPackageisclassifiedasnon-safetyrelated.ThesafetyevaluationhasshownthatthisEPdoesnotimpactplantsafetyandoperationanddoesnotconstituteanunreviewedsafetyquestionorrequireaTechnicalSpecificationchange.Therefore,priorNRCapprovalisnotrequiredforimplementation.0186L

PCM114-186SafetEvaluationWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.TheCondensatePumpexpansionjointsarelocatedbetweentheCondenserandCondensatePumpsandareutilizedtoabsorbdifferentialthermalexpansionbetweenthesecomponents.Theydonotperformanysafetyrelatedfunctionandthereforeareclassifiedasnon-safetyclass,QualityGroupD.Thefailureanalysishasshownthatfailureofthesecomponentsvillnotaffectanysafetyrelatedequipment.Thisnon-safetyrelatedmodificationdoesnotinvolveanunreviewedsafetyquestionbecause:Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportisnotincreased.TheStLucieUnitNo1PSAR,Section10.4.6describestheCondensateSystem.ThisSectionindicatesthattheportionofCondensateSystembeingmodifiedandtheexpansionjointarenotdesignedtoseismicClassIstandardsandtheyarenotusedinanysafetyanalysisforaccidentsormalfunctionofequipment.Thissystemisnon-safetyrelatedandwillhavenoeffectonequipmentvitaltoplantsafety.(ii)Thepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisisnotcreated.Thecomponentsinvolvedinthismodificationdonotperformanysafetyrelatedfunction.NochangeshavebeenmadetotheoperationaldesignoftheCondensateSystem.(iii)ThemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisnotaffectedbythisPCM,sincethecomponentsinvolvedinthismodificationarenotdirectlyincludedinthebasesofanyTechnicalSpecification.TheimplementationofthisPCMdoesnotrequireachangetotheplantTechnicalSpecification.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunzevievedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.0186L

PCMNO.119-186REVNO1STLUCIEPLANT-UNITNO110CFR50.49ENVIRONMENTALQUALIFICATIONLISTREVISIONREASLN-85-58ABSTRACTThisEngineeringPackageprovidesthevehicleforupdatingseveralareasofequipmentqualification.Thispackageincludescorrectionstothe10CFR50.49list,changesinmaintenancerequirements,andvariousdocumentationpackagecorrections.ThisEngineeringPackage(EP)isconsideredNuclearSafetyRelatedbecauseitaffectsequipmentfallingunderthescopeof10CFR50.49.ThispackagedoesnotrepresentanunreviewedsafetyquestionsinceitdealsstrictlywithenhancingthepresentdocumentationusedtoqualifyequipmentatStLucieUnitNo1andnophysicalplantmodificationsarerequiredbytheEP.ThesafetyevaluationofthispackageindicatesthatachangetothePlantTechnicalSpecificationsisnotrequired.Removalofequipmentfromthe10CFR50.49listdoesnotaffectplantsafetyandoperation.Sulement1ThisEPrevisionaddsterminalblockstothe10CFR50.49listandthei,rassociatedEquipmentQualificationDocumentationPackage8770-A-451-17.0"AmeraceTerminalBlocks".TheequipmentandEQDocumentationPackagedoesnotaffecttheoriginalsafetyevaluation.

PCM119-186SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunrevisedsafetyquestion:(1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ii)ifapossib1lityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated,or(iii)ifthemarg1nofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThisEngineeringPackageprovidesforseveralchangestothepresentStLucieUn1tNo.l's10CFR50.49list.Thisdocumentation&llaffectthefutureprocurementofvarioussafetyrelatedcomponentsandassistinvalidatingthecomponents'bilitytofunctionbefore,duringandafteradesignbasisaccident.Therefore,thisEPisconsideredNuclearSafetyRelated.ThedocumentationchangesaddressedinthispackagerangefromcorrectionsoftypographicalerrorsonthelOCFR50.49listtoadditionsanddeletionsofequipmentasaresultofEgdocumentationpackagesreviews.Noneofthechangesrequirephysicalmodificationtoanyplantsystem.Theydo,ho@ever,affectthefuturemaintenanceofvariousequipment.ThepossibilityofnewDesignBasisEvents(DBEs)notconsidered1ntheUFSARisnotcreatedsincethischangedoesnotalteranyequipmentusedtomitigateaccidents.Thismodificationisanenhancementoftheenvironmentalqualificationdocumentationofvariousequipmentandinno@ayaffectstheplantdesign.

PCM119-186DuetothefactthatthisEPdoesnotaffectormodifyanycablesessentialtosafereactorshutdownorsystemsassociatedwithachievingandmaintainingshutdowns,thispackagehasnoimpacton10CFR50Appendir"R"firepxotectionrequirements.TherefoxetheproposeddesignofthispackageisincompliancewiththeapplicablecodesandUFSARrequirementsforfireprotectionequipment.SincethismodificationinvolvesnophysicalmodificationstosafetyrelatedequipmentandchangesinthemaintenancescheduleswillnotresultInfailureofequipment,thedegreeofprotectionprovidedtoNuclearSafetyRelatedequipmentisunchanged.Removalofequipmentfromthe10CFR50.49listdoesnotaffecttheplant'ssafety.Theprobabilityofmalfunctionofequipmentisunchanged.Theprobability.ofmalfunctionofequipmentimpoxtanttosafetypreviouslyevaluatedintheUFSARremainsunchanged.TheconsequencesofmalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheUFSARareunchanged.ThepossibilityofmalfunctionsofadifferenttypethanthoseanalyzedintheUFSARisnotcxeated.Basedontheabove,themodificationsincludedinthisEngineeringPackagedonotinvolveanunreviewedsafetyquestionbecauseofthefollowingreasons:TheprobabilityofoccurrenceandtheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportwillnotbeincreasedbythismodificationbecauseit'oesnotaffecttheavailability,redundancy,capacity,orfunctionofanyequipmentrequiredtomitigatetheeffectsofanaccident.(ii)ThepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportwillnotbecxeatedbythismodification.Function,mountingandtheabilitytowithstandharshenvironmentalconditionshavenotbeenalteredandthismodificationdoesnotaffectanyothersafetyrelatedequipment.(iii)ThemaxginofsafetyasdefinedinthebasesforanytechnicalspecificationisnotreducedsincethismodificationdoesnotchangetherequirementsoftheTechnicalSpecifications.TheImplementationofthisPCMdoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheImplementationofthisPCMisnotrequired.

PCM128-186STLUCIEPLhNTUNITNO1STARTlJPTBhNSFORMERLOCXOUTDISCONNECTSWITCHESREA-SIR&77-10ASSXRhCTThisEngineeringPackage(EP)providesfortheinstallationofdisconnectswitchesintheplantstartuptransformerslockoutrelaycircuits.Thepurposeofthischangeistofacilitatelockoutrelaymaintenancetestingwhileeliminatingthepossibilityofinadvertentplanttripbypropagationofalockoutrelaytripduringlockoutrelaymaintenancetest.ThisEPisclassifiedas~1ityRelatedsincelockoutcircuitactuationvilltripthestartuptransformerandwouldresultinplantoperationunderLimitingConditionsforOperationasdefinedinthePlantTechnicalSpecification.Subsequentlossofoffsitepowertothestationbusescouldaffectplanttrip,startingandloadingBaergencyDieselGenerators.hreviewofthechangestobeimplementedbythisPCM@asperformedinaccordanceWththerequirementsof10CFR50.59.hsindicatedintheSafetyEvaluation(Section3.0),thisPCMdoesnotinvolveanunreviewedsafetyquestion,nordoesitrequirearevisiontotheplantTechnicalSpecifications.Thismodificationvillhavenoeffectonplantsafetyoroperation.PriorComnissionapprovalisnotrequiredfortheimplementationofthisPCM.0186L SAFETYEVALUATIONPaf128-186WithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ii)ifthepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafety.analysisreportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebarrisforanyTechnicalSpecificationisreduced.ThemodificationsincludedinthisEngineeringPackagedonotinvolveanunreviewedsafetyquestionbecause:(i)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluated,inFSARSection8.3.1.1,isnotincreasedsincethestartuptransformersandtheirlockouttripcircuitsarenotNuclearSafetyRelatedequipment.FailureofthetestswitcheswillnotaffecttheavailabilityoftheEmergencyDieselGeneratorsintheeventoflossofoffsitepower(LOOP).ii)Thereisnopossibilityforanaccidentormalfuncgionofadifferenttypethananypreviouslyevaluatedsincethestartuptransformersareusedforplantstartupandshutdown.Zatheeventoftestswitchfailurewhichmayresultinunavailabilityofthepreferredoffsitepowersource(start~transformer),-theemergencydieselgeneratorscanprovidethepowerrequiredforsafeshutdownaspreviouslyevaluatedinFSARSection8.3.(iii)ThismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanyTechnicalSpecification.ThishasbeendeterminedbasedonthefactthatthismodificationdoesnotexceedthelimitationsofPlantTechnicalSpecificationanddoesnotaffectsafereactorshutdown,themitigationoftheconsequencesofadesignbasisevent(DBE),orthecontrolofradioactivereleasestotheenvironment.ThisEPaffectsequipmentthatisNonnuclearSafetyRelated.However,sincestartuptransformer'failure,andstartuptransformertripsignalactuationwiU.resultinplantoperationunderTechnicalSpecificationlimitations,thisEPisclassifiedasQualityRelated.ThisEPhasnoeffectoncablesessentialtosafereactorshutdownorcomponentslistedontheEssentialEquipmentList.Therearenochangestoequipmentinvolving10CFR50Appendix"R"FireProtectionrequirements(seeattachment7.1).Thus,theproposeddesignofthispackageisincompliancewiththeapplicablecodesandFSARrequirementsforfireprotectionequipment.ImplementationofthisPCMdoesnotrequireachangetothePlantTechnicalSpecificationsandmaybeimplementedwithoutpriorCommissionapproval.Theforegoingconstitutes,per10CFR5059(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionnordoesitrequirearevisiontotheplantTechnicalSpecifications,andpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

STLUCIEUNITNO1AUTOLEARRATETESTERPORPERSONNELAIRLOCKSREA-SLN-86&05PCM131-186ABSTRACTThisengineeringpackageallowsforthereplacementoftheezistingVolumetricsAutomaticLeakTestSystemmodel14324(obsolete)withthecurrentlyavailableVolumetricsmodel14330-2.Thissystemwillprovidebothlocalandremote(maincontrolroom)alarmonfailureofleakratetest.SincetherearenoessentialcablesassociatedwiththisEP,thispackagehasnoimpacton10CFR50hppendiz"R"requirements.Theleakratetestsystemisnotrequiredforsafereactorshutdownanddoesnotservetomitigatetheconsequencesofadesignbasesevent(DBE)andisthereforenotsafetyrelatedequipment.However,sincethispackageincludesmodificationstocontrolboardannunciators,andisrequiredtomaintainthelimitsofStLucie-Unit1TechnicalSpecificationSection3/4.6,"ContainmenthirI,ocks,"itisconsideredQualityRelated.Thisengineeringpackagewillrestoreautomatictestcapabilitiestothepersonnelairlocksandreducemanpowerrequirementstomanuallyoperatetheezistingleakratetesters.Theezistinginteriordoortester,currentlyinsidethecontainmentvessel,isrelocatedoutsidetheezteriordoorsoasto<<inimizepersonnelcontactwiththeRCA.TheimplementationofthisPCNdoesnotrequireanychangetotheStLucie-Unit1TechnicalSpecifications.ThemodificationsdonotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthispackageisnotrequired.

SAFETYEVALUATIONPCN131-186WithrespecttoTitle10oftheCodeofFederalRegulations,-Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(i)iftheprobabilityofoccurxenceortheconsequencesofanaccidentor<<alfunctionofequipmenti<<portanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased,or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreport<<aybecreated,or(iii)ifthemarginofsafetyas.definedinthebasesforanytechnicalspecificationisreduced.TheproposedmodificationaffectspersonnelairhatchleakratetestingwhichprovideslocaLandremote(maincontrolzoom)alarmontestfailure.ThepxobabilityofoccurenceofaDBEpxeviouslyaddressedintheFOSARisnotaffectedbythis<<odification.Thissystemwillinfactdecreasetheprobabilityofabreachofcontainmentbyassuringcontainmentintegrity.Failureofthissystemtooperatepropexlywillbeannunciatedtherebypreventingtheperformanceofinaccuratetesting.ThepossibiLityofnewDBEsnotconsideredintheFUSARisnotcreatedsince.thedesignphilosophyhasbeenpreviouslydiscussedintheFOSAR.This<<odificationisanenhancementtoapre~istingsystemasisbeingperformedtoprovidethehighestcaliberequipmentpossibLe.DuetothefactthatthisEPdoesnotinvolveanycablesessentialtosafereactorshutdownoxsystemsassociatedwithachievingandmaintainingsafeshutdownconditions,thispackagehasnoimpacton10CFR50hppendiz"R"fireprotectionrequirements.ThereforetheproposeddesignofthispackageisincompliancewiththeapplicablecodesandFOSARzequirementsforfireprotectionequipment.'heleakdetectionsystemisnotnecessaryforsafereactorshutdownnordoesitserveto<<itigatetheconsequencesofadesignbasesevent(DBE.Hence,thispackageisnotsafetyrelated.However,sinceare<<otealarmintheMainContxolBoardisprovidedbytheContainmentPersonnelAirLockAutomaticTestSystemand<<odificationstotheannunciatoxpanelsareincludedinthisdesign,thispackageisQualityRelated.~LityControlEngineershallwitnesstheinstallationofthenewannunciatortileintheContxolRoomaswellastheautoleakratetesterinthepersonnelaccessarea.Astheevaluationoffailure<<ode(Section2.27)indicates,thefailuremodeofthissystemhasnoeffectonsafetyrelatedsystemsox'quipment.BencethedegreeofprotectionprovidedtonuclearsafetyreLatedequipmentisunchanged.Theprobabilityofmalfunctionofequipmenti<<portanttosafety,pxeviouslyevaluatedintheFOSARremainsunchanged.Theconsequencesof<<alfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFOSARax'eunchanged.Thepossibilityof<<alfunctionsofadifferenttypethanthoseanalysedintheFOSARisnotcreated.TheimplementationofQalityRelatedPC/M131-186doesnotrequixeachangetotheplanttechnicalspecifications,nordoesitcreateanunreviewedsafetyquestions.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunzeviewedsafetyquestionandpriorCommissionapprovalfortheimplementation,ofthisPCMisnotrequiredi pCM133-186ST.LUCIEUNIT1SPDSSOFTMAREMODSABSTRACTThisEngineeringPackagecoversthemodificationstothepreviouslycertifiedsoftwareofthegualifiedSafetyParameterDisplaySystem(gSPDS).Themodificationsconsistofadditionstoassisttheplantoperatorinaccident.monitoring.ThereisnomajorgSPDShardwaremodificationasaresultofthisPC/M.However,theexchangeofidenticalErasableProgrammableReadOnlyMemory(EPROM)chipswererequiredasaresultsofsoftwaremodifications.ThisEngineeringPackageissafetyrelatedbecauseitinvolvesmodificationstoasafetygradedsystemgSPDS.ThegSPDSisasafetygradeclasslEprocessinganddisplaysystemusedforpost-accidentmonitoring.Thehardwareandsoftwarechangesof'hisPC/MwereevaluatedagainstIOCFR50.59.Theresultsoftheevaluationarethatthereisnounreviewedsafetyquestion.

PCM133-186SAFETYEVALUATIONThisengineeringpackageissafetyrelatedbecauseitinvolvesamodificationtoasafetygradedsystem.WehaveevaluatedtheeffectsofthisPC/Mwithrespecttoregulation10CFR50.59.ThetwoapplicableitemsfortheQSPDSare:a)UnreviewedSafetyQuestionsTherearenomajorhardwarechangesduetothisPC/M,sincetheexchangedhardware(EPROM's)areidenticaltooriginal.Thesoftwarechangesconsistoftheadditionofonedisplaypagewhichisconsistentwiththerequirementsofformat,contentandvisibilityoftheoriginaldesign.Therefore,thereisnoincreaseintheprobabilityofoccurrenceorconsequenceofanaccident,ormalfunctionofequipmentbecauseofthismodificationtotheQSPDS.ThepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedprevreviouslyintheFSARhasnotbeencreated.InadditionthemarginofsafetyisnotdecreasedbythisPC/M.Instead,thesafetymarginisconsideredtobeincreasedduetotheincreasedvisibilityofthesafetyparametersbytheoperatorasaresultofthisPC/M.b)TechnicalSpecificationsTherequirementsestablishedintheTechnicalSpecificationfortheQSPDSareunaffectedbythisPC/M.ThechangesofthisPC/Mdidnotaffectdesign,norpreviousfunction,itmerelyimprovedHumanFactorsEngineeringconsiderations.

PCM138-186BECKMANWASTEGASSYSTEMOXYGENANALYZERREPLACEMENTSTLUCIEPLANT-UNITNO1REA-SLN-86-030Inordertoincreasetheavailabilityoftheoxygenanalyzersforfrequentmonitoringoftheoxygenlevelsinthewastegasdecaytanks,theexistingoxygenanalyzerswillbereplacedwithupdatedoxygenanalyzershavingananalyticalelementdesignedforsamplingservicesineitherliquidorgaseoussamplestreams.Theinherentdesignfeaturesofthereplacementanalyzerswillincludethedesignandoperationalcriteriaforsamplemonitoringandinstallationinpotentiallyhazardouslocations,therefore,thisdesignshallbeconsideredasQualityRelated.TheimplementationofthisEngineeringPackagewillhavenoimpactonplantsafetyorplantoperation.AreviewofthechangestobeimplementedbythisPCMwasperformedagainsttherequirementsof10CFR50.59.AsindicatedinSection3.0ofthisEngineeringPackage(EP),thisPCMdoesnotinvolveanunreviewedsafetyquestion,nordoesitrequirearevisiontothetechnicssp-i-"ttherefore,priorCommissionapprovalisnotrequiredforimplementationofthisPCM.

SAFETYEVALUATIONPCM138-186WithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthe0safetyanalysisreportmaybeincreased,or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.i)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunct5onofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportisnotincreasedsincetheOxygenAnalyzersareusedforfrequentmonitoringofoxygenconcentrationsinthewastedecaytanksandasdescribedinPSL-1FSARSubsection11.3.2.1thissystem'sfunctionisnotessentialforthesafetyoftheplant.ThereplacementofOxygenAnalyzerswillprovidecontrolimprovementsto.maintaintheWasteGasAnalysisSystemfunctionalwithsignificantreductioninsystemmaintenanceandcomponentreplacements.ii)Thepossibilityofanaccidentormalfunctionofadifferenttypeotherthananyevaluatedpreviouslyinthesafetyanalysisreportisnotcreatedsince:a)ThisinstallationisinaccordancewiththeCodeofFederalRegulation10CFR50.49andnoimpactisincurredbythisinstallation.b)ThenewequipmentmountingsandaddedcomponentshavebeenanalyzedinaccordancewiththespecificationfortheDesignFabricationandErectionofStructuralSteelforBuilding,andithasbeendeterminedthatthestresseswiththenewequipmentarelesst5anthepanelstresseswiththeoriginalequipment.c)ThisinstallationisinaccordancewiththeCodeofFederalRegulation10CFR50.49andhasbeendeterminedtohavenoimpactontheEnvironmentalQualificationcriteriasincetheequipmentdoesnotmonitorormitigatetheeventcausingtheharshenvironment.d)TheWasteGasSystemOxygenAnalyzersareneitherrequiredforsafeshutdownnorformitigatingtheconsequencesofanaccident.iii)ThemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationsisnotaffectedbythisEPsincethecomponentsinvolvedinthismodificationarenotincludedinthebasesofanyTechnicalSpecification.TheimplementationofthisPC/MdoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorNuclearRegulatoryCommissionapprovalfortheimplementationofthisPCMisnotrequired.

PCM140-186STLUCIEPLANT-UNIT1ANNUNCIATORNUISANCEhIhLNSREA-SLN-86-052ABSTRACTThisEngineeringPackage(EP)coversthemodificationsoffiveannunciatorcircuitsintheMainControlRoom.Existinglogic,circuitconfigurationandcomponentswillbechangedintheReactorTurbineGeneratorBoards(RTGBs)soastoeliminateexistingnuisanceconditionscausedbyerroneousalarmindicationofthesefiveannunciatorcircuits.ByimplementingthisEP,thesecircuitswillbeconsistentwiththe"DarkAnnunciator"conceptwhichallowsforlightedannunciatorsduringoff~ormalconditionsonly.ThisEPisclassifiedasNuclearSafetyRelatedsinceitinvolvestheinterposingofacontrolrelayinasafetyrelatedcircuit(hydrogenanalyzer)andtheextensionofsafetyrelatedpowersupplycables(10482E,10482L,and10485H).ThesafetyevaluationhasdeterminedthatthisEPdoesnotinvolveanunreviewedsafetyquestionanddoesnotrequireachangeintheplanttechnicalspecifications.ThisPCMmaybeimplementedwithoutpriorNRCapproval.SUPPLANT1ThisEngineeringPackageRevisioncoversmodificationofthesixannunciatorcircuitsassociatedwithannunciatedwindowsP"30,P-35,P-36>P-42,Q-40andX-5intheControlRoom.Thesemodifications,whichincluderelocationof-localresetswitches,installationofreflashersandlogicmodifications,willeliminatethenuisancealarmstatusofthesixannunciators.ByimplementingthisPCMSupplement,thesesixannunciatorswillbebroughtintocompliancewiththe"DarkAnnunciator"conceptofNUREG0700"GuidelinesforControlRoomDesignRevie~"~TheoriginalSafetyEvaluationhasbeenrevised.TheSafetyEvaluationstillconcludes,however,thatthisEPdoesnotinvolveanunreviewedsafetyquestion,orachangetothetechnicalspecifications.Therefore,priorNRCapprovalisnotrequiredforimplementationofthePCM.TheintentoftheoriginalSafetyEvaluationisnotaffectedbythissupplement.SUPPLEMENT2ThisEngineeringPackageRevisioncoversmodificationofthethreeannunciatorcircui.tsassociatedwithannunciatorwindowsN-45,R-50,andS-24intheControlRoom.Thesemodifications,whichincludetheinstallationoffour(4)relays,evaluationtosupportsetpointmodificationsanddrawingcorrections,willeliminatethenuisancealarmstatusoftheannunciators.TheSafetyEvaluationofSupplement1tothisPCMhasbeenrevised.TheSafetyEvaluationstillconcludesthatthisEPdoesnotinvolveanunreviewedsafetyquestionorachangetotheTechnicalSpecifications.Therefore,priorCommissionapprovalisnotrequiredforimplementationofthePCM.TheintentoftheoriginalSafetyEvaluationisnotaffectedbythissupplement.

PCM140-186SAFETYEVALUATIONPithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangedshallbedeemedtoinvolveanunreviewedsafetyquestion'.(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased;or(ii)ifthepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.ThemodificationsincludedinthisEngineeringPackagedonotinvolveanunreviewedsafetyquestionbecause:(i)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisnotincreasedsincetheannunciatorsservenofunctioninthecontrolofplantoperationsorsafeshutdown.Electricalseparationisprovidedbetweenredundantsafetyrelatedwiringandcomponentsandannunciatorlogicwhichisseparatedtoprotectcontrolfunctionsfrombeingaffectedbyannunciationcircuitfailure.(ii)Thereisnopossibilityforanaccidentormalfunctionofadifferenttypethananypreviouslyevaluatedsincenochangeshavebeenmadetotheoperationaldesignofanycontrolcircuitsorassociatedsystems.(iii)Thismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanytechnicalspecification.SincethisEPaffectsequipmentthatisidentifiedasNuclearSafetyRelated(HydrogenAnalyzerandSITankIsolationValves3614,3624,3634.63644)andrequirestheextensionofNuclearSafetyRelatedpowersupplycables(10482E,10482L>and10485H),itisconsideredNuclearSafetyRelated.DuetothefactthattheEPdoesnotinvolveanycablesessentialtosafereactorshutdownorsystemsassociatedwithachievingandmaintainingsafeshutdownconditions,thispackagehasnoimpacton10CFR50Appendix"R"fireprotectionrequirements.Therefore,theproposeddesignofthispackageisincompliancewiththeapplicablecodesandStLucie-Unit1FSARrequirementsforfireprotectionequipment.ImplementationofNuclearSafetyRelatedPCM140-186andSupplements142tothesamePCMdonotrequireachangetotheplanttechnicalspecificationsandmaybeimplementedwithoutpriorNRCapproval.Theforegoingconititutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorNRCapprovalfortheimplementationofthisPCM,aswellasSupplements162tothesame,isnotrequired.

'

PCM147-186LUCIEUNITIICMOISCHARGEPIPfZINCRIB80N(REA-SLN-SS-137-12)~BSTRACTackaecoverstheinstallationofzincribbonMt{ICM)dischargepiping.'cialanodesintheIntakeCoolingaerh'lldithepipebeginningattheComponentMaterCCM)wallandextendingtothedischargecanal,ThheanodeswillbeinsaeneovidecathodicprotectionfortheinternalsurfaceThPC/Hi1if'tRelatedbecausethesacrificialanodesaretobeinstalledftyRelatedICMpipe.Theanodesperformnosafetydoesnotconstituteanunreviewedsafetyquestionorrequire.ftPltsafetyoroperationandtheinstallationachaneQtotheplantTechnicalSpecifications.

SAFVA'ATIOThesacrificialanodestobeinstalledintheICWdischargepipeasdescribedinthisdesignpackagedonothaveasafetyfunction.Asdemonstratedbythefailuremodesevaluationinthedesignanalysis,theprincipleeffectonsafetyisthepotentialforinternalpipecoatingdamageintheeventthatazincribbonpipeattachmentfails.Forthisreason,gualityRelateddesignrequirementshavebeenappliedandthemodificationisclassifiedasgualityRelated.Basedupontheaboveandinformationsuppliedinthedesignanalysis,itcanbedemonstrated,thatanunreviewedsafetyquestionasdefinedbyIOCFR50.59doesnotexist.i)TheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetyevaluatedinthesafetyanalysisreporthasnotbeenincreasedbecausethezincanodesareinstalleddownstreamofallactiveICWSystemcomponentsevaluatedintheFSAR.Therefore,thereisnointeractionwiththeevaluatedsystemcomponents.ii)Thepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreporthasnotbeencreatedbecause,asdemonstratedinthedesignanalysis,theworstcasefailureofthezincanodepipeattachmentswouldhavenoimpactontheICWSystemcapabilitytoperformitsdesignfunctionsasspecifiedinFSARSection9,2.1.Inaddition,thepipeattachments(thermitwelds)havebeenevaluatedandthedeterminationhasbeenmadethatthebondingprocesswillnotcausedetrimentalmetallurgicalconditionsorimpactthepipecoatingsystems.iii)ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenreduced.TheinstallationofthezincanodeswillhavenoimpactonthestructuralintegrityoftheICWsystempipingorthedesignflowrequirementsofthesystem.Forthisreason,itisconcludedthatthemarginofsafetyhasnotbeendecreased.IOCFR50.59allowschangestoafacilityasdescribedintheFSARifanunreviewedsafetyquestiondoesnotexistandifachangetotheTechnicalSpecificationsisnotrequired.Asshownintheprecedingsections,thechangeproposedbythisdesignpackagedoesnotinvolveanunreviewedsafetyquestionbecauseeachconcernposedbyIOCFR50.59thatpertainstoanunreviewedsafetyquestioncanbepositivelyanswered.Inconclusion,thechangeproposedinthisdesignpackageisacceptablefromthestandpointofnuclearsafety,doesnotinvolveanunreviewedsafetyquestion,doesnotrequireachangetotheTechnicalSpecificationsanddoesnotrequirepriorNRCapproval.

PCM013-187FLORIDAPOWER6LIGHTCOMPANYSTLUCIEPLANT-UNITNO1SIMULATORTRAININGFACILITYGAI-TRONICSREA-NONEABSTRACTThisEngineeringPackage(EP)includesmodificationstoprovideGai-Tronicscommunicationcapability,includingemergencyalarmsandinstructions,fortheSimulatorTrainingFacility.ThenewGai-TronicsequipmentwillbetiedintotheexistingStLucieUnit1Gai-TronicsSystemattheServiceBuilding.ThemodificationspresentedbythisEngineeringPackageimpactonlynon"safetyrelatedequipment.However,twoconduitsupportsarebeingaddedtoasafetyrelatedblockwall.Theadditionalloadinghasbeenreviewedanddeterminedtohavenoeffectonthestructuralintegrityofthewall.TheGai-TronicsmodificationsarerequiredinordertoassurecompliancewiththeStLuciePlantEmergencyPlan.Also,thepowersupplyfortheGai-TronicsSystemissuppliedfromavitalACsource.Therefore,thispackageisclassifiedasQualityRelated.AreviewofthechangestobeimplementedbythisPC/Mwasperformedagainsttherequirementsof10CFR50.59asindicatedinSection3.0ofthisEP.Asaresult,theexpansionoftheGai-TronicsSystemtoincludetheSimulatorTrainingFacilitydoesnotconstituteanunreviewedsafetyquestionandwillnotaffectplantsafetyanditsoperation.TheimplementationofthisPCMdoesnotrequireachangetothePlantTechnicalSpecifications.Therefore,priorcommissionapprovalisnotrequiredforimplementationofthisEP.

C SafetEvaluationPCM013-187WithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.ThisEngineeringPackageprovidestheengineeringanddesigndetailsrequiredtoexpandtheStLucieUnit1Gai-TronicsCommunicationSystemtoincludetheSimulatorTrainingFacility.Gai-TronicsspeakerswillbelocatedthroughouttheSimulatorTrainingFacilityinordertoassurecompletecoveragefortheemergencyalarmsignals(e.g.,siteevacuationalarm)~Onehandset/speakeramplifierwillbelocatedintheSimulatorFacilitytoprovidetwomayGai-Tronicscommunicationcapability-BasedupontheexpansionoftheGai-TronicsSystempresentedbythisEP,thebreakerforcircuit33ofnon-safetyrelatedVitalACBusNo1(thepowerfeedfortheGai-TronicsSystem)willbeincreasedfroma20amptoa30ampbreaker.Also,thefeedercablefromVitalACBusNo1totheGai-TronicsPowerDistributionCabinet(Cable11201F)willbechangedfrom1-2/Cf10to2-1/Cf4.Allothersupplementalequipment(i.e.,the70ampfuse,isolationtransformerandfeedercables11201YandZassociatedwiththepowersupply)remainunchanged.Theadditionalloadpresentedbythismodification(3.6ampsmaximumat120VAC)isconsideredinsignificantandwillhavenoimpactonloading.Also,theincreaseinbreakersizewillnotaffectcircuitbreakercoordination.AfaultonVitalACBusNo1,circuit33willnotresultinthelossoftheentirevitalbus(i.e.fthecircuitbreakerand/orfuseforcircuit33willclearthefaultbeforeanyupstreambreakeropens).Baseduponthefeedercablechangeout,anewnon-safetyrelatedconduitisrequiredintheRABfromVitalACBusNo1tocabletrayC3.Twonewconduitsupportsareaddedtoseismicallydesignedblockwall4167.Theadditionalloadinghasbeenreviewedandithasbeenconcludedthat'neitherthestresslevelsinthewallnoritsfundamentalnaturalfrequencyaresignificantlyaffectedbythismodification.TheGai-TronicsSystemandthe120VVitalACSystemarenotsafetyrelatedsystems.TheexpansionoftheGai-TronicsSystemtoincludetheSimulatorTrainingFacilityhasnoimpactonanyotherplantsystemsoroperations.TheGai-TronicsSystemisnotrequiredtomitigateormonitoranyresultofanaccident.Failureofthissystemhasnoimpactonpreviouslygeneratedsafetyanalysisreports.ThemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisnotreduced~JTheimplementationofthisPC/MdoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanyunreviewedsafetyquestions,andpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired~~a,t~e+gs+yv~w~'

PCM016-187CCWiTCWANDOBCWVALVEACTUATORREPLACEMENTSTLUCIEPLANT-UNITNO1REA-SLN-86&31ABSTRACTThisEngineeringPackage(EP)istoreplacetwo(2)existingBettisactuators,includingallaccessories,ontheshutdowncoolingheatexchangerisolationvalves,I-HCV-14-3Aand3B.Theseactuatorsopenthevalvesonthesafetyinjectionactuationsignal(SIAS)andsupplycoolingwatertotheheatexchanger.Duringtheoutageof1985,theactuatorswereinspectedandfoundtohavecylinderwear.Theexistingactuators,model746-X-2SR-42,arenolongermanufacturedandsparepartsarenotavailable,thereforetheyare.beingreplacedwithBettisactuators,modelNT312-SR4&3.Thenewactuatorsoperateinthesamemannerandwillperformthesamefunctionastheexistingactuators.ThemodificationconsideredinthisEPisontheComponentCoolingWaterSystem.ThevalvesandactuatorsareClass3SeismicCategoryI>thereforethisEPisclassifiedasSafetyRelated.Designdetailsareprovidedfortheinstallationofthenewactuatorsandallaccessoriesontheexiftingvalves.ThesafetyevaluationhasshownthatthisEPdoesnotconstituteanunreviewedsafetyquestionandimplementationofthisEPdoesnotrequireachangetotheTechnicalSpecification.Therefore,priorNRCapprovalisnotrequiredforimplementation.TheimplementationoftheEPwillhavenoimpactonplantsafetyoroperation.

PCM016-187SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59>aproposedchangeshallbedeemedtoinvolveaaunrevievedsafetyquestion:(i)iftheprobabilityofoccurrenceoxtheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybe'ncreased;or(ii)ifthepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisRepoxtmaybecreated;or(iii)ifthe,marginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.ThemodificationconsideredinthisEPisclassifiedassafetyrelatedbecausetheshutdowncoolingheatexchangerisolationvalves,I-HCV".14-3Aand3B,andactuatoxsareSafetyClass3,SeismicCategoryI.Inthemodificationthetvo(2)existingBettisactuators,model746A-X-2SR-42villbereplacedwithnevactuatore,modelNT312"SR4%3,becausetheexistingactuatorsarenolongermanufacturedandsparepartsarenotavailable.Theactuatoreopentheisolationvalvesintheeventofaa,SIAS.Thenevactuatorsvillperformthesamefunctioninthesamemannerastheexistingactuators.Nonewfailuremodesarecreated.Onloseofpowerorlossofairthevalves"failopen".ThemodificationsincludedinthisEngineeringPackagedonotiavolveanunreviewedsafetyquestioabecause:i)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedarenotincreasedbecausethenevactuatorsvillperformthesamefunctioninthesamemannerastheexistingactuators.ii)Thereisnopossibilityforaaaccidentormalfunctioaofadifferenttypethananypreviouslyevaluated.ThisEPdoesnotmodifytheintendedopexationortestrequirementsofthesystembecausethenevactuatorswillperformthesamefunctioninthesamemannerastheexistingactuators.iii)ThismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationbecauseitneitherchangesthedesignparametersoftheCCWsystemnordoesitchangetheCCWdesignflovorfunctionalrequirements.TheimplementationofthischangedoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationvhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestiontherefore,priorNRCapprovalfortheimplementatioaofthisPCMisnotrequired.

PCM018-187SYLUCKUNrrIDrainforPipeLine2-VM-DOO(REA-SLN-86-86)ABSTRACTThisEngineeringPackage(EP)isforpreparationandissuanceofnecessarychangesindocumentationtoreflectpermanentinstallationofadrainconnection/tapinstalledinthespoolpiecedownstreamofFIT6608inline2-WM-D00byCircuitAlterationTagNo.2025.FIT6608islocatedinaverticalrunofpipingintheWasteManagementSystemoffgasheaderintheRAB.Theoffgasheadermustbeperiodicallydrainedduetocondensationinthepiping.FIT6608actslikeacheckvalveandpreventswaterfromgoingtoalowpointdrain.Thedrainconnection/taplocatedinthespoolpieceallowswaterabove(downstream)FIT6608tobedrainedoutoftheheader.Theexistingpipingatthedrainconnection/taplocationisnon-seismic,OualityGroupD,performsnosafetyrelatedfunction,hasnoaffectonsafetyrelatedequipment,hasnoaffectonplantsafetyandoperation,andthegasflowingthroughthepipeisacceptablefordischargetotheenvironment.But,sincethegasandcondensationinthepipinghasthepotentialtoberadioactive,theEPisclassifiedasqualityrelated.Basedonafailuremodeanalysisand10CFR50.59review,thechangeproposedbythisEPisacceptablefromthestandpointofnuclearsafety,itdoesnotinvolveanunreviewedsafetyquestion,anddoesnotrequireanychangestoTechnicalSpecifications.Therefore,priorNRCapprovalisnotrequiredforimplementationofthemodification.

SAFETYEVhLUATIONpCN018-187ThisEPisforpreparationandissuanceofnecessarychangesindocumentationtoreflectpermanentinstallationofadrainconnection/tapinstalledinthespoolpiecedownstreamofFIT6608inline2-WM-D00byCircuitAlterationTagNo.2029.FIT6608islocatedinaverticalrunofpipingin.theWasteManagementSystemoffgasheader.Theoffgasheadermust'beperiodicallydrainedduetocondensationinthepiping.FIT6608actslikeacheckvalveandpreventswaterfromgoingtoalowpointdrain.Thedrainconnection/taplocatedinthespoolpieceallowswaterabove(downstream)FIT6608tobedrainedoutoftheheader.Theexistingpipingatthedrainconnection/taplocationisnon-seismic,QualityGroupD,performsnosafetyrelatedfunction,hasnoaffectonsafetyrelatedequipmentorfunctions,andthegasflowingthroughthepipeisacceptablefordischargetotheenvironment.But,sincethegasandcondensationinthepipinghasthepotentialtoberadioactive,theEPisclassifiedasqualityrelated.Basedontheaboveandtheinformationsuppliedinthedesignanalysis,itcanbedemonstratedthatanunreviewedsafetyquestionasdefinedby10CFR50.59doesnotexist.oTheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.Thedrainconnection/tapandassociatedpipingarenotusedinanysafetyanalysisforaccidentsormalfunctionofequipment.Thismodificationisnon-nuclearsafetyrelatedandwillhavenoeffectonequipmentvitaltoplantsafety.Basedonthis,theprobabilityofoccurrenceortheconsequencesofallanalyzedaccidentsremainunchanged.oThepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreporthasnotbeencreated.Thismodificationisnon-nuclearsafetyrelatedandbasedonthefailuremodesanalysiswillhavenoeffectonsafetyrelatedequipmentandfunctions.oThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenreduced.Nofunctionofthesubjectdrainandassociatedpipingiscontrolledbyorinthebasisfor,anyTechnicalSpecification.Thus,themarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenreduced.10CFR50.59allowschangestoafacilityasdescribedintheFSARifanunreviewedsafetyquestiondoesnotexistandifachangetotheTechnicalSpecificationisnotrequired.Asshownintheprecedingsections,thechangeproposedbythisdesignpackagedoesnotinvolveanunreviewedsafetyquestionbecauseeachconcernposedby10CFR50.59thatpertainstoanunreviewedsafetyquestioncanbepositivelyanswered.Also,nochangetotheTechnicalSpecificationsisrequiredbasedontheaboveevaluation.Inconclusion,thechangeproposedinthisdesignpackageisacceptablefromthestandpointofnuclearsafety,doesnotinvolveanunreviewedsafetyquestion,anddoesnotrequireanychangetoTechnicalSpecifications.Therefore,priorNRCapprovalisnotrequiredforimplementationofthemodifications.

pcs034-187ST.Mcmmtre1COHDEHSEROQTIZTTUBESHEETPHDQhTERBOXCOhTIHGShBSTRhCTThisengineeringpackageaddressestheadditionofanepoxycoatingtothecondenseroutlettubesheetsandvaterboxes.Thismodificationvillenhancethecorrosionresistanceofthetubesheetsandwaterboxesandallovreductionofthecathodicprotectionsystempotentialsandcurrentdensities.Thecondensersandtheplantcirculatingwatersystemareclassifiedasnon-nuclearsafetyrelatedandtherefore,themodificationaddressedinthisengineeringpackagedoesnotconsistuteanunreviewedsafetyquestion.Furthermore,theadditionofaprotectivecoatingtothecondenseroutlettubesheetsandwaterboxesdoesnotrequireachangetotheplantTechnicalSpecifications.mm-"ThissupplementconsistsofthecorrectionofthedrawingnumberlistedunderSection11.2nfthisEngineeringPackageandthecorrectionofatypographicalerrorintheabstract.Thesechangesdonotaffecttheoriginaldesignbasesanddonotaltertheconclusionsoftheoriginaldesignanalysisorsafetyevaluation.

PCM034-187AsnotedinFSARSections9.2.3and10.4.5,thecondensersandcirculatingwatersystemperformnonuclearsafetyrelatedfunction.Afailuremodeevaluationoftheproposedcondenseroutlettubesheetandwaterboxcoatingshasdeterminedthereisnopotentialforinteractionwithequipmentorfunctionsimportanttonuclearsafety.Accordingly,themodificationaddressedbythisengineeringpackageisclassifiedasnonnuclearsafetyrelated.Basedontheaboveevaluationandinformationsuppliedinthedesignanalysis,ithasbeendemonstratedthatanunreviewedsafetyquestionasdefinedby10CFR50.59doesnotexist.Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.Sincethereisnopotentialforinteractionbetweenthemodificationaddressedbythisengineeringpackageandequipmentoffunctionsimportanttosafety,previoussafetyanalysisreportevaluationsrelatedtosafetyremainunaffected.Thepossibilityofanaccidentormalfunctiondifferentthanthosepreviouslyevaluatedinthesafetyanalysisreporthasnotbeencreated.Nonewaccidentsormalfunctionsassociatedwiththefailureofthecondenseroutlettubesheetandwaterboxcoatingshavebeencreated.ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationhasnotbeenr"educed.Sincethereisnopotentialforinteractionbetweenthemodificationaddressedbythisengineeringpackageandequipmentorfunctionsimportanttosafety,themarginofsafetyasdefinedinanyTechnicalSpecificationremainsunaffected.lnconclusion,themodificationproposedinthisengineeringpackageisacceptablefromthestandpointofnuclearsafety,doesnotinvolveanunreviewedsafetyquestionanddoesllnotrequireachangetoanyTechnicalSpecifications.Accordingly,NRCapprovalpriortoimplementationisnotrequired.

i PCM036-187ST+LUCIKUNITCondenserTubingStrainSageInstallation8QQXBBtXAspartoftheinvestigationintotitaniumcondensertubehydriding(hydrogenembrittlement)whichhasbeendiscoveredattheSt.LucieNuclearPlant,straingageinstrumentationwillbeusedtomeasureactualtubestrainfollowingtheunit'sreturntopoweroperation.afterthepresentrefuelingoutage.Dataonactualtubestrainlevelsduringfull.poweroperationisrequiredinordertodevelop"realistic"criteriaforfuturetubepluggingwhichmayberequiredduetohydriding.Thisdesignpackageprovidestheengineeringnecessaryto'installa11/2"diameterpenetrationintothecondensersteamspacetoallowforroutingofstraingagewiring.Alsoprovided'reguidelinesforinstallingthestraingagesandtheleadwiringinthecondenserandthroughthenewpenetration.Followingtesting,thestraingageleadwiringistobecut>andthenewpenetrationistobecappedandalljointsare.tobesealwelded.Duringthene~trefuelingoutage,thewiringand"piping"conduitaretoberemovedfrominsidethecondenser.Thisdesignpackageisclassifiedas"Non-NuclearSafetyRelated"sinceitaffectsonlynonseismic,QualityGroupDpipingandstructuresinNon-NuclearSafetyRelatedsystems.Basedon.thefailuremodesanalysisand10CFR5059review,thismodificationdoesnotimpactanysafety'el'atedequipmentandisnotrelieduponforanyaccidentpreventionormitigation.Thusitdoesnotconstituteanunreviewedsafetyquestion.Sincetherearenounreviewedsafetyquestions,andsincenochangestotechnicalspecificationsareinvolved,thisPC/NmaybeimplementedwithoutpriorNRCapproval.

PCN036-187SAFETYEVALUAITONThnt1CondeneUiserisaNon-NuclearSafetyRelatedcomponentandassuchisnotrequiredtofunctionduriaganyexistinganalyzedaccidentscenarios.Therefore,modificationstothecondenseraffectsonlyNon-NuclearSafetyRelated,QualityGroupDequipnent.Theaddedpenetrationwillmeetalldesigncriteriaofexistingpenetrationstoinsurethatthecondenserpressureboundaryismaintained.Postulatedfailuresofthematerialswouldhavenoimpactonsafeshutdownoftheplant,orsafetyrelatedsystems.AnymaterialsinvolvedinthismodificationwhichcouldbepostulatedtobecomedislodgedwouldbecaughtinthecondenserhotwellpumpscreenNoneofthematerialsarelargeenoughtoimpactpumpsuction.Additionally,postulatedfailuresofthecondenserwouldhavenoimpactonsafeshutdownoftheplant,orsafetyrelatedsystems.Thecondenserisnotusedtopreventpostulatedaccidents,mitigatetheconsequencesofsuchaccidents,maintainsafeshutdownconditions,oradequatelystorespentfuel.Thefollowingstatementsdemonstratethatanunreviewedsafetyquestion,asdefinedby10CFR50.59,doesnotexist:.*Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.Failureofthecondenserisnotconsideredasanaccidentinitiatingeventorconsideredindeterminingtheprobabilityofanaccident.Also,sincethisdesignchangedoesnotalteroraffectequipnentusedtomitigateaccidents,theprobabilityofmalfunctionofequipmentimportanttosafetyremainsunchanged.Thepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysishasnotbeencreated.ThereisnonewfailuremodeintroducedbythischangethathasnotbeenevaluatedpreviouslyintheFSAR.Additionally,nofailuremodesanalyzedbytheFSARareaffectedbythisdesign.*ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationshasnotbeenreduced.ThischangehasnoeffectonanyexistingTechnicalSpecificationsanddoesnotrequireanychangestotheTechnicalSpecifications.Sincenounreviewedsafetyquestionshavebeendeterminedtoexist,andsincenorevisionstotheTechnicalSpecificationsarerequired,NRCapprovalisnotrequiredpriortoimplementation.0198L/

CONDENSATERECIRCULATIONTOCONDENSERSQUAREROOTEXTRACTORREPLACEMENTSTLUCIEPLANT-UNITNO.IREA-SLN6-OIIp~039-187ABSTRACTThisEngineeringPackagecoversthereplacementofone(I)squarerootextractor.Thepresentlyinstalledsquarerootextractorisnolongerbeingmanufacturedandasuitablereplacementisbeingprovidedformaintenancereasons.ThisEngineeringDesignPackageisconsideredqualityrelatedsincethereplacementdeviceisanIntegralpartofthecondensaterecirculationsystemandadirectreplacementforpreviouslyapprovedinstrument.Theinstrumentationloop,ofwhichthisdeviceispartof,isnotusedtomitigateincidents.andaccidentsand,therefore,thisPC/Mlsneoconsideredtobesafetyrelated.hreviewofthechangestobeimplementedbythisPCMwasperformedagainsttherequirementsof10CFR50.59.AsindicatedinSection3.0ofthisPCM,thisPCMdoesnotinvolveanunreviewedsafetyquestion,nordoesitrequirearevisiontothetechnicalspecification.Therefore,priorcommissionapprovalisnotrequiredfort}wimplementationofthisPCM.SAFETYEVALUATIONThechangingoutoftheSquareRootExtractorinthisPC/Mdoesnotinvolveanunreviewedsafetyquestionbecause:\ThisEPreflectsnointerferencewiththesafetyequipmentinthattheyarenotrequiredforasafereactorshut-downandcouldnotbeusedtomitigateanaccident.Thesquarerpotextractorsarenon-safetyrelated.Thismodificationwillhavenoeffectonequipmentperforminganysafetyfunction.Thereisnopossibilityforthecreationoianaccidentormalfunction.Intheeventofatotalfailureofthissquare-rootextractor,itwillhavenoeffectuponanysafetyrelatedequipement.Theprobabilityofoccurrenceoftheconsequencesofanaccident.ormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisneitherincreasednoroccurssincethissystemisnon-safetyrelated.Thismodificationwillhavenoeffectonequipmentperforminganysafetyfunction.Thissystemand/orcomponentpartsarenotusedinanyaccidentscenarioandthereisnopossibilityforcreatinganaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyreport.Itsfailurewillhavenoimpactontheplantsafeshut-down.Ithasnoeffectuponthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationsincethereplacementofthesquarerootextractordoesnotchangetheoriginaldesignoroperationandtheproposednewextractor'sarefunctionallyidenticaltoexistingunits.Therearenochangestotheplanttechnicalspecifications.Theforegoingconstitutes,per10CFR50.59,thewrittensafetyevluationwhichprovidesthebasisthatthischangedoesnotinvolveanunreviewedsafetyquestion.Therefore,priorcommissionapprovalisnotrequiredforimplementationofthisPC/M.

PCM041-187TUCIEUNITNOMFRVPOSITIONINDIChTORSREMOVhLREh-SLN-85-043-10BSTRhCTThisengineeringpackagecoverstheremovaloftwoMainFeedwaterRegulatingValvepositionindicators(ZI-9011,9021)fromRTGBoard102alongwithassociatedwiring,cable,andconduit.hsteelplatewillbefastenedtothecontrolboardtocovertheexposedarea.Since.theseindicatorsareoperationallyunreliable,thepotentialexistsforincorrectinterpretationofregulatingvalveposition.RemovaloftheindicatorswillaccomplishtheresolutionofaHumanFactorsDiscrepancy(HED).Nomodificationstothevalvecontrolcircuitrywillbeperformed.Hence,routinevalveoperationswillcontinuetobecontrolledfromsignalsreceivedautomaticallyviatheFeedwaterRegulatingSystem.Therefore,this'modificationwillnothaveanyadverseeffectuponplantsafetyoroperation.ThereareneitheranyTechnicalSpecificationnorRegulatoryGuide1.97requirementsforthesedevices.SincethisdesignrequiresamodificationtotheRTGboard,QualityRelatedrequirementsshallbeimposed./Thesechangeswerereviewedagainsttherequirementsof10CFR50.59.hsverifiedintheSafetyEvaluation,thischangeneitherrequiresaTechnicalSpecificationrevisionnorisitanunreviewedsafetyquestion.Therefore,priorNRCapprovalisnotrequired.

PCN041-187ShFHTYHVhLUhTIONThisBPisclassifiedasQualityRelatedbecausethecomponentsbeingremoved,whileperformingaNon-NuclearSafetyRelatedfunction,areinstalledintheRTQBoardwherethepotentialexistsforimpactingSafetyRelatedequipmentthroughmodificationofthewiringintheRTGBoard,theremovalofequipment,andtheinstallationofcoverplatesthatcouldpotentiallyhaveaneffectontheseismicintegrityoftheRTGBoard.ThisdesignproposestoremovetheMainPeedwaterRegulatingValve(MFRV)positionindicatorscurrentlyinstalledintheRTGBoard102.Theindicatorsareunreliableandcouldprovidemisleadingvalvepositionindication.Removaloftheindicatorswillnotaffecttheoperator'sabilitytodeterminefeedwaterfloworsteamgeneratorlevel.hmpleinstrumentationisavailabletomonitortheseparametersfromthecontrolroom.Inaddition,indicatinglightsinthecontrolroomwillremaintodeterminewhetherthesubjectflowcontrolvalvesarefullyopenorfullyclosed.TheindicatorsbeingremoveddonotperformaNuclearSafetyRelatedfunctionandarenotincludedunderanyTechnicalSpecificationorRegulatoryGuide1.97requirement.InternalwiringchangesarebeingperformedintheRTGBoardtodisconnectthesubjectindicatorsandtoremove(SIS)wiring.Whenrequired,onlyqualifiedwirejumperswillbeinstalledinsidetheRTGBoard.Noconduitisbeingremovedadjacentto,orinthevicinityoftheRTQBoardorcontrolroom.TherestorationoftheRTGBoardthroughappropriatecoverplatestoreplacetheremovedindicatorshasbeenevaluatedwithinthispackage.ThisevaluationconcludedboththattheseismicintegrityoftheRTQBoardwillberetainedandthatnomissilescouldbegeneratedduringaseismiceventwhichcouldadverselyimpactSafetyRelatedequipment.

PCM054-187STLUCIEPLANT-UNITNO1CONDENSATEPOLISHERTIE-INSREA-SLN-85-14ABSTRACTThisEnineeringPackage(EP)isfortheinstallationofthe24inchUnit1tie-inpipingandmanualisolationvalvesrequiresgneuiredforthefutureconnectionoftheCondensatePolisherSystem(2CdtSystem.Italsoincludestheinstallati,onofthe8inchoncasaetie-inpipingthatwillconnecttheCPSbackwashpumpsucUi2CondensateStorageTanknon-safetyclassconnection.existingntonensaeThisisforprovidingthecapabilityofusingtheUnit2ccondensateforbackwashingthecondensatepolisher.ThisEPisclassifiedqualityrelatedsinceitalsoinvolvesmodificationstoteheRTGB-102whichisseismicallyqualifiedandlocated-02involveinhUit1ControlRoom.ThemodificationstotheRTGB-1nvovetenoninlihtsteatonohddiifthetie-inisolationvalvepositionindicatnggandalarmforvalvemisalignment.ThesafetyevaluationhasdeterminedthattheEPdoesnotconstituteanunreviewedsafetyquestionandimplementationoftheEPdoesnotrequireachangetothePlantTechnicalSpecification.Therefore,priorNRCnotificationforimplementingthisEPisnotrequired.ThisEPhasnoimpactonplantsafetyandoperation.SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulation,Part50.59,aproposedchange,shal1bedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccenomidtralfunctionofequipmentimportanttosafetypreviously~(ii)ifaevuavaluatedinthesafetyanalysisrepoxtmaybeincreased;or()assibilityforanaccidentormalfunctionofadifferenttypethannyaevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefined'nthebasesforanyTechnicalSpecificationisreduced.ThisEngineeringPackage(EP)isfortheinstallationofthe24inchcondensateUnit1tie-inpipingrequiredforthefutureconnectionoftheCondensatePolisherSystem(CPS)totheUnit2CondensateSystem.Italsoincludestheinstallationofan8inchconnectiontothecondensatepolisherbackwashpumpsuctionfromanexistingnon-safetyclassconnectiontotheUnit2condensatestoragetank.Thisisforprovidingthecapabilityofusing,inthefuture,Unit2condensateforbackwashingthecondensatepolishers.TheportionsoftheCondensateSystem,CondensateStorageTankpipingandtheCPSthatthismodificationwillbeimplementingdonotperformanysafetyfunctionorinteractwithsafetyrelatedequipment;however,sincethisEPalsoinvolvesmodificationstotheRTGB,whichisseismicallyqualified,fortheadditionofanannunciatorandindicatinglightsforthecondensatepolisherisolationvalves,itisclassifiedqualityrelated.

p~054-187SAPETYEVALUATION(CONTINUED}ThenewannunciatorandindicatinglightsthatwillbeaddedtotheRTGBhavebeendesignedandwillbeinstalledtothesamerequirementsasexistingannunciatorsandindicatinglightsintheRTGB.ThisadditionofcomponentstotheRTGBhasbeenreviewedandconsideredacceptableandincompl1ancewiththeseismicrequirementsapplicabletotheRTGB.Basedontheabovedescription,themodificationincludedinthisEngineer1ngPackage(EP)1sconsideredtobequalityrelated.This.EPdoesnotinvolveanunreviewedsafetyquestion,andthefollowingarebasesforthisjustification-(1)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluated1nthesafetyanalysisreportisnotincreased.TheportionsoftheCondensateSystem,wherethismodificationwillbeimplemented,andtheCPSarenotusedinanysafetyanalysisforaccidentsormalfunctionofequipmentandassucharenon-safetyrelatedandwillhavenoeffectonequipmentvitaltoplantsafety.Theaddit1onofthenewannunciatorandindicatInglightstotheRTGBhasbeenreviewedandconsideredtobeacceptableandincompliancewiththeseismicrequirementsapplicabletotheRTGB.Thepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreport1snotcreated.Thecomponentsinvolvedinth1smodificat1onhavenosafetyrelatedfunctionandnochangeshavebeenmadetotheoperationaldesignofthesystem.(111)ThemarginofsafetyasdefinedinthebasesforanyTechn1cal.SpecificationisnotaffectedbythisPCM,sincethecomponentsinvolvedinthismodificationarenotincludedinthebasesofanyTechnicalSpecification.TheimplementationofthisPCHdoesnotrequireachangetotheplantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidedthe'asesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommisisionapprovalfortheimplementationofthisPCMisnotrequired.

PCH075-l87STLUCIEUNITNO1FIREDETECTORMODIFICATIONSREA-SLN-86-63-10ABSTRACTThisEngineeringPackagecoversthemodificationstothefiredetectionsystemwhichispartoftheFireProtectionSystem.ThisEngineeringPackagewillprovidetheengineeringanddesigndetailsrequiredtoimplementthereplacementoftheexistingionizationsmokedetectors.Theexistingdetectorsaredividedintotwo(2)groups:Theoriginals(installedeleven(ll)yearsago)whichareobsolete;andtheirreplacements(installedastheoriginalsfailed)whicharenolongermanufactured.Toensurethereliabilityofthefiredetectionsystem,newstateoftheartionizationsmokedetectorswillbeinstalled.TheFireDetectionSystemisnon-safetyrelated,butisprovidedinareasthatcontainorpresentafireexposuretoequipmentessentialtosafeplantshutdown.Therefore,thisEngineeringPackageisclassifiedasQualityRelated.Thesafetyevaluationhasdeterminedthatthismodificationdoesnotinvolveanunreviewedsafety.questionandimplementationofthisPCMdoesnotrequireachangetoPlantTechnicalSpecifications.Therefore,priorNRCapprovalfortheimplementationofthisPCMisnotrequired.ThisEPhasnoimpactontheplantsafetyandoperation.SAFETYEVALUATIONkithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityof.occurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.ThisEngineeringPackageprovidestheengineeringanddesigndetailsrequiredtoimplementthereplacementoftheexistingionizationsmokedetectorswithnewdetectorsandnewwiringbases.Theexistingdetectorsareeitherobsoleteornolongermanufactured.TheimplementationofthisEngineeringPackageensurestheavailabilityoftheindividualdetectorstodetectafire.

PCM075-187SAFETYEVALUATION(CONTINUED)Firedetectionsystemsareprovidedinareasthatcontainorpresentafireexposuretoequipmentessentialtosafeplantshutdown.Therefore,thisEngineeringPackagehasbeenclassifiedasQualityRelated.Basedonthepreceding,thisEPdoesnotinvolveanunreviewedsafetyquestionandthefollowingarethebasesforthis5ustification:Theprobabilityofoccurrenceortheconsequenceofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportisnotincreased,sincethereplacementoftheionizationsmokedetectorsenhancestheoperabilityoftheequipment.Thereplacementoftheobsoletedetectorswithnewdetectorsisonaonetoonebasis,withthenewdetectorshavingthesamecharacteristicsastheexistingdetectors.Thepossiblefailureofthedetectorswillnotpreventsafetyrelatedequipmentfromperformingtheirintendedfunctions.Thedetectorsarenotrequiredduringanaccidentcondition.(ii)Asaresultofthismodification,thereisnopossibilityforanaccidentormalfunctionofadifferenttypethananypreviouslyevaluated.Thedetectorsarenotrequiredduringanaccidentconditionnorwilltheypreventsafetyrelatedequipmentfromperformingtheirfunctions.Theexistingdetectorsarebeingreplacedonaoneto.onebasis.Thismodificationdoesnotaffectanysafetyrelatedequipment.(iii)ThismodificationdoesnotreducethemarginofsafetyasdefinedinthebasesforanyTechnicalSpecification.ThefunctionsoftheFireDetectionSystemthatarecontrolledbytheapplicableTechnicalSpecificationsaremaintainedbythischange.TheimplementationofthisPCMdoesnotrequireachangetotheplantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

PCM076-187STLUCIEPLANT-UNIT1ERMDS/SASUPGRADEREA-NONEThisEngineeringPackageprovidesformodificationstothecomputerroominpreparationforimplementinganupgradetotheEmergencyResponseDataAcquisitionandDisplaySystem,whichiealsoknownaetheSafetyAssessmentSYstem(ERDADS/SAS),underPCM076-187Supplement1andPCM077-287.Includedinthisworkaretheconnectionofthecomputerroomtotheadgoiningoffice,relocationofcomputerroomandofficedoors,installationofafalsefloorintheoffice,upgradeoflightingandconvenienceoulete,andinetaH.ationofconduitandcablesforthecomputercontrolterminals,thedataloadingterminal,CRT812console,anddiskdrives.ThisEngineeringPackageieclassifiedasqualityrelatedduetothecableandconduitwhicharebeinginstalledtosupportSASqualityrelatedcomponents.ImplementationofthisPCMdoesnotinvolveanunreviewedsafetyquestionorchangetothePlantTechnicalSpecificatione.Therefore,itcanbeimplementedwithoutpriorCommissionapproval.ImplementationofthisEPwillnotaffectthesafetyofoperationoftheplant.SUPPLEMENT1Inadditiontomodifyingthecomputerroom,thisEngineeringPackageprovidesforanupgradetotheERDADS/SAShardwareandsoftwareincludingtheSafetyParameterDisplaySystem(SPDS),intheStLucie-Unit1controlzoom,computerroomandtechnicalsupportcenter.ItvillimprovetheperformanceanddisplaycapabilitiesoftheexistingsystemandwillincludenewdisplayCRTsandkeyboards,newcolorhazdcopiers,additionalprinters,adataloadingterminal,additionalmemoryandnewinternalcomputerswitchingandcommunicationscomponentsiThisEPremainsclassifiedasqualityrelatedsincethefunctionoftheERDADS/SASsystem,whichistoassisttheoperatorsinevaluatingthesafetystatusoftheplant,hasnotchanged.Theoriginalsafetyevaluationhasnotbeenaffected.Therefore,implementationofthisEPdoesnotinvolveanunreviewedsafetyquestionorachangetothePlantTechnicalSpecifications.ItmaybeimplementedwithoutpriorCommissionapproval.ImplementationofthisRPwillnotaffectthesafetyoroperationoftheplant.0198L/

076-187SUPPLEMENT2SupplementThisEPremainsclassifiedasqualityrelatedsincethefunctionoftheERDADS!SASsystem,whichistoassisttheoperatorsinevaluatingthesafetystatusoftheplant,hasnotchanged.Theoriginalsafetyevaluationhasnotbeenaffected.Therefore,implementationofthisEPdoesnotinvolveanunrertewed-safwt~uestionorachangetothePlantTechnicalSpecifications.ItmaybeimplementedwithoutpriorCommissionapproval.ImplementationofthisEPwillnotaffectthesafetyoroperationoftheplant.2tothisEngineeringPackagemodifiesthedesigntoreplacetheCRTs,videogenerators,andsupportingcomponentswhichwereoriginaly11specifiedinSupplement1duetohardwarecompatibilityproblemsTheoveralldesignremainsthesame.SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunx'eviewedsafetyquestion:(i)iftheprobabilityofoccuxrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincx'eased;or(ii)ifthepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisfoxanytechnicalspecificationisreduced.

SAFETYEVALUATION(continued)076-187ThemodificationsincludedinthisEngineeringPackagedonotinvolveanunrev3.ewect'afetyquestionbecause:i)TheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedarenotincreasedsincetheexistinginputisolationoftheERDADS/SASequipmentwillnotbemodifiedandwillmaintainthesamelevelofprotectionforsafety-relatedequipment.ii)Thereisnopossibilityforanaccidentormalfunctionofadifferenttypethananypreviouslyevaluatedsincenonewsafety-relatedfunctionsorinterfaceswithsafety-relatedsystemsarecreatedbythisEP.iii)ThismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanyTechnicalSpecification,sincenoequipmentinstalledormodifiedbythisEPaffectsanyparameterreferencedintheTechnicalSpecifications.ThisEPmodifiesequipmentwhichisnotnuclearsafetymelated.However,sincetheERDADS/SASsystemassistscontrolroompersonnelinevaluatingthesafetystatusoftheplant,thisEPisclassifiedasqualityrelated.TheHumanFactorsEngineeringevaluationoftheSPDSportionoftheERDADSsystemfoundseventy"four(74)HEDs.Allfour(4)Priority1HEDshavebeencorrected.Therefore,theHEDsfoundthroughthisHumanFactorsEngineeringreviewdonotaffectplantsafety.ThisEPhasnoeffectoncablesorcomponentsnecessaryforsafeshutdownoftheplant.Changestoequipmentandstructuresinvolving10CFR50Appendix"R"fireprotectionrequirementsandchangestoequipmentontheEssentialEquipmentListhavebeenaddressed.(SeeAttachment7.1).Thus,theproposeddesignisincompliancewithapplicablerequirementsforfireprotection.TheimplementationofthischangedoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.ThisEPhasnoeffectoncablesorcomponentsnecessaryforsafeshutdownoftheplant,.Changestoequipmentandstructuresinvolving10CFR50Appendix"R"fireprotectionrequirementsandchangestoequipmentontheEssentialEquipmentListhavebeenaddressed.(SeeAttachment7.1).Thus,theproposeddesignisincompliancewithapplicablerequirementsforfireprotection.TheimplementationofthischangedoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b'),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

PCN078-187STLUCIEPLANT-UNIT1REPLACEMENTOPPISCHERANDPORTERCONTROLLERSREA-SLN&6-91-10ThisEngineeringPac'kage(EP)coversthereplacementofthenowobsoletePischer6PortercontrollerawiththecurrentlymanufacturedandfunctionallyequivalentPischer6Portercontrollers.Thecontrollersareusedtomaintainthelevelandpressureparametersinthepressurizerwithintherequiredlimitsduringthenormalplantoperation.ThesecontrollersperformNon-NuclearSafetyRelatedfunctions.However,beinglocatedonthemaincontrolboard,theyareexpectedtomaintaintheirstructuralintegrityduringthedesignbasisseismicevent.ThecontrollersareclassifiedQualityRelated.Thesafetyevaluation(Section3.0)indicatesthatthisEngineeringPackagedoesnotinvolveanunreviewodsafetyquestion,anddoesnotrequireachangeinthePlantTechnicalSpecifications.Therefore,NRCapprovalforthesemodifications,priortotheirimplementation,isnotrequired.ThisEPhasnoimpactonplantsafetyorop'eration.

PCM078-187SAPETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ii)ifapossibilityforanaccidentormalfuntionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThemodificationsincludedinthisEngineeringPackagedonotinvolveanunreviewedsafetyquestionbecauseofthefollowingreasons'.TheprobabilityofoccurrenceandtheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportarenotincreasedbythismodificationbecauseitdoesnotaffecttheavailability,redundancy,capacity,orfunctionofanyequipmentrequiredtomitigatetheeffectsofanaccident.ThepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportwillnotbecreatedbythismodificationbecausethefunctionofthecontrollershasnotbeenalteredbythismodification.(iii)Themarginofsafetyasdefinedinthebasesforanytechnicalspecificationisnotreducedsincethenewcontrollersperformnon-nuclearsafetyrelatedfunctionsandarenotincludedinthebasesofanytechnicalspecification.ThenewcontrollersreplacetheobsoletecontrollersonClass1Emaincontrolboard,therefore,thisEPisclassifiedQualityRelated.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecifications,nordoesitcreateanunrevtewedsafetyquestion.Therefore,thePCMmaybeimplementedwithoutpriorCommissionapproval.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

STLUCIEUNIT1TURBINEGENERATORSEALOILSYSTEMENHANCEMENTS@GAEA:SLN-86-092-10)ABSTRACTThisEngineeringPackagecoversmodificationstotheTurbineGeneratorSealOilSystemasrecommendedinV/estinghouseOperationsandMaintenanceMemo005l{Reference6.3).Thismodificationprovidesfortheinstallationofa"dripleg"intheairsidesealoilpumpsuctionlineandanadditionalventlinebetweentheexistingventlineandthehydrogensidedrainregulatortank.Thesesystemenhancementsshouldminimizeoilintrusionintothegeneratorhousing,anddecreasetheamountofdirtandcontaminationthatwouldleadtodamage/weartosystemcomponents.TheTurbineGeneratorSealOilSystemperformsnosafetyrelatedfunctionsnordoesitinteractwithsafetyrelatedequipment.Therefore,thismodificationisclassifiedasnon-nuclearsafetyrelated.Basedonafailuremodeevaluationanda10CFR50.59review,thismodificationdoesnotinvolveanunreviewedsafetyquestionnorrequirechangestotheTechnicalSpecifications.Therefore,priorNRCapprovalisnotrequiredforimplementationofthismodification.Thismodificationhasnoadverseeffectonplantsafetyoroperability.

PCM085-187SAFETYEVALUATIONThisEngineeri'ngPackagecoversthemodificationstotheTurbineGeneratorSealOilSystem.A"dripleg"willbeinstalledintheairsidesealoilpumpsuctionline.Also,anadditionalventlinewillbeinstalledbetweentheexistingventlineandthehydrogensidedrainregulatortank.Thismodificationisclassifiedasnon-nuclearsafetyrelated,sincetheSealOilSystemperformsnosafetyrelatedfunctionanddoesnotinteractwithsafetyrelatedequipment,components,orfunctions.Basedontheaboveandinformationsuppliedinthedesignanalysis,itcanbedemonstratedthatanunrev.'edsafetyquestionasdefinedby10CFR50.59doesnotexist.oTheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.Duetothelocationofthe"dripleg"andtheventline,theirfailurewouldnotcauseinteractionwithanysafetyrelatedequipment.Also,theturbinegeneratorsealoilsystemisnotconsideredbytheFSARindeterminingtheprobabilityofaccidents,possibletypesofaccidents,orintheevaluationofconsequencesofaccidents.Therefore,itcanbeconcludedthattheprobabilityofoccurrenceofaccidentspreviouslyaddressedintheFSARremainsunchanged.oThepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreporthasnotbeencreated.Thecomponentsinvolvedinthismodificationdonotperformsafetyrelatedfunctions.Theoperabilityoftheturbinegeneratorsealoilsystemhasnotbeenadverselyaffectedbythemodification.Also,thelocationofthe"dripleg"andventlineeliminatesthepossibilityofinteractionwithsafetyrelatedequipment.Therefore,thepossibilityofanaccidentofadifferenttypehasnotbeencreated.oThemarginofsafetyasdefinedinthebasisforanytechnicalspecificationhasnotbeenreduced.Sincethecomponentsinvolvedinthismodificationarenotdirectlyincludedinthebasesofanytechnicalspecification,themarginofsafetyhasnotbeenreduced.10CFR50.59allowschangestoafacilityasdescribedintheFSARifanunreviewedsafetyquestiondoesnotexistandifachangetothetechnicalspecificationsisnotrequired.Asshowninthepreceedingsections,thechangeproposedbythisdesignpackagedoesnotinvolveanunreviewedsafetyquestionbecauseeachconcernposedby10CFR50.59thatpertainstoanunreviewedsafetyquestioncanbepositivelyanswered.Also,nochangetotheTechnicalSpecificationsisrequiredbasedontheaboveevaluation.Therefore,priorNRCapprovalisnotrequiredforimplementationofthismodification.

PCM088-187EQMOTEREACTORVESSELLEVELINDICATORSTLUCIEPLANT-UNITNOlREA-SLN-8706ABSTRACTThisEngineeringPackage(EP)istoinstallaremotelevel1ndicatorforthereactorvessel.thisindicatorwillprov1dereliablelevelindicationduringrefueling.ThemodificationsconsideredinthisEPareontheReactorCoolantSystem.TheconnectionsaredesignatedasNuclearSafetyRelatedandseismicallyqualifiedsincetheyarewithintheReactorCoolantPressureBoundary,andtherefore,thismodificationisclassifiedasSafetyRelated.Theinstrumentsideofthesystemdownstreamofthepipingisolationvalveisdesignatedasnon-safety,seismicdesign.Twotransmitters(onewiderange,onenarrowrange)andassociatedcableswillbeinstalled.IndicationwillbeaddedtotheControlRoomtoallowmonitoringofrefuelingwaterlevel.ThesafetyevaluationhasshownthatthisEPdoesnotconstituteanunrev1ewedsafetyquestionandpr1orNRCapprovalisnotrequiredforimplementation.TheimplementationofthisEPdoesnotrequireachangetotheTechnicalSpecificationanddoesnotreducethemarginofsafetyforanyTechnicalSpecification.TheimplementationoftheEPwillhavenoimpactonplantsafetyoroperation.SupplementNolThepurposeofthissupplementistoremoveallholdpointsassociatedwithth1sEP.Thereactorcoolantpipingsupportsandtheconduitsupportswithinthecontainmentareahavebeenevaluated,sotheholdpointsarenolongernecessary.Theimplementationofthissupplementwillhavenoimpactonplantsafetyoroperation.

PCM088-187SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulation,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.ThemodificationsincludedinthisEngineeringPackagearefortheReactorVesselwaterlevelindicatorinstallationinvolvingpiping,tubing,valvesandorificesanddifferentialpressuretransmitters,allconnectedbetweentheRCSandthePressurizer.Basedontheabovedescription,themodificationincludedinthisEngineeringPackage(EP)isconsideredtobesafetyrelated.thisEPdoesnotinvolveanunreviewedsafetyquestion,andthefollowingarebasesforthisgustificati.on:i)TheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportisnotincreasedsincethismodificationprovidesameanswherebyanaccurateReactorVesselwaterlevelcanbereadilydeterminedduringrefueling.DuringpoweroperationthissystemisisolatedfromtheRCS.3heportionsofthismodificationwithinthenormalRCSpressureboundaryhavebeendesignedtotheoriginalrequirementsoftheRCSpressureboundary.ii)Asaresultofthismodification,thereisnopossibilityforanaccidentormalfunctionofadifferenttypethananypreviouslyevaluatedbecausethemodificationprovidesdoubleisolationvalvingwhichvillisolatethesystemfromtheRCSduring-poweroperation.iii)%hismodificationdoesnotreducethemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationbecauseitneitherchangesthedesignparameteroftheRCSnordoesitchangetheRCSdesignflovorfunctionalrequirements.TheimplementationofthisP(MdoesnotrequireachangetotheplantTechnicalSpecifiqation.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionorachangetotheTechnicalSpecifications,andpriorcommissionapprovalfortheimplementationofthisPCMisnotrequired.

pCN105-187STLUCIEUNIT1CHARGINGPUMPBLOCKMATERIALCHANGEESLN-85--9ABSTRACTThisdesignpackagecoversthereplacementofthecurrentchargingpumpblockmaterial"of316stainlesssteel(ASTM-A-182F316)with17-4PHstainlesssteel(ASME-SA-705Gr.6301150HT).The17-4PHmaterialhasatestedfatiguestrengthapproximatelytwicethatof304.or316stainlesssteel.Fieldtestingofchargingpumpsystemsindicatethatstrongpressurepulsationsexist.attimesinthesystem.Thesepulsationsareinpartresponsibleforthefatiguefailuresofthechargingpumpblocks.Reductionofpressurepulsationsisacurrentconcern.Theincreaseinfatiguestrengthofthenewmaterialshouldresultinasubstantialimprovementinblocklife.Basedonafailuremodeanalysisand10CFR50.59review,thechangesproposedbythisengineeringpackageareacceptablefromthestandpointofNuclearSafety.ThismodificationdoesnotinvolveanunreviewedsafetyquestionandaTechnicalSpecificationchangeisnotrequired,therefore,priorNRCapprovalisnotrequiredforimplementationofthismodification.Thefunctionofthechargingpumpsisnotalteredbythismodification.ThisengineeringpackageisclassifiedasNuclearSafetyRelated.

PCM105-187-SETYVALUA0Thismodificationconsistsofreplacementoftheexisting316stainlesssteelchargingpumpblockswith17-4PH1150HTstainlesssteel.Thismodificationdoesnotaffectthedesignfunctionofthechargingpumpsanddoesnotintroduceanynewactivecomponentstothesystem..Thenewmaterialisstrongerthantheexistingmaterialandshouldprovideasubstantiallylongerservicelifefortheblock.SincethesystemandcomponentsmodifiedbythisengineeringpackageareASMESectionIII,ClassII,thispackageisclassifiedasNuclearSafetyRelated.Thefollowingconstitutesanevaluationtodetermineiftheimplementationofthisengineeringpackagewillresultinanunreviewedsafetyquestionasdefinedby10CFR50.59:Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisisnotincreasedsincenonewactivecomponentsarebeingadded,andthefailuremodesofexistingcomponentsarenotbeingaltered.Accidentprobabilitiesandconsequencesarenotaffectedbythismodification.TheprobabilityofanaccidentormalfunctionofadifferenttypethanpreviouslyevaluatedintheFSARhasnotbeencreated.SincethesystemdesignbasesasdescribedinFSARSections9.3.4.3.2(f)arenotaffectedbythismodification,nonewaccidentsaremadepossible.Themarginofsafetyasdefinedinthebasisforanytechnicalspecificationhasnotbeenreducedsincenosystemdesignparametersarebeingaltered.Thetechnicalspecificationshavebeenreviewedandithasbeendeterminedthatnochangesarerequired.Inconclusion,thechangeproposedinthisdesignpackageisacceptablefromthestandpointofnuclearsafety,doesnotinvolveanunreviewedsafetyquestion,anddoesnotrequireanychangetotechnicalspecifications.Therefore,priorNRCapprovalisnotrequiredforimplementationofthemodifications.

STLUCIEUNITNO1REPLACEMENTOFSAFETYRELATEDBATTERIES1Aand1B(REA-SIN-87-008-11)ABSTRACTThisEngineeringPackagecoversthemodificationstotheSafetyRelatedStationBatteriesIAand1Bwhicharepartofthe125VDCDistributionSystem.ThisEngineeringPackagewillprovidetheengineeringanddesigndetailsrequiredtoimplementthereplacementoftheexistingbatterieswithnewbatteries.Theexistingbatteriesareshowingsignsofdegradation(thebatteryacidiscontactingthecopperpoets).Thenewbatterieswillalsohaveanincreasedsparedesignmargin(capacity)of3Zovertheexistingbatteries,whichwereInstalledintheearly80s,forfutureloadgrowthcapability.Thestationbatteries,whicharepartofthe125VDCsystem,areclassifiedasClasslE,areseismicallyqualifiedandperformasafetyrelatedfunction.ThisEPwillbeclassifiedasSafetyRelated.ThisEPdoesnotconstituteanunreviewedsafetyquestionsincethemodificationsdescribedabovewerereviewedinaccordancewith10CFR50.59.andweredeterminedtohavenoadverseimpactonplantoperationsorsafetyrelatedequipmentTheimplementationofthisPCMdoesnotrequireachangetothePlantTechnicalSpecifications.ThischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.SAFETYEVALUATIONVithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59>aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion,'i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;o'r(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisreduced.

PCM116-187ThisEngineeringPackageprovidestheengineeringanddesigndetai1srequiredtoimplementthereplacementoftheexistingbatterieswithnewbatteries.Theexistingbatteriesareshowingsignsofdegradationwhichcou1dreducethecapacityofthebatterycells.TheimplementationofthisEngineeringPackageincreasestheavaila-bilityofthebatteries,uponlossoftheACpowersystem,toprov1depowersufficienttosupplytheDCloadsuntilthebatterychargersareloadedontothedieselgenerators.The125VDCsystems,whichincludethestationbatteries,aresafetyxelatedandcompleteseparat1onandindependencearemaintainedbetweenequipmentandcixcuits,includingraceway.Asinglefailureatanypo1ntineithexsystemwillnotdisablebothsystems.Thestationbatterieswhicharebeingreplacedperformasafetyrelatedfunctionwithinthe125VDCdistributionsystemandaredesignedforoperationunderconditionsthatcouldbeimposedbyaDesignBasisAccident(DBA).ThisEngineeringPackagehasbeenclassifiedasSafetyRelated.Basedonthepreceding,thefollowingconclusionscanbemade.(1)Theprobabilityofoccurrenceortheconsequenceofanaccidentox'alfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportisnotincreased,sincethereplacementofthestationbatteriesenhancestheopera-bilityoftheequipmentTheadditionofnewbatteriesensuresthatthebatter'ieswillsupplytheminimumDCpowerrequirementstosafelyshutdowntheplantand/ormitigatetheconsequencesofaDBA.(ii)Asaresultofthismodification,thereisnoposs1bilityforanaccidentormalfunctionofadifferenttypethananypxeviouslyevaluated.Thismodificationaffectsaccidentm1tigatingequip-menttoenhancetheiroperation.TheDCsystemvoltageremainsthesamebutthenewbatteriesprovideanincreasedsparedesignmargin(capacity)forfutureloadgrowth.Thereis.nointroductionofanynewfailuremodefortheequipment.(iii)ThismodificationdoesnotreducethemarginofsafetyasdefinedinthebasesforanyTechnicalSpecification.ThesafetyfunctionthatiscontrolledbythevariousapplicableTechnicalSpecificationsismaintainedbythischange.Thepx'oposeddesignensuresthatthebatterieswillfunct1onasassumeddur1nganaccident..ThusthemarginofsafetyprovidedbytheTechnicalSpecificationsispreserved.TheimplementationofthisPCMdoesnotrequireachangetotheplantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

STLUCIEUNIT1GROUTINGOPMASONRYBLOCKWALLSREASLN87-061PCM119-187InthecourseofpreparingthePireProtectionAppendixoftheUnit1FSAR,econcernwasraisedastowhethercertainmasonryblockwallsassumedtobe3hourfirebarriersareactuallygroutfilled.Asafetyevaluationwasperformed(Reference6.5)vhichestablishedthat,ifthesewallsarei.nfactnotfilledwithgroutaadthereforenotprovidingthefull3hoursoffireprotection,theplantbti11maintainsitsabilitytoachievesafeshutdown.Thisfetyevaluationrecommendedthataninspectionoftheseveilsbeperformedtoestablishtheiras-builtcondition.Suchaninspectionwasperformedandconcludedthatthewallsarenotfullygrouted.ThisEngineeriagPackage(EP)providesthedetails/requirementsforgroutingthevoidsiablockwalls79,84,84A,85,92A,114,115,and115A.Thisgroungtiwillbeperformedintwophases.'AHOLDPOINTisplaceonconstructionactiviti.esatthecompletioaofPhaseIwork.seconstructionactivitieswillresumefollowingengineeringapprovalofthePhaseIIgroutiagmaterial.Thismodificatioadoesnotinvolveaauarevievedsafetyquestion,hasaoeffectonplantsafetyandoperation,anddoesaotinvolveachangetoanyplantTechnicalSpecification.Uponcompletionofthismodification,theactioniaTechnicalSpeci.fication3/4.7.12villnolongerberequiredforthewellsmodified.ThisEPisclassifiedQualityRelatedsincealloftheveilsinvolvedarerequiredper10CFR50AppendixRtobefirebarriers.SAFETYEVALUATIONSafetAnalsisWithrespecttoTitle10oftheCodeofFederal.Regu1ations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceorconsequeacesofanaccidentormalfunctionofequipmeatimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;(ii)ifapossibilityforanaccidentormalfuncti.onofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmeybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.WhenaconcernvasraisedthattheveilsmodifiedbythisEPmightnotbefullygrouted,areport(Reference6.5)vaswri.ttentoevaluatethesafetyimplicationsifthewallsverefoundtobenotfullygrouted.Thisreportdemonstratedthat,ifanungroutedconditionwasconfirmed,nounreviewedsafetyquestionsexistsendcontinuedoperationoftheplantis)ustified.ThisEPprovidesthedetails/requirementsforgroutingthewallssothattheyareinconformanceviththedesignbasesestablishedinSubsection3.11.2oftheStLucieUnit1FSARAppendix9.5A;consequently,thismodificationcannotgiverisetoanunreviewedsafetyquestion.Althoughthewallsdonotperformasafety-relatedfunction,thisEPisclassifiedQualityRelated,sinceellofthewallsarerequiredper10CFR50AppendixRtobefirebarriers.

PCM119-187Basedontheabove,thefollowingprovidestheJustificationthatanunreviewedsafetyquestiondoesnotexist:(i)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisnotincreased.-Sincethe~allalocatedinthevicinityofsafety"relatedequipmentmaintaintheirseismicqualification,noaccidentsduetostructuralfailurearepostulated.Theonlyothertypeofaccidentpotentiallyassociatedwiththewallsaffectedbythismodificationinvolvesdamagethatcouldoccurifthewallsfailtoprovidethreehoursoffireprotection.TheJCOdiscussedabove,however,demonstratedthatnosinglefireeventcouldimpairtheplant'sabilitytoachievesafeshutdown.Consequently,therearenoaccidentsormalfunctionsofequipmentimportanttosafetypreviouslyevaluatedwhoseprobabilityofoccurrenceorconsequencesareincreasedbythismodification.ConstructionactivitieswillstopwhenPhaseIiscompleted.PhaseIIconstructionwillcontinueafterPhaseIImaterialshavebeenreviewedandapprovedwithrespecttotheirdensityandtheirstructural,radiationresistance,andthermalresistanceproperties,andtheuseofthesematerialshasbeenshownnottodegradetheseismicqualificationofWalls85and114.ThisitemisidentifiedasaHOLDPOINTandmustberesolvedpriortotheimplementationofPhaseII.Thesafetyevaluationwillber'eviseduponresolutionofthisitem.(ii)Thereisnopossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslysincethemodificationprovidesthewallswithathreehourfireratingwhilethedesignensuresthatthestructuralintegrityoftheseismicallydesignedwallsismaintained.(iii)ThismodificationdoesnotchangethemarginofsafetyasdefinedinthebasesforanyTechnicalSpecification.ThebasisforTechnicalSpecification3/4.7.12indicatesthatfirebarriersensurethatfiredamagewillbelimitedandthepossibilityofasinglefireeventinvolvingmorethanonefireareapriortodetectionandextinguishmentwillbeminimized.ThereferencedJCOindicatedthatthecurrentsituation,incombinationwithcompensatorymeasures,doesnotviolatethisbasis.Whenthewallsarefullygrouted,thebarrierswillbefullyoperational,eliminatingtheneedforthesaidcompensatorymeasures.TheimplementationofthisPCMdoesnotrequireachangetoplanttechnicalspecifications.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

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STLUCIEPLANT-UNITNO1SAFETYINJECZIONTANKANDCONTAINMENTFANCOOLERINSTRUMENTATIONUPGRADEREA-SLN-86&76-11,-13,-21,-23PCM128-187ABSTRACTThisEngineeringPackageaddresseslevel,temperatux'e,andflowinstrumentationupgradefortheSafetyInfectionTank(SIT),ComponentCoolingWaterandContaiameatFanCoolers.TheSafetyIn)ectionTanksarepartoftheSafetyIn)ectionSystemwhichautomaticallydischargesboratedwaterintotheReactorCoolantSystemondepressurizationofRCSasaresultofaLossofCoolantAcciden(levelinstrumentationbeingupgradedmeasurestheSafetyIn)ectionTankwaterlevelandprovidesindicationattheRTGB.TheContainmentFenCoolersarepartoftheContainmentCoolingSystemwhichprovidesthemeansofContainmentheatremovalduringnormaloperationsandintheeveatofaLOCA.TheflowiastrumentatioabeingupgradeddetectslowComponentCoolingWaterflowthroughtheContainmentFanCoolers,providiag'ocalindicationandremoteannunciation.Thetemperaturedetectingelements(thermocouples)attheinletandoutlet'oftheContainmeatFanCoolersusedtomeasuretheductairtempexaturearealsobeingupgraded.TheseinstrumentscurrentlyaredesignatedasNon"-NuclearSafetyRelated.Thiseffortvillupgradeselectedinstxumentatioa,associatedelectricalcircuitloopsandstructuralsupporttoNuclearSafetyRelatedmeetingtherequirementsofUSNRCRegulatoryGuide1.97,Rev3,Category2,TypeDVariable.ThisUSNuclearRegulatoryCommissionrequirementisdefinedasthoseinstrumentsthatx'emaiafunctionalduringallaccidentconditionsandprovideindicationandrecordsformanyvariablesrequiredtofollowthecourseoftheaccen.pecidtSecificallyTypeDvariablesaredefinedasthosevariablesthatprovideinformationtoindicatetheopexationofindividualsafetysysstemsandothersystemsimportanttosafety.Category2providesforequipmentqualificationwhichislessstringentiathatitdoesnotincludeseismicqualificatioa,redundancyorcontinuousdisplaysaadrequiresonlyahigh-reliabilitypowersource.Basedontheusageoftheseinstrumentstomonitorsafetyrelatedequipment,thisEPisclassifiedasNuclearSafetyRelated.ThesafetyevaluationofthispackagehasshownthattheimplementationofthisPCMdoesnotconstituteanunreviewedsafetyquestionandpriorcommissionappzovalforitsimplementationisaotrequiredThisEPhasnoimpactonpleatsafetyendoperationorPlantTechnicalSpecifications.SUPPLEMENT1ThisengineeringpackagerevisionrevisescontrolwiringdiagramsandcablesplicedetailsdealingwiththerevisedConaxthermocoupleelectx'icconductorsealassembly.EnvironmentalQualificationDocumentationPackage8770-A-451-6.0,ContinentalWireandCable,haebeenupdatedtoincludereferencestomodelCC-2200(XLPE)B/MD5-1.Theoriginalsafetyevaluationhaenotbeenaffectedasaresultof.thissupplement.

II SAFETYEVALUATIONP~128-ZS7WithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(1)iftheprobabilityofoccurrenceortheconsequencesofaaaccidentormalfunctionofequipmentimportaattosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ii)ifapossibilityforanaccidentormalfuactionofadifferenttypethananyevaluatedpreviously1ntheSafetyAnalysisReportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThemodificationsincludedinthisEngineeriagPackagedonotinvolveanunreviewedsafetyquestionbecauseofthefollowingreasons:(1)TheprobabilityofoccurrenceandtheconsequencesofanaccidentormalfunctionofequipmeatimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportvillnotbeincreasedbythismodificationbecauseexistingequipmentavailability,redundance,capacity,orfunctionrequ1redtomitigatetheeffects'ofanaccidentareaotaffected.(ii)Theposeibili.tyforanaccidentormalfunctionofadifferenttypethananyevaluatedprevi.ouslyintheSafetyAnalysisReportwillnotbecreatedbythismodificationbecausereplacingmoaitoringinstrumentationwithsimilarreplacementshavingbetterenvironmentalqualificationsdoesnotcreatechangeswhichcouldpostulateaaewaccidentormalfunction.(iii)Themargiaofsafetyasdefinedinthebasesforanytechnicalspeci,ficationisnotreducedsincethi.smodi.ficationinstallsqualifiedthermocouplesandflowswitcheswhichwillenhancethemonitoringoftheContainmentHeatRemovalSystem.Furthermore~thisnewequipmentissei.smicallyandenvironmentallyqua11fiedtowithstandthenormalandaccidentconditionsanticipatediatheareasthattheyareinstalled.Thismodificati.onisfortheupgradeoftheSafetyInjectionSystem,ComponentCoolingWaterSystemaadContainmentCool1ngSysteminstrumentationinordertomeettherequirementsofUSNRCRegulatoryGuide1.97,Ryv3,Category2,TypeDVariable.ThismodificationupgradewillprovideamorereliableandqualifiedinstrumeatatioalooptodetectandmonitorContainmentHeatRemovalSystemoperation.Hence,th1eEPisconsideredNuclearSafetyRelated.Sincethismodif1catioareplacesexistingmonitoringinstrumentationwithquali.fieddevicesandinvolvesnoothermodificatioastosafetyrelatedequipment,thedegreeofprotect1oaprovidedtonuclearsafetyrelatedequipmentieunchanged.TheprobabilityofmalfunctionofequipmhatimportanttosafetypreviouslyevaluatedintheFSARremainsunchanged.Theconsequencesofmalfunctionofequ1pmentimportanttosafetypreviouslyevaluatedintheFSARareunchanged.Thepose1bilityofmalfunctionsofadifferenttypethanthoseanalyzedintheFSARienotcreated.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecifications,nordoesitcreateanunreviewedsafetyquestion.Theforegoingcoastitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionaadpriorCommi.ssionapprovalfortheimplementationofthisPCHisnotrequired.

PCM141-187STLUCIEUNIT1480VSWITCHGEAR1A2&1B2TRANSFORMERREPLACEMENT(REASLN"86-007-10)ABSTRACTDuetoenvironmentalconcernsattendanttopolychlorinatedbiphenyl(PCB)cooliug/insulatingliquids,alltransformersfilledwithPCBarebeingeliminatedfromFP&L'ssystem.Thestationservicetransformersfor480voltswitchgear1A2andlB2arefilledwithPCBcooling/insulatingoil.Eachtransformercontains370gallonsand254gallonsrespectivelyofPCBliquid.ThisEngineeringPackageprovidesforthereplacementoftheexistingPCBfilledstationservicetransformerswithequivalenttransformersofdrytypeconstructionandfortheremovaloftheconcretecurbssurroundingthetransformers.Thecurbsarenolongerrequi.redsincetheirfunctionwastoretainleakageofcooling/insulatingliquidwhichisnolongerpresentinthereplacementtransformers.Stationservicetransformers1A2and1B2performnuclearsafetyrelatedfunctions.BecauseoftheirimportanceinClasslEserviceapplicationsthereplacementtransformersareclassifiedassafetyrelatedinthisEngineeringPackage.Transformers(1A2&1B2)arelocatedintheSwitchgearRoomatElevation43'0"oftheReactorAuxiliaryBuilding.ResultsofthesafetyevaluationconcludethatmodificationspresentedbythisEngineeringPackagedonotconstituteanunreviewedsafetyquestion,donotrequireanychangestothePlantTechnicalSpecificationsanddonotrequirepriorNRCapprovalfortheimplementationofthisPC/M.TheimplementationofthisPC/Mwillnothaveanadverseimpactonplantsafetyoroperations-SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifa,possibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmay3mcreated;or(iii)ifthemargindfsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThisEngineeringPackageaddressedthereplacementofPCBliquidfilled480VstationservicetransformerslA2&1B2locatedonelevation43'ntheReactorAuxiliaryBuildingofUnit1.Thereplacementtransformerswillbefurnisheddimensionallycompatibleandequivalentinelectricalcharacteristicswiththeexistingtransformers.Thephysicalcharacteristicsofthereplacementtransformersaredifferentbecausetheyaredrytype.

PCM141-187Thenewtransformersaresafetyrelatedbecauseoftheirimportancetoessentialplantoperations.Thesenewtransformersperformthesamefunctionastheexistingtransformers1A2and1B2.Thereplacementtransformershavebeenseismicallyandenvironmentallyqualified(References6.18and6.19)andwillbeseismicallymounted.Theexistingseismicqualificationofswitchgearlineups,1A2and1B2willnotbeaffectedbythereplacementofthelA2and1B2PCBfilledtransformerswiththenewdrytypetransformers.Thecurbsdonotperformanysafetyfunction.Theyweredesignedtocontaincooling/insulatingliquidwhichwillnolongerbeused;thereforethesecurbsarenolongerrequired.Basedonthepreceding,thefollowingconclusionscanbemade:(i)TheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARwillnotbeincreasedbecausetheexistingtransformersarebeingreplacedonaone-for-onebasisbytransformersthatareessentiallyequivalentinfunction,capacityandqualifications.Thecurbsdidnotperformasafetyrelatedfunction.Theirremovalvillnothaveanysafetyrelatedimplications.(ii)Thismodificationdoesnotchangetheoperationofthe480Vsafetyrelatedstationservicetransformersandswitchgear.Therefore,thereisnopossibilitythatanaccidentormalfunctionofadifferenttypethananyevaluatedintheFSARmaybecreated.(iii)Thereplacementstationservicetransformersareessentiallyequivalentinpurposeandcapabilitytotheexistingtransformers.Therefore,thismodI.ficationdoesnotreducethemarginofsafetyasdefinedinthebasesforanytechnicalspecification.TheimplementationofthisPC/MdoesnotrequireachangetothePlantTechnicalSpecificationsTheforegoingconstitutesper10CFR50.59(b)thewrittensafety,evaluationwhichprovidesthebasesthatthischangedoesnotInvolveanunreviewedsafetyquestionandpriorNRCapprovalfortheimplementationofthisPC/Misnotrequired-STLUCIEUNIT1480VSMITCHGEAR1A361B3TRANSPORMERREPLACEMENT(REASLN-8607-10)PCM142-187Duetoenvironmentalconcernsattendanttopolychlorinatedbiphenyl(PCB)cooling/insulatingliquids,alltransformersfilledwithPCBaxebeingeliminatedfromPP&L'ssystem.Thepressurizerheatertransformersfor480voltswitchgeax1A3and1B3arefilledwithPCBcooling/insulatingoil.Eachtransformercontains208gallonsofPCBliquid.ThisEngineeringPackageprovidesfoxthereplacementoftheexistingPCBfilledpresaurizerheatertransformerswithequivalenttransformersofdrytypeconstruction,andfortheremovaloftheconcretecurbssurroundingthetransformers.Thecurbsarenolongerrequiredsincetheixfunctionwastoretainleakageofcooling/-insulatingliquid,whichisnolongerpresent.PressurizerheaterstransformersIA3and1B3performnon-nuclearsafetyrelatedfunctions.BecauseoftheirimportanceinpLantopexationsanandbecausetheyarefedfromSafetyRelatedbuses,4160V1A3and1B3,thereplacementtransformersareclassifiedasQualityRelatedinthisEngineeringPackage.Transformers(lA361B3)arelocatedonElevation43'0"oftheReactorAuziliaryBuilding.ResultsofthesafetyevaluationconcludethatmodificationspresentedbythisEngineeringPackagedonotconstituteanunreviewedsafetyquestion,donotrequireanychangestothePlantTechnicalSpecificationsanddonotrequitepriorNRCapprovalfox-theimplementationofthisPC/M.TheimplementationofthisPC/Mwillnothaveanadverseimpactonplantsafetyoroperations.SAFETVEVALUATION~ithrespecttoTitle10oftheCodeofFederalRegulations,PartS0.59>aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentoxmalfunctionofadifferenttypethananyevaluatedpxeviouslyinthesafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThisEngineeringPackageaddressedthexeplacementofPCBliquidfilled480Vpressurizerheatertransformers1A361B3locatedonelevation43'ntheReactorAuxiliaryBuildingofUnit1.Thetransformerssupplypowertothepressurizerheatersandarelocatedinanareaoftheplantcontainingsafety-relatedequipment.The480VPressurizerHeaterTransformerslA3and133donotperformanynuclearsafetyrelatedfunctions,however,becauseoftheirimportancetonormalplantoperationsandbecausetransformers1A3and1B3arefedbysafetyrelated4160VBuses1A3and1B3,thereplacementtransformersareclassifiedasQualityRelatedinthisEngineeringPackage.The'drytype'eplacementtransformexswillbefurnisheddimensionallycompatibleand.equivalentinelectricalcharacteristicswiththeexistingtransformers.

PCM142-187Thephysicalcharacteristicsofthereplacementtransform<<sdifferentbecausetheyaredrytype.ThesenewtxansformexsperformthesamefunctionastheezistingtransformerslA3andlB3.Thereplacementtransformersvill1beseismicallymounted.Thecux'bsdonotperformanysafetyfunction.Theyweredesignedtocontaincooling/insulat1ngliquidwhichwillnolongerbeused>thereforethesecuxbsarenolongerrequired.Basedonthepreceding,thefollowingconclusionscanbemade:(1)Theprobabilityofoccuxrenceortheconsequencesofanaccidentox'alfunctionofequipmentimportanttosafety'reviouslyevaluatedintheFSARwillnotbeincreasedbecausetheexistingtxansformexsarebeingreplacedonaone-foronebasisbytransformexsthatareequivalentinfunction,capacityandelectxicalcharacteristics.Thecurbsdidnotperformasafetyx'elatedfunction,theirremovalwillnothaveanysafetyrelatedimplication.(ii)Thismodificationdoesnotchangetheoperationofthe480Vnon-safetyrelatedpressurizerheatertransformersandswitchgear.Therefore,thereisnopossibilitythatanaccidentormalfunctionofadifferenttypethananyevaluatedintheRSARmaybeczeated.(111)Thereplacementpressurizerheatertransformersazeequivalentinpurposeandfunctiontotheexistingtxansformezsandperformnosafetyrelatedfunctions.Therefore,thismodificationdoesnotreducethemarginofsafetyasdefinedinthebasesforanytechnicalspecification.Theimplementationofth1sPC/Mdoesnotxequ1reachangetotheplantTechnicalSpecifications.ITheforegoingconstitutesper10CRR5059(b)thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorNRCapprovalfortheimplementationofthisPC/Misnotrequix'ed.

PCM143-187TrTLE480VPCBFILLEDTRANSFORMERREPLACEDESCRlPTlONOFCHAN@K/ABSTRACTtEXISTINGPCBFILLED1500KVASTATIONSERVICETRANSFORMERSlAland1BlAREBEINGREPLACEDWITHNON-PCBFILLEDSILICONEIMPREGNATEDDRYTYPETRANSFORMERSTOSATISFYENVIRONMENTALCONCERNSREGARDINGPCB'S.IfftplefftentetionafthisDEEPdoesnotconstituteenunreviearedsefetyquestionnoreffectPlentTechnicelSpecifica-tions.NRCepprovelisnotrequiredpriortaistplementetion.ThisDEEPhesnoirdpectonplentsefetyoroperetion.NUCLEARSAFETYEYALUATLONCHECKLlSTThe~rittenevaluationoftheproposeddesignchangetodemonstratethatthechangedoesnotaltertheplantsdesignbasisandisboundedbythedesignanalysesisattachedtotheDesignEquivalegtEngineeringPackage.Theanswersbelowaresupportedbythisevaluation.TYPEOFCHANGEYesXNoAchangetotheplantasdescribedintheFSAR?YesNoxAchargetoproceduresasdescribedintheFSAR?YesNoX.AtestorexperimentnotdescribedintheFSAR?.YesNoxAchangetotheplanttechnicalspecifications?EFFECTOFCHANCEYesNoxWftltheprobabilityofanaccidentpreviouslyevaluatedintheFSARbeincreased?YesNoxYesNoYesNoYesNoxYesNox'esNo~%illtheconsequencesofanaccidentpreviouslyevaluatedintheFSARbeincreased?MaythepossibilityofanaccidentwhichisdifferentthananyalreadyevaluatedintheFSARbecreated?1VilltheprobabilityofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?%'illtheconsequencesofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?MaythepossibilityofamalhactionofequipmentimportanttosafetydifferentthananyalreadyevaluatedintheFSARbecreated?%illthemarginofsafetyasdefinedinthebasestoany.technicalspecificationbereduced?

PCM152-187SITSAMPLEVALVEASBUILDINGMODIFICATIONDESCRIPTIONOPCHANGE/ABSTRACT:ReviseCWD8770-B-327Sh322toshowas-buildingstateofSITSamplingIsolationValve,I-FCV&3-1Pwiringasfollows:W&BconductorsofH-SBtobeshownconnectedtoTB639:9&10respectivelyinsteadofTB635:7&8asperattachedmarkeddrawing.This.isadrawingchangeonly.Itdoesnotaffectsystemfunctionorqualification.ItdoesnotrequireaTech.Spec.changeanditdoesnotinvolveanunreviewesafetyquestion.NUCLEARSAFETYEVALUATiONCHECKLlSTThewrittenevaluationoftheproposeddesignchangetodemonstratethatthechangedoesnotaltertheplantsdesignbasisandisboundedbythedesignanalysesisattachedtotheDesignEquivalentEngineeringPackage.Theanswersbelowaresupportedbythisevaluation.TYPEOFCHANCEYesNox.AchangetotheplantasdescribedintheFSAR?YesNoxAchangetoproceduresasdescribedintheFSAR?YesI'loxAtestorexperimentnotdescribedintheFSAR?YesNoxAchangetotheplanttechnicalspecifications?EFFECTOFCHANCEYesNoxYesNoxYesNoXYesNoXWilltheprobabilityofanaccidentpreviouslyevaluatedintheFSARbeincreased?WilltheconsequencesofanaccidentpreviouslyevaluatedintheFSARbeincreased?MaythepossibilityofanaccidentwhichisdifferentthananyalreadyevaluatedintheFSARbecreated?WilltheprobabilityofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?YesNo~WilltheconsequencesofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?YesNoxYesNoxMaythepossibilityofamalfunctionofequipfnentimportanttosafetydifferentthananyalreadyevaluatedintheFSARbecreated?Willthemarginofsafetyasdefinedinthebasestoanytechnicalspecificationbereduced?

PCM157-187STLUCIEUNIT1CONTROLELEMBCDRIVESYSTEM6COILPOWERPROGRAMMERPARTLENGTHREMOVALREA-SLN-86&5ThisEngineeringPackage(EP)providesfortheremovalofunusedequipmentintheControlElementDriveSystem(CEDS).Theunusedequipmentwsspreviouslyemployedforpowershapingwithpart-lengthcontrolelements.Thepart-lengthcontrolelementshavebeenxemovedfromthereactor.Theelectroniccomponentsassociatedwiththeseelements(powersupplies,coilpowerprogrammermodules,powershapinggroupmodules,displays,etc.)willberemovedandmaintainedasspares.TheControlElementDriveSystemisnotaNuclearSafetyRelatedSystem(seeFSARSection7.1).Howevex,sincetheCEDSisusedtocontx'olreactoroperation,andsincemodificationstotheRTGBoardmustbereviewedfortheireffectonRTGBseismicqualification,thisEngineeringPackageisclassifiedasQualityRelatedImplementationofthisPCMdoesnotinvolveanunreviewedsafetyquestionorachangetothePlantTechnicalSpecifications.Therefore,pxiorcommissionapprovalfortheimplementationofthisFCMisnotrequired.ImplementationofthisPCMdoesnotaffectthesafetyoroperationoftheplant.

pCN157-187SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulatione,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestioat(1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfuactionofequipmentimportaattosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybe1ncreased:or(11)ifthepossibilityforanaccidentormalfunctioaofadiffereattypetheaanyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforaaytechnicalspecificatioa1sreduced.ThemodificationsiacludedinthisEngiaeeringPackageconsistofthcremovalofnon-functioaingequipment,aotclassifiedassafctymelated,whichhasnoeffectonoperatingplantsystems.Themodificatioaedonotinvolveanunreviewedsafetyquestionbecause:1)Theprobabilityofoccurreaceortheconsequencesofanacc1dentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedareaotincreasedsinceaomodificationismadetoanysafetyrelatedcomponent,system,orfunction.ii)Thereisnopossibilityforanaccideatormalfuactionofadifferenttypethananypreviouslyevaluateds1nceaonewsafetymelatedfunctioaeor.interfaceswithsafetymelatedsystemsarecreatedbythisEP.iii)ThismodificationdoesnotchangethemarginofsafetyasdefinediathebasisforanyTechaicalSpecification,sinceaoequipmeatremovedormodifiedbythisEPaffectsanyparameterrefereacedintheTechnicalSpecifications.ThisEPdoesnotmod1fyequipmentwhichisnucleareafetymelated.However,sincetheControlElementDriveSystemieusedtocontrolreactoroperationaadsiacemodificationstotheRTGBoardmustberev1ewedfortheireffectonRTGBseismicqualification,thisEPisclassifiedas~lityRelated.ThisEPhasaoeffectoncablesorcomponeatsnecessaryforsafeshutdowaoftheplant,oronequipmentontheEssentialEquipmentList.Changestoequipmentandstructuresinvolving10CFR50Appends"R"fireprotectionrequirementshavebeenaddressed.Thus,theproposeddes1gnisiacompliancewithapplicablerequirementsforfireprotection.TheimplementationofthischangedoesnotrequireachangetothePleatTechnicalSpecificatioas.Thcforegoingconstitutes,per10CFR50.59(b),thewritteasafetyevaluationwhichprovidesthebasesthatthischangedoesnot1nvolveanuareviewedsafetyquestioaandpriorCommissionapprovalfortheimplementationofthisPCMisnotrequired.

PCM001-188ST.LUCIEUNITIlSISTllRESEPARATORZEHEATERSHELLREPAIR(REA-SLN-87-031)ThisdesignpackageprovidesthenecessaryengineeringforaddingerosionprotectionfeaturestotheinternalsurfacesoftheMoistureSeparatorReheater{MSR)shells.Theeffortinvolvestheinstallationofchromium-molybdenumlinerplatestotheshellsinthearea(s)beingaffectedbywetsteamimpingement/erosion.Basedonthefailuremodesanalysisand10CFR50.59review,thismodificationdoesnotimpactanysafetyrelatedequipmentandisnotrelieduponforanyaccidentpreventionormitigation.Thusitdoesnotconstituteanunreviewedsafetyquestionandiscorrectlyclassifiedasnon-nuclearsafetyrelated.Implementationofthismodification,therefore,doesnotrequirepriorNRCapproval.Therearenotechnicalspecificationsaffectedandthemodificationswillnotaffectplantsafetyoroperation.

~FUDThisdesignpackageprovidesthenecessaryengineeringforaddingerosionprotectionfeaturestotheinternalsurfacesoftheHoistureSeparatorReheater(HSR)shells.Theeffortinvolvestheinstallationofchromium-molybdenumlinerplatestotheshellsinthearea(s)beingaffectedbywetsteamimpingement/erosion.Thismodificationisclassifiedasnon-nuclearsafetyrelated,sincetheHSRsperformnosafetyrelatedfunctionanddonotinteractwithsafetyrelatedequipment,components,orfunctions.Basedontheaboveandinformationsuppliedinthedesignanalysis,itcanbedemonstratedthatanunreviewedsafetyquestionasdefinedby10CFR50.59doesnotexist.Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreporthasnotbeenincreased.TheHSRsarenotusedinanysafetyanalysisforaccidentsormalfunctionofequipmentand'ssucharenon-safetyrelatedandhavenoeffectonequipmentvitaltoplantsafety.Thepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyreporthasnotbeencreated.Thecomponentsinvolvedinthismodificationhavenosafetyfunctionandnochangeshavebeenmadetotheoperationaldesigntothesystem.oThemarginofsafety-asdefinedinthebasisforanytechnicalspecificationhasnotbeenreduced.Sincethecomponentsinvolveinthismodificationarenotincludedinthebasesofanytechnicalspecification,themarginofsafetyhasnotbeenreduced.10CFR50.59allowschangestoafacilityasdescribedintheFSARifanunreviewedsafetyquestiondoesnof,existandifachangetothetechnicalspecificationsisnotrequired.Asshownintheprecedingsections,thechangeproposedbythisdesignpackagedoesnotinvolveanunreviewedsafetyquestionbecauseeachconcernposedby10CFR50.59thatpertainstoanunreviewedsafetyquestioncanbepositivelyanswered.Also,nochangetotheTechnicalSpecificationsisrequiredbasedontheaboveevaluation.Therefore,priorNRCapprovalisnot.requiredforimplementationofthismodification.

PCM003-188DTITLECondenaex'xanaionJointZminemthtPlateModificationsCRIPTIONOFCHANGE/ABS3RACTtTheexistingimpingementplatedesignisDESinadequateforsatisfactorylong-termperformance.Weldedattachmenentsontheplateshavecontinuouslyfailed,causingtheplatestofallonanddamagecondensertubes.Thenewplatedesigninvolvesnoweldingandwillpreventanyfurteraurea.ehfilTheCondenserisaNon-NuclearSafetyRelatedQualitydandGroupDomponen~o"DssCtNochangestoTechnicalSpecificationsarerequire,antlantnounreviewedsafetyquestionsareinvolved.ThisPCMwillnotaffecpansafetyoroperation.NUCLEARSAFETYEVALUATIONCHECKLISTThewrittenevaluationoftheproposeddesignchangetodemonstratethatthechangedoesnotaltertheplantsdesignbasisandisboundedbythedesignanalysesisattachedtotheDesignEquivalentEngineeringPackage.Theanswersbelow'are.supportedbythisevaluation.YesYesYesYesTYPEOFCHANGENo'AchangetotheplantasdescribedintheFSARVNor"AchangetoproceduresasdescribedintheFSAR'?No.~AtestorexperimentnotdescribedintheFSAR'?Not~Achangetotheplanttechnicalspecifications'?YesYesYesYesYesYesEFFECTOFCHANGENaI~'WilltheprobabilityofanaccidentpreviouslyevaluatedintheFSARbeincreased'?No~WilttheconsequencesofanaccidentpreviouslyevaluatedintheFSARbeincreased'?Na~MaythepossibilityofanaccidentwhichisdifferentthananyalreadyevaluatedintheFSARbecreated'?,Not'illtheprobabilityofamalfunctionofequipmentimportanttosafetypreviauslyevaluatedintheFSARbeincreased?NoLWillthecansequencesofamalfunctianofequipmentimportanttasafetypreviouslyevaluatedintheFSARbe~increased?NoMaythepossibilityafamalfunctionofequipmentimportanttosafetydifferentthananyalreadyevaluatedintheFSARbecreated?NouvWillthemarginofsafetyasdefinedinthebasestoanytechnicalspecificationbereduced'?

PCM005-188METRASCOPEREPIACEMENTSTLUCIE-UNITNO1REA-SLN-87-56-10ABSTRACTStLucie-Unit1currentlyutilizesaMetrascopeSystemtomonitoranddisplaytheControlElementAssembly(CEA)positions.Thissystemwillbereplacedwithanewonewhichhascolorgraphicsandaprogrammablecomputerfordataprocessinganddisplaycreation.Thiswillalleviateexcessivecalibrationtime,provideCEAdisplaysmoreconsistentwithUnit2,andmodifyPre-PowerandPowerDependentInsertionLimits(PPDIL/PDIL)whichresultinrestrictedCEAoperationofseveralinchesatfullpower.Additionally,thereplacementwillresolveeightopenHumanEngineeringDiscrepancies(HEDs)citedagainsttheMetrascopeSystemduringtheDetailedControlRoomDesignReview.TheHEDsrevolvearoundtheexistingsystem'sdisplayinadequaciesandthelackofoperatorcontroloverdisplaygeneration.TheControlElementAssemblyPositionDisplaySystem(CEAPDS)isnotaSafetyRelatedsystemsinceitdoesnotfunctiontoassuretheintegrityofthereactorcoolantboundary,thecapabilityforsafeshutdownofthereactor,orthecapabilitytopreventormitigatetheconsequencesofaccidentswhichcouldresultinoff-siteexposureadescribedin10CFR100.However,theproposedcomponentswillbeseismicallymountedinRTGB-104.ThereforethisEPisclassifiedasQualityRelated.ThesafetyevaluationconcludedthatthemodificationsimplementedbythisEPdonotinvolveanunreviewedsafetyquestionandthatpriorNRCapprovalfortheimplementationofthisEPisnotrequired.Sincethemonitoringfunctionofthesystemwillnotbechangedbytheupgrade,therewillbenoeffectonplantsafetyandoperation.ThereisnochangetotheplantTechnicalSpecifications.SUPPLEMENT1ThissupplementtotheEngineeringPackageaddsacableretractorfortheCEAPDSCRTwhichwillhelpprotectitscablesandanoiseisolatortothe9-powerinput,whichwillpreventapotentialgroundfaultfrombeingtransferredfromthenewCEAPDStotheRPS.Similartotheoriginalissue,thissupplementisQualityRelated.Themodificationsimplementedbythissupplementdonotinvolveanunreviewedsafetyquestion,thereforepriorNRCapprovalforitsimplementationisnotrequired.TherewillbenoeffectonplantsafetyandoperationortothePlantTechnicalSpecifications.

PCM005-188SAFETYEVALUATIONQfthrespecttoTitle10oftheCodeofFederalRegulatione,Part5059,'proposedchangeshallbcdeemedtoinvolveaauareviewedsafetyquestion:(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmeatimportanttosafetypreviouslyevaluatediatheSafetyAnalysisReportmaybeincreased,or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated,or(iii)ifthemarginofsafetyaedefinedinthebasesforanyTechnicalSpecificationisreduced.(i)TheprobabilftyofoccurrenceandtheconsequencesofanaccideatormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAaalysisReportvillnotbeincreasedbythismodificationbecauseitdoesnotmodifyoraffectanySafetyRelatedequfpmentandthenewcomponentsareeefsmicallymounted.Thereforeithaeaoeffectoathefunctionofanyequipmeatrequiredtopreveatortomitigatetheeffectsofanaccident.(ii)ThepossibilityforanaccidentormalfunctfonofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportvillnotbecreatedsincenonewfailuremodesareintroducedwhichcouldchangethefunctionofanySafetyRelatedequipment(iii)ThemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationienotreducedsincethismodificationdoesnotreducetheoperabilityoftherodblockcfrcuitortheCEApoeitfoaindicationsystems.Instead,themodfficationsimplementedbythisEPwillimprovetheoperator'sabilitytodeterminethepositionoftheCEAsaadtoidentifylimitingconditione.TheCoatrolElementAssemblyPositionDisplaySystem(CEAPDS)isnotaSafetyRelatedsystemsinceitdoesnotfunctiontoassuretheintegrityofthereactorcoolantboundary,thicapabilityforsafeshutdownofthereactor,orthecapabilitytopreventormitigatetheconsequencesofaccidentswhichcouldresultinoff-siteexposuresdescribedfn10CFR100.However,theproposedcomponentswillbeseismicallymountedinRTGB-104andqualificationoftheboardhasbeenreviewedtoensureitsseismicintegrity.ThereforethisEPisclassifiedasQualityRelated.TheimplemeatatfonofthisEPdoesaotrequireachangetothePlantTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),themittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunrevfewedsafetyqucstfonandpriorNRCapprovalfortheimplementationofthfePCMfsnotrequired.

i STLUCIEPLANT-UNITNO1RCPSEALCOOLERHEATEXCHANGERTUBELEAKDETECTIONPm006-188ABSTAACTThisEngineeringPackageaddressesthereplacementofexistinglimitswitchesforComponentCoolingWater(CCW)outletvalvesHCV-14-11-A1,A2,BlandB2andminorwiringmodificationstothevalvecontrolcircuits.Thereplacementlimitswitcheswillmodifyvalvepositionindicationsothattheindicatinglightswilldiscriminatebetweentwo(2)conditions:valvefullyclosedandnotfullyclosed~Thewiringmodificationtothevalvecontrolcircuitsconsistso<<e<<<<ngexistingtimedelayrelaystointroducea60secondtimeThi<<imedelayvillallowsufficientCCWflowthroughtheRCPSealCoolerHeatExchangerstonormalixethetemperature,thus,prohibitingtheinitialtemperaturedifferentialfrominitiatinginadvertantvalvecontrollockout.CCWtotheRCpisclassifiedasNon-NuclearSafetyRelatedandnon-seismicaccordingtoStLuciePlant-Unit1(PSL-1)FSARSection9.2.2.3.Also,thevalvepositionindicationcircuitsareNon-NuclearSafetyRelated.Howeverssincethefunctionofthesealcoolerisolationvalvesistoisolatereactorcoolantleakageintothecomponentcoolingsystem,thisEPisclassifiedQualityRelated.Thesafetyevaluationofthispackageindicatesthatneitherthereplacementofthelimitswitchesno>>thevalvecontrolcircuitwiringmodificationsconstituteanunreviewadsafetyquestion,anddonotrequireachangeinthePlantTechnicalSpecifications.Therefore,priorNRCnotificationforimplementationofthisEPisnotrequired.ThisEPhasnoimpactonplantsafetyandoperations.

PCM006-188SAFETYEVhLUATION1threspecttoTitle10oftheCgdeofFederalRegulati.ons>Part~~0.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion.'1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ii)ifthepossibilityforanacc1dentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecificationisreduced.Themodif1cationsincludedinthisEngineeringPackagedonotinvolveanunreviewedsafetyquestionbecauseofthefollowingreasons:(1)TheprobabilityofoccurrenceandtheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalys1sReportwillnotbeincreasedbythismodification.Electricalseparationismaintainedbetweensafetyrelatedwiringandcomponents.Themodificationsprovidedbythispackagehavenoimpactonequipmentimportanttosafetyandintroducenonewfailuremodes.Therefore,thismodificationdoesnotincreasetheprobabilityofanaccidentormalfunctionofequipmentimportanttosafety.(ii)ThepossibilityforanaccidentormalfunctionofadifferenttypethananyeviluatedpreviouslyintheSafetyAnalysisReportwillnotbecreatedbythismodification.Nonewfailuremodeshavebeenintroducedasstatedinsection2.1.8ofthisEP.(iii)Themarginofsafetyasdefinedinthebasesforanytechnicalspecificationisnotreducedsincethismodificat1ondoesnotdegradetheCCVsystem,andtheCCWSealCoolersdonotformthebasesofanyTechnicalSpecification.Asdescribed1nPSARsection9.2.2theComponentCoolingSystemisaclosedloopcoolingwatersystemthatutilicesdemineralisedwatertocoolvariouscomponents.ThemodificationsdescribedinthisPCMinvolvereplacingexistinglimitswitchesandrewiringtheassociatedCCMoutletvalvecircuits.ThesechangesdonotinterrupttheclosedloopComponentCoolingMaterSystemandaretoaNon-NuclearSafetyRelatedvalveindicationfunctionwhichdiscriminatesbetweenafullyclosedandnotfullyclosedvalvepositionHowever,sincethefunctionofthesealcoolerisolationvalvesistoisolatereactorcoolantleakageintothecomponentcoolingsystem,thisEPhasbeendeterminedtobeQualityRelated.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecifications,nordoesitcreateanunreviewedsafetyquestion.Theforegoingconstitutes,perLOCFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthesechangesdonotinvolveanunreviewedsafetyquestionandpriorNRCapprovalfortheimplementationofthisPCMisnotrequired.

PCM007-188(RCPVIBRATIONMONITORINGE(}UIPMENTUPGRADESTLUCIE-UNITNO1REA-SLN-86-018ABSTRACTTheReactorCoolantPump(RCP)VibrationMonitoringSystem1eutilizedtomoaitoxthev1brationoftheRCPshaftsonallfourRCPs.It1smadeupoftworadialprobes(X6Y)located90ooutof.phasewitheachothergustabovethemechanicalsealofeachRCP.VibrationssensedbytheprobesaremonitoredbyfourelectronicmodulesmountedontherearfaceofRTGB-104intheContx'olRoom.ThisEngineeringPackagewillimplementanupgradetotheRCPV1brationMonitoringSystemwhichwillincludethereplacementoftheXandYprobes,theirrelocationtothelowermotorshaftareaofeachpump,andtheadditionofathirdprobe(Keyphasor)inthesameareaofeachpumptoproviderotationalphasepositioninformation.Thefourelectronicmodulesoftheexistingsystemvillbereplacedbytwomodularinstrumentrackscontainingprobemonitorsforalltwelvenewprobes,twopumpsperrack.TheRCPVibrationMonitoringSystemisnotaSafetyRelatedsystemsinceitdoesnotfunctiontoassuretheintegrityofthereactoxcoolantboundary,thecapabilityfoxsafeshutdownofthexeactor,orthecapabilitytopreventormitigatetheconsequencesofaccidents.However,theproposedcomponentswillbeseismicallymountedinRTGB-104.ThereforethisEPieclassifiedasQualityRelated..ThesafetyevaluationconcludedthatthemodificationsintheRTGboardasimplementedbythisEPdonotinvolveanunreviewedsafetyquestionandthatpxiorNRCapprovalfortheimplementationofthisEPisnotrequired.Sincethemonitoringfunctionofthesystemwillnotbechangedbytheupgrade,therewillbenoeffecttoplantsafetyandoperation.ThereisnochangetothePlantTechnicalSpecifications-SUPPLEMENT1Revision1ofthisEngineeringPackagehasbeenissuedtoprovidetheinstallationofcable,conduit,andprobesassociatedvithReactorCoolantPumps(RCPs)iBlandlA2only.Thesafetyevaluationxemaiasvalidwiththeimplementationofthissupplement;thisEPdoesnotinvolveanunreviewedsafetyquestionandpriorNRCapprovalisnotxequiredforiteimplementation.ThisrevisiontotheEPhasnoeffectonplantsafetyoroperatioaanddoesnotinvolveanychangetothePlantTechnicalSpecificatioas.SUPPL1RENT2Revision2ofthisEng1neeringPackagehasbeen1ssuedto11ftallremainingholdpointstoallowtheiastallationofcable,conduit,andprobesassociatedwithReactorCoolantPumps(RCPs)1A1and1B2inordertocompletetheimplementationofthisPCM.Inadditioa,theproximitoxefoxthetvopumpsvillberelocatedinnevelectricalboxes.Thesafetyevaluationremainsvalidviththeimplementationofthissupplement;th1sEPdoesnotinvolveanunreviewedsafetyquestionandpriorNRCapprovalisnotrequiredforitsimplementation.Thisrevisionto'heEPhasnoeffectonplantsafetyoroperationanddoesnotinvolveanychangetothePlantTechnicalSpecifications.

PCM007-188SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFedexalRegulations,Part50.59,apx'oposedchangeshallbedeemedto1nvolveanunreviewedsafetyquestion:(1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmay=beincreased,or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasesfoxanyTechnicalSpecification1sreduced.(1)TheprobabilityofoccurrenceandtheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypxeviouslyevaluatedintheSafetyAnalysisRepoxtwillnotbeincreasedbythemodif1cationsintheRTGboardasimplementedinthisEngineeringPackagebecauseitdoesnotmod1fyanySafetyRelatedequipmentandinvolvestheseismicinstallationofallRTGboardcomponents.Therefore,ithasnoeffectonthefunctionofanyequipmentrequiredtopreventortomitigatetheeffectsofanaccident.(11)Thepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviously1ntheSafetyAnalysisReportwillnotbecreatedsincenonewfailuremodesareintroducedwhichcouldchangethefunctionofanySafetyRelatedequipment.(iii)ThemarginofsafetyasdefinedinthebasesforanyTechnicalSpecificationisnotreducedsincethismodificationdoesnotinterfacewithequipmentlistedintheTechnicalSpecifications.TheRCPVibrationMonitoringSystemisnotaSafetyRelatedsystemsinceitdoesnotfunctiontoassuretheintegrityofthereactorcoolantboundary,thecapabilityforsafeshutdownofthereactor,orthecapabilitytopreventormitigatetheconsequencesofaccidents.However,theproposedcomponentswillbemountedinRTGB-104suchthataseismiceventwillnotcausethemtodamageadjacentSafetyRelatedequipment.ThereforethisEPisclassifiedasQualityRelated.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecifications.Theforegoingcqnsti.tutes,per10CFR50/59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunx'eviewedsafetyquestionandthatpriorCommissionapprovalfortheimplementationofthisPCMisnotrequirdforworktobeperformedintheRTGboard.

STLUCIEPLANT-UNITNO1PCM009-188UPDATEDOPLIMITORQUEEQDOCUMENTPACKAGEANDDISCONNECTSPACEHEATERS(REA-SLN-87-007)ABSTRACTLimitorquevalveoperatorswhoselimitswitchcompartmentshavebeenfurnishedwithspaceheatershavebeenrecognizedbytheNRC(IENotice86"71,"RecentIdentifiedProblemsWithLimitorqueMotorOperators")toposeapotentialhazardtotheinternalwiringoftheLimitorqueoperator.Thehazardarisesfrominternallimitswitchcompartmentwiringpotentiallymakingcontactwiththeenergizedspaceheaterortheheaterbracket.Theresultantinsulationdamagecouldconceivablyresultinthesewiresbecom1nggroundedtothelimitswitchhousingThisEngineeringPackagewillfacilitatetheremovalofpowertothespaceheaterstherebyeliminat1ngtheproblem.TheLimitorquevalveoperatorsofthisEngineeringPackageareaU.SafetyRelatedinasmuchasthevalvestheycontrolperformnuclearsafetyrelatedfunctions.InformationrelatingtodisconnectingpowertothelimitswitchcompartmentspaceheaterswillbeincludedintheEQDocumentationPackageforLimitorquemotoroperators.ItisalsotheintentofthisEngineeringPackagetoremovefromtheLimitorqueEQDocumentationPackageMarathon.1600terminalblockswhicharenotconsidered,atthistime,tobesuitableforuseinEnvironmentalQualification(EQ)applications.Additionallytheuseof3MtapedsplicesisprohibitedinLimitorqueoperators1nsidecontainmentandthisalsowillbereflectedbyrevis1ontotheLim1torqueEQDocPac.Resultsofthesafetyevaluationconcludethatmod1ficationspresentedbythisEngineeringPackagedonotconstituteanunreviewedsafetyquestion,donotrequireanychangestothePlantTechnicalSpecificationsanddonotrequirepriorCommissionapprovalfortheimplementationofthisPC/M.TheimplementationofthisPC/Mwillnothaveanadverseimpactonplantsafetyoroperations.

PCM009-188SAFETYEVALUATIONQithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinth'esafetyanalysisreportmaybecreated;or(iii)ifthemarginofsafetyesdefinedinthebasesforanytechnicalspecificationisreduced.Todeterminetheeffectofremovalofthespaceheaterwithregardtothecriteriaoutlinedin10CFR50.59(a)(1)whichallowsplantchangeswithoutpriorCommissionapproval,providingthatthechangesdonotinvolveachangetoplantTechnicalSpecificationsoranunreviewedsafetyquestion,thefollowingcriteriawereaddressedasrequiredby10CFR50.59(a)(2):1)TheprobabilityofoccurrenceortheconsequencesofadesignbasisaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARisnotincreased.Disconnectingthepowertothe.spaceheatersdoesnotincreasetheprobabilityofoccurrenceortheconsequencesofadesignbasisaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARsinceoperabilityoftheLimitorquemotoroperatorisnotdependentuponhavingthespaceheaterenergized.Limitorquedoesnotrecommendtheuseofenergizedspaceheatersfornormaloperationandhasreportedthattheirqualificationtestingwasconductedwiththespaceheatersde-energized.Limitorquefurnishesspaceheatersforuseduringlongtermvalvestorageinanuncontrolledatmosphere.Problemsrelatingtopotentialmotoroperatorinoperabilit'ywerereportedviaZZNotice86-71.Thisnoticewasinregardtothepossiblityofdamagetothecontrolwiringofthemotoroperatedvalveduetocontactwiththeapaceheater/heaterbracket.PowertothelimitswitchcompartmentspaceheatersinallvalvesinthispackageexceptforfiveauxiliaryfeedwatervalvesisremovedfromterminalsintheMotorControlCenters.Thedeterminatedconductorsaretapedandotherwiseleftfnplace.Thefiveauxiliaryfeedwatermotoroperatedvalveshavemotorspaceheatersaswellaslimitswitchcompartmentapaceheaters.Thelimitswitchcompartmentspaceheaterswereparalleledwiththemotorspaceheatersforthefiveauxiliaryfeedwatervalves.Therefore,thedeterminationofthevalveoperatorlimitswitchcompartmentspaceheatersfortheauxiliaryfeedwatervalveswillbemadeattheterminalsinthevalvelimitswitchcompartmentinordertomaintainthemotorspaceheatersenergized.The120voltfeedertothemotorcompartmentspaceheaterswillbereconnectedtotheterminalsinthelimitswitchcompartmentaswiU.theleadstothevalvemotorenclosurespaceheatertherebykeepingthemotorspaceheaterenergized.Theleadstothelimitswitchcompartmentspaceheaterwi11betapedandleftinplace.

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PCM009-188'SAFETYEVALUATION(Continued)Thesafetyrelatedvalveshavenotbeenphysicallymodifiedandtheiroperationistoremainthesame.Therefore,there.isnochangetotheirseismicorenvironmentalqualification.ProhibitingtheuseofMarathon1600terminalblocksforusewithsafetyrelatedvalvesandprohibitingtheuseof3MtapedsplicesinsideofcontainmentresolvesconcernsregardingtheuseofthisequipmentinviewofNRCquestionregardingtheirsuitablity.2)ThepossibilityofanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthePSARwillnotbecreated.Removingthepowertothespaceheaterswi11havenoaffectontheoperabilityoftheplantmotoroperatedvalves.Asstatedabove,Limitorquedoesnotrecommendtheuseofenergizedspaceheatersexceptforvalvesinstorageandtheirqualificationtestingwasnotconductedwiththeapaceheatersenergized-CurrentlytherearenoMarathon1600terminalblocksinusewithEQrelatedvalvesor3Msplicesinuseincontainment.ThisLimitorqueEQDocPacupdatewillpreventthepossiblityoffutureaccidentsoccurringduetotheuseofthismaterial.3)ThemarginofsafetyasdefinedinthebasisforanyTechnicalSpecificationisnotreduced.Sinceoperabilityoftheplantsafetyrelatedmotoroperatedvalvesisnotaffectedbydisconnectingthespaceheaters,'sincenoMarathon1600terminalblocksareinuseintheplantinassociationwithEQrelatedvalvesandsinceno3Msplicesareinuseincontainment,thebasisforany'lantTechnical.Specificationisunchanged.Therefore,PlantTechnicalSpecificationsareunchangedbydisconnectingthespaceheaterstoplantsafetyrelatedmotoroperatedvalvesorprohibitingtheuseofMarathon1600terminalblocksor3Mspliceincontainment.Theforegoingconstitutesper10CFR50.59(b)thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionor.changetoplantTechnicalSpecifications.CONCLUSION:Itisthereforerecommendedthatspaceheatersbede-energizedforallsafetyrelatedLimitorquemotoroperatorsattheStLuciePlantinresponsetoIEInformationNotice86-71.Thisrecommendationisbaseduponthemanufacturer'srecommendation,uponfavorableindustryandPPLexperiencewithmotoroperatorshavingtheirspaceheatersde-energizedanduponreportedproblemsrelatingtopotentialdamagetotheinternalwiringofthemotoroperatorsasdescribedinIENotice86-71.Unit1motoroperatorshavetheirheatersfedfromcircuitswhicharecommontootherheatersforfansandmotors.TheUnit1apaceheatersausthavetheirpowerleadsliftedattherespectiveMCCsorasdescribedabove.

/q PCM010-188STLUCIEPLANT-UNIT1STATIONAIR/INSXRM9iTAIRPRESSUREINDICATORREPLACEMENTREA-SIR-87-13-10ThisEngineeringPackagexeplacestheezistingvoltagedrivendualindicatingmeter(PI-18-9/PI-18-16)withacurxentdrivendeviceandmodifiesthe4-20mADCcurx'entloopsothatthenewindicatorwillbeinseriesintheloop.Replacementoftheezistingdualindicatorisrequiredduetoitsfailux'e;revisiontotheloopconfigurationwillallowforthereplacementoftheindicatorwithpartsmaintainedinstoresinventory.Thismeterprovidescontrolroomindicationofstationairandinstrumentairpressuxe,neitherofwhichareclassifiedasnuclearsafetyrelatedsystemsThisEPhasnoaffectonanyequipmentrequiredforsafereactoxshutdown,usedtomitigatetheconsequencesofadesignbasesevent(DBE),orcontrolradioactivereleasestotheatmosphereintheeventofaDBE.SincethisEPinvolvestheseismicanalysisofmountingdetailsforequipmentmountedintheReactorTurbineGenexatorBoard(RTGB),thispackageisclassifiedaspolityRelated.TheimplementationofthisEPdoesnotconstituteanunreviewedsafetyquestionnorwoulditsimplementationaffectthePlantTechnicalSpecifications.Thus,CommissionapprovalisnotrequiredpriortoimplementationThisEPhasnoimpactonplanthafetyoroperation.1SAPETYEVALUATIONarithrespecttoTitle10oftheCodeofPederalRegulations,Part50.59,apxoposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestionx(i)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyhnslysisReportmaybeincreased,or(ii)ifthepossibilityfoxanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisrepoxtmaybecreated,or(iii)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.

010-188SAFETYEVALUATION(Coatiaued)'ThemodificatioasincludedinthisEagineerIngPackagedonotInvolveanunrevIewedsafetyquestionbecauses(1)Theprobabilityofoccurrenceorthccoasequeacesofaaaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisnotincreased.Thisieconfirmedbythefollowiag:TheCompressedAirSystem(statioaairaadInstrumentair)servesno'afetyfunctionpexStLucie-UnitJFSARSection9.3.1.1.ThereplacementofthedualpressureindicatorPI-18-9/Pl-18-16hasnoeffectonanynucleaxsafetyrelatedequipmentanditsfailurewillnotincreasetheprobabilityofoccurrenceortheconsequencesofaaaccidentas.IndicatedinSection2.1.8ofthisEP(11)Thereisnopossibilityforanaccideatormalfunctionofadifferenttypethananypreviouslyevaluatedaeconfirmedbythefollowing:ThemodifIcationofthecompressedaIrinstrumentationloopusesthesamecixcuitdesignusedthroughouttheplantandhasbeenpreviouslyevaluatedforbothsafetyandnon-safetyloops.ReplacementofthedualpressureIndicatox'I-18-9/PI-18-16providescontrolroomindicatioaofstationairandiastrumentairpressurebyutilieingacurrentdriveadevice.Thisconfigurationdoesnotintroduceanypossibilityofaccidentormalfunctionnotpreviouslyevaluated.Secsect1on2.1.8ofthisEP.(iii)ThismodificationdoesnotxeduccthemargiaofsafetyasdefinedinthebasesforanytechnicalspecificationsinceithaeaonegativeeffectonsafetyrelatedcomponentsorsystemsasdefinedinanyTechnicalSpecificationsandprovidesforstatioaairandinstrumentaixindicationasoriginallyspecifiedintheStLucie-Uait1FinalSafetyAnalysisRcport.Sincethispackagedoesaotaffectanyequipmentthatisidentifiedasnuclearsafetyrelated,thispackageneednotbeconsiderednucleax'afetyrelated.However,sincetheimplementationofthisPCMxequiresworktobedoneinsidethereactorturbinegeneratorboard(RTGB)>thispackageisclassifiedQualityRelatedastheRTGSisaseismicallydesigaedcontrolpanel.ThisEPdoesnotinvolveanyequipmentontheEssentialEquipmentListandhasnoeffectonsafereactorshutdownoralternateshutdown.Thereareaootherchangestoequipmentwhichinvolve10CFR50Appendix"R"fireprotectIoa{seeAttachment7.1).Implemeatationof~ityRelatedPCM010-188doesnotrequireanychangetothePlaatTechnicalSpecifications.Theforegoingconstitutes,per10CFR50.59(b),thcwr1ttensafety'valuationwhichprovidesthebasesthatt+schangedoesnotinvolveanunreviewedsafetyquestionnorachangetoanyTechnicalSpecificationeaadpriorCommissionapprovalfortheimplementationofthisPCMisaotrequired.

PCM011-188ST.LUCIEUNITIWKWAYNCOSURREA-SLN-87-037Ql~SRACTThisengineeringpackagecoversthemodificationoftheenclosedwalkwaywhichconnectstheReactorAuxiliaryBuildingandthepersonnelhatchenclosureattheReactorContainmentBuilding.Theexistingfiberglasspanelswhichcoverthewalkwayarebeingreplacedwithnon-combustiblematerials.Also,theexistingopening'locatedatthesouthendofthepersonnelhatchenclosurewillbesealedtopreventtheentryofstormwaterintotheRABRCBwalkwayandpersonnelhatchenclosures.TheexistingRABRCBwalkwayandpersonnelhatchenclosuresdonotperformanynuclearsafety-relatedfunctionssothismodificationwillnotbeclassifiedasnuclearsafety-related.However,thismodificationdoesrequiretheinstallationofconcreteexpansionanchorsinSeismicClassIstructuresincludingtheReactorAuxiliaryBuilding.SincereinforcementsteelinSeismicCl.assIstructurescouldpotentiallybedamagedduringinstallationofthismodification,quality-relatedrequirementsareappliedtothisdesign.Asafetyevaluationofthismodificationhasbeenperformedinaccordancewith:$0CFR50.59.ThisevaluationindicatesthatimplementationofthisEngineeringPackagedoesnotinvolveanunreviewedsafetyquestion.Furthermore,theimplementationofthismodificationdoesnotrequireach'angetotheplantTechnicalSpecificationsandhasnodetrimentaleffectonplantsafetyandoperation.Therefore,priorNRCapprovalforimplementationofthismodificationisnotrequired.

FYVAUTONfifthrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion:(i)fftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased,or(ff)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviou'slyintheSafetyAnalysisReportmaybecreated,or(iif)ffthemarginofsafetyasdefinedfnthebasesforanytechnicalspecificationisreduced.Themodificationsincludedinthisengineeringpackagedonotinvolveanunreviewedsafetyquestionbecauseofthefollowingreasons:(i)Theprobabflftyofoccurrenceandtheconsequencesofanaccidentor.malfunctionofequipmentimportanttosafetypreviouslyevaluatedfntheFinalUpdatedSafetyAnalysisReportarenotincreasedbythismodificationbecauseitdoesnotaffecttheavailability,redundancy,capacity,orfunctionofanyequipmentrequiredtomitigatetheeffectsofanaccident.(ff)ThepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyfntheFinalUpdatedSafetyAnalysisReportwillnotbecreatedbythismodificationbecausethemodfficat4onfnvolvesnon-nuclearsafety-relatedstructuresandfailureofanyitemsadded.bythismodificationwillnotimpactanynuclearsafety-relatedfunctions.(iii)Themarginofsafetyasdefinedinthebasesforanytechnicalspecificationfsnotaffectedbythismodificationsincethecomponentsfnvo1vedinthismodificationarenotincludedfnthebasesofanyTechnicalSpecifications.TheRABRCBwalkwayandpersonnelhatchenclosuresareclassifiedasnon-nuclearsafety-related.Ouethelocationofthemodificatfon,failureoftheRABRCBwalkwayenclosureorthemodifiedportionofthepersonnelhatchenclosur'ewillnotaffectanynuclearsafety-relatedequipment.However,thismodificationdoesinvolvetheinstallationofconcreteexpansionanchorsinSeismicClassIstructures.Sincesteelreinforcementinthestructurescouldpotentiallybedamagedduringinstallationoftheanchors,qualfty-relatedrequirementshavebeenappliedtothisdesign.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecifications,nordoesitcreateanunreviewedsafetyquestion.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorNRCapprovalfortheimplementationofthisPCMisnotrequired.

PCM012-1880TITLE:IB&IDInstrumentInverterDrawingChangeDESCRIPTIONOPCHANGE/ABSTRACT:Thischangemodifiesadrawing(Seedrawinglist)toshowthecorrectcircuitnumbersforthe125VDCfeedstotheIB&IDinstrumentinverters.Nophysicalmodificationsarerequired,onlyacorrectiontoadrawing.Nounreviewedsafetyquestionorchangetotechnicalspecifictionisrequired.NUCLEARSAFETYEVALUATIONCHECKLISTThewrittenevaluationoftheproposeddesignchangetodemonstratethatthechangedoesnotaltertheplantsdesignbasisandisboundedbythedesignanalysesisattachedtotheDesignEquivalentEngineeringPackage.Theanswersbelowpresupportedbythisevaluation.TYPEOFCHANCEYesNo~YesNo~YesNo~YesNo~AchangetotheplantasdescribedintheFSAR?AchangetoproceduresasdescribedintheFSAR'?AtestorexperimentnotdescribedintheFSAR?Achange.to:theplanttechnicalspecifications'sEFFECTOFCHANCEYesNo~'esNo~YesNo~fYesNoQ~Willtheprobabilityofanaccident'previouslyevaluated'intheFSARbeincreased?Willtheconsequencesofanaccidentprev'iouslyevaluatedintheFSARbeincreased?MaythepossibilityofanaccidentwhichisdifferentthananyalreadyevaluatedintheFSARbecreated'?WilltheprobabilityofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?YesNo~WilltheconsequencesofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?YesNo~(.MaythepossibilityofamalfunctionofequipmentimportanttosafetydifferentthananyalreadyevaluatedintheFSARbecreated?YesNo~Willthemarginofsafetyasdefinedinthebasestoanytechnicalspecificationbereduced?0191L Pm013-188IlSECURITYLIGHTINGPANELS-RELAYSANDCONTACTORSDESCRIPTIONOFCHANCE/hBSTRACTsThesechaesovldefortherotacernentofafailedASCOre'lautilizedlnSecurityLightingPanel2S,andforthedocumentationof'HwlltcondltlonsAnunrevlewedsafetyquestiondoesnotexistandtherelsnochangetotechnicalsclficatlons.involved~~1emcntNo.1-Thissupplementistoaddpage3a(DesignInterfaceecoranst~oŽdicatethepurchasingquahtyeveonaacmen.osuetyquestiondoesnotemstandthere4nochangetotechnicalspecificati~involved.NUCLEARSAFETYEVALUATIONCHECKLISTThcwrittenevaluationoftheproposeddesignchangetodemonstratethatthechangedoesnotaltertheplantsdesignbasisandisboundedbythedesignanalysesisattachedtotheDesignEquivalentEngineeringPackage.Theanswersbelowaresupportedbythisevaluation.YesNoXYesNoXYesNoXYesNo.TYPEOFCHANCEAchangetotheplantasdescribedintheFSAR?AchangetoproceduresasdescribedintheFSAR?AtestorexperimentnotdescribedintheFSAR?Achangeto.theplant.technicalspecifications?YcsNoYesNoXYesNoYesNoXYesNoXYesNoXYesNoXEFFECTOFCHANCEWilltheprobabilityofanaccidentpreviouslyevaluatedintheFSARbeincreased?WIIItheconsequencesofanaccidentpreviouslyevaluatedintheFSARbeincreased?MaythepossibilityofanaccidentwhichisdifferentthananyalreadyevaluatedintheFSARbecreated?WilltheprobabilityofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?WilltheconsequencesofamalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheFSARbeincreased?MaythepossibilityofamalfunctionofequipmentimportanttosafetydifferentthananyalreadyevaluatedintheFSARbecreated?Willthemarginofsafetyasdefinedinthebasestoanytechnicalspecificationbereduced?

PCM015-188S'UCIEPLANT-UNITNO1ICMLUBEWAERPIPERES~~TMODIFICATIONSABS'iiACTThetornadom'ss'lebarriersaroundtheintakecoolingwaterpumpsareexposedtosaltwatersprayfromthepumppacking.Thebarriersareconstructedofcoatedca-bonsteelandhavesufferedcorrosionfromthesaltwaterexposure.Inparticular,thestructuralmembersnearthebottomoftheenclosureonthe.eastandwestfaceshaveexperiencedseveredeterioration.SeveralofthesemembersfurnishsupportforICWlubewate"systempiperestraints.Anevaluationoftheas-foundconditionisbeingperformedaspartoftheoveralleffortassociatedwiththedispositionofNCR1-133.FendingalongtermsolutiontocorrecttherootcausesofthecorrosionprobloblemthisEngineeringPackageisbeingissuedtomodifythosecorrodedstructuralelementswhichareintegralpartsofthepiperestraints.ThisEngineeringPackagedoesnotinvolveanunreviewedsafetyquestionandhasnoeffectonplantsafetyoroperation,nordoesitrequireachangetotheplantTechnicalSpecificationsThesysteminvolvedisclassifiedasSafetyRelated,consequentlythisEngineeringPackageisalsoclassifiedasSafetyRelated.

PCM015-188SAFETYEVALUATIONWithrespecttoTitle10oftheCodeofFederalRegulations,Part50.59,aproposedchangeshallbedeemedto1nvolveanunrevtewedsafetyquestion:(1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheSafetyAnalysisReportmaybeincreased;or(ii)ifthepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyintheSafetyAnalysisReportmaybecreated;or(iii)ifthemarginofsafetyasdefinedinthebasisforanytechnicalspecification1sreduced.ThisEngineeringPackageprovidesmodificat1onstopiperestraintsfortheICWlubewatersystem,whichisasafetyrelatedsystem.Accordingly,thisEngineeringPackagehasbeenclassifiedasSafetyRelated.Itdoesnotinvolveanunreviewedsafetyquestion.Thefollowingarethebasesforthisconclusion:(1)Theprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedisnotincreasedsincethismodificationrestoresandenhancestheoriginaldesignmarginoftheaffectedrestraintsandw111beperformedinaccordancewithSafetyRelatedrequirements,hencetherecanbenoimpactonanySafetyRelatedstructures,systems,orequipment.(11)ThereisnopossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslysincethereisnopotentialfortheinteractionofthesemodificationswithanySafetyRelatedequ1pmentorsystemsotherthantheICWlubewatersystemitselfandtheICWpumpmissilebarriertowhichtheaffectedrestraintsareattached;therestorationofthesecomponentstotheiroriginaldesignmarginwillnotaffectanysafetyrelatedsystemsorequipment.(iii)Thismodificationdoesnotchangethemarginofsafetyasdefinedinthebasisforanytechnicalspecificationasthemod1ficationshavebeendesignedtothesamecriteriaastherestraintsofwhichtheyareapart.~'heimplementationofthisEngineeringPackagedoesnotrequireachangetoplanttechnicalspecif1cations.Theforegoingconstitutes,per10CFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunrevtewedsafetyquestionoraTechnicalSpecificationchangeandthuspriorCommissionapprovalfortheimplementationofthisEngineer1ngPackageisnotrequired.

PCM018-188FLORIDAPSKR&LIGHTCOMPANYSTLUCIEPLANT-UNITNO1CONDENSATEPUMPDISCHARGESAMPLINGLINESREA-SLN-86%61-92ABSTRACTThisEngineeringPackageprovidesdetailsfortheadditionofcondensatesamplingpointsdownstreamofeachcondensatepump(lA,1B,1C)andinthecommondischargelineforallthepumps.Italsoprovidesfortheconnectionofthesesamplepoints,throughavalvemanifold,toanexistingsamplelinetotheChemicalAnalyzerintheColdChemistryLaboratory.~sEPisclassifiedasnon-safetyrelatedsinceitprovidesfora-modificationtoanon-safetyrelatedsystem.ThesafetyevaluationhasshownthatthisEPdoesnotconstituteanyunreviewedsafetyquestion.TheimplementationofthisEPdoesnotrequireachangetothePlantTechnicalSpecification;thereforepriorNRCnotificationforimplementationoftheEPisnotrequired.Thissamplingsystemisnon-safetyrelatedandwillhavenoeffectonequipmentvitaltoplantsafety,norwilliteffectplantoperation.

PCN018-188SAFETYEVALUATEONarithrespecttoTitle10oftheCodeofFederalRegulat1ons,Part50.59,aproposedchangeshallbedeemedtoinvolveanunreviewedsafetyquestion;(1)iftheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunct1onofequipmentimportanttosafetypreviouslyevaluatedinthesafetyanalysisreportmaybeincreased;or(ii)ifapossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviouslyinthesafetyanalysisreportmaybecreated;or(111)ifthemarginofsafetyasdefinedinthebasesforanytechnicalspecificationisreduced.ThisEPprovidesfortheadditionofsamplingpointsinthecondensatelines,connectionofthesepointstoavalvemanifoldstationandthentotheexistingcommonlinetotheColdChemistryLab.Stainlesssteeltubingwithcompressionfittingswillbeusedforthesamplelines.TheEPhasbeenclassifiedasnon-safetyrelatedanddoesnotinvolveanunreviewedsafetyquestionbecause-(1)Theprobabilityofoccurxenceox'heconsequencesofanaccidentormalfunctionofequipmentimpox'tanttosafetypreviouslyevaluatedinthesafetyanalysisreportisnotincreased.TheStLucieUnitNolFSAR,Section10.4,"SteamandPowerConversionSyst:em",statesthatthefeaturesandcomponentsofthissystem,whichincludesthecondensatesystem,servenosafetyfunctionsincetheyaxenotrequiredforsafeshutdownortomitigatetheeffectsofaLOCA.Thismodificationisonanon-safetyrelatedsystemandwillhavenoeffectonequipmentvitaltoplantsafety.(11)Thepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedpreviously1nthesafetyanalysisreportisnotcxeated.Thecomponentsinvolvedinthismodificationhavenosafetyrelatedfunctionandnochangeshavebeenmadetotheoperationaldesignofthesystem.(iii)Themarg1nofsafetyasdefined1nthebasesforanyTechnicalSpecificationisnotaffectedbythisP(X,sincethecomponentsinvolvedinthismodificationarenotincludedinthebasesofanyTechn1calSpecification.TheimplementationofthisPQ4doesnotrequireachangetotheplantTechnicalSpecifications.Theforegoingconstitutes,perlOCFR50.59(b),thewrittensafetyevaluationwhichprovidesthebasesthatthischangedoesnotinvolveanunreviewedsafetyquestionandpriorCommiss1onapprovalfortheimplementationofthisP(Hisnotrequired.