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| {{#Wiki_filter:/'CATEGORY1REGULATRYINFORMATIONDISTRIBUTXOSYSTEM(RXDS)IACCESSIONNBR:98FACXL:50-335St50~389StAUTH.NAMEKUNDALKAR,R.S.RECIP.NAME03190069DOC.DATE:98/03/11'OTARIZED:YESLuciePlant,Unit1,FloridaPowerELightCo.LuciePlant,Unit2,FloridaPower6LightCo.AUTHORAFFILIATIONFloridaPower&.LightCo.RECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET¹0500033505000389 | | {{#Wiki_filter:/'CATEGORY1REGULATRYINFORMATION DISTRIBUTXO SYSTEM(RXDS)IACCESSION NBR:98FACXL:50-335 St50~389StAUTH.NAMEKUNDALKAR,R.S. |
| | RECIP.NAME03190069DOC.DATE: |
| | 98/03/11'OTARIZED: |
| | YESLuciePlant,Unit1,FloridaPowerELightCo.LuciePlant,Unit2,FloridaPower6LightCo.AUTHORAFFILIATION FloridaPower&.LightCo.RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET¹0500033505000389 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Submits90-dayresponsetoGL97-05;"SteamGeneratorTubeInspTechniques."DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD2-3LAGLEAVES,WCOPIESLTTRENCL1.111RECIPIENTIDCODE/NAMEPD2-3PDCOPIESLTTRENCL11E0INTERNAL:ACRS.NRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS3EXTERNAL:NOAC111111111011ILECENRRDE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDR1111111111DNNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATIONiCONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR14ENCL13 Jt1I FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34S57March11,1998L-98-7310CFR50.410CFR50.54(0U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555RE:St.LucieUnits1and2DocketNos.50-335and50-389GenericLetter97-05-ResonseTheFloridaPowerandLightCompany(FPL)responsestoGenericLetter(GL)97-05,SteamGeneratorTubeInspectionTechniques,forSt.LucieUnits1and2isattached.Thegenericletterrequested,within90days,thatlicenseesprovidecurrentinformationregardingtheuseofsizingtechniquesattheirfacilities.OnDecember17,1997,theNRCissuedGL97-05requestinglicenseestoverifycompliancewithAppendixBto10CFR50andthetechnicalspecifications,andtomaintainareasonablelevelofassurancethatstructuralandleakageintegritymarginsforsteamgeneratortubesaresatisfied.TheNRCconcludedthatitisappropriateforthelicenseestoreviewthetypesofsteamgeneratortubeindicationsthatarebeingleftinservicebasedonsizing,theinspectionmethodbeingusedtoperformthesizingforeachtypeofindication,andthetechnicalbasisfortheacceptabilityofeachinspectionmethod..TheattachedinformationisprovidedpursuanttotherequirementsofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f).Thislettercontainsnonewregulatorycommitments.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,*;v<.iRajiv.KundalkarVicePresidentNuclearEngineeringRSK/GRMAttachmentcc:RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant9803i900b99803iiPDRADOCK05000335PPDRanFPLGroupcompanyll!ill!ffff!lflllfllllNffffflJfffffff rIf' | | Submits90-dayresponsetoGL97-05;"SteamGenerator TubeInspTechniques." |
| 'MSt,LucieUnits1and2DocketNos.50-335and50-389L-98-73Page2STATEOFFLORIDACOUNTYOFST.LUCIERajivS.Kundalkarbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,Engineering,fortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.ajivS.KundalkarSTATEOFFLORIDACOUNTYQF~SworntoandsubscribedbeforemehiIIdyf~IYlC,19~8byR.S.Kundalkar,whoispersonallyknowntome.NameofNotaryPubic-StateofFloridaLeslloJ.WhlbNell.a..*!MYCOMMISSIONfCCQ6f83B(PIAESMay12,200f"~igni'"'ONOTOTHRUTROYFAlNNSURANCE,INC.(Print,typeorstampCommissionedNameofNotaryPublic) hIjIIINihil'.lt'h~j!lI)("j,h)hl"f-')hII)hIL' ISt.LucieUnits1and2DocketNos.50-335and50-389L-98-73AttachmentPage1NRCRequest:Within90daysofthedateofthisgenericletter,addresseesaretosubmitawrittenresponsethatincludesthefollowinginformation:(1)whetheritistheirpracticetoleavesteamgeneratortubeswithindicationsinservicebasedonsizing,(2)iftheresponsetoitem(1)isaffirmative,thoselicenseesshouldsubmitawrittenreportthatincludes,foreachtypeofindication,adescriptionoftheassociatednondestructiveexaminationmethodbeingusedandthetechnicalbasisfortheacceptabilityofthetechniqueused.NRCRequestPartI:WhetheritistheirpracticetoleavesteamgeneratortubeswithindicationsinservicebasedonsizingFPLResponsePart1:TheUnit1steamgeneratorsareBWIreplacementunits,andtheUnit2steamgeneratorsareCombustionEngineeringSeries3410.ItiscurrentlythepracticeforSt.LucieUnits1and2toleavesteamgeneratortubeswithmechanicalwearindicationsatsupportstructuresinservicebasedonsizing.NoothertypeofserviceinduceddegradationisinservicebasedonsizingforthecurrentcycleofoperationforSt.LucieUnits1and2.Specifically,steamgeneratortubeswithmechanicalwearindicationswhichcanbesizedaslessthantheTechnicalSpecificationvalueof40%ofthenominaltubewallthicknessareleftinservice.SteamgeneratortubeinspectionsforpreviousoperatingcyclesincludedsizingofIGA/SCCindicationsinadditiontomechanicalwearindications,asdiscussedabove.SizingofIGA/SCCindicationswaslastconductedduringtheSpring1996inspectionatSt.LucieUnit1.Inthe1996inspection,IGA/SCCindicationswhichwerelocatedinthesludgepileregion,orateggcratetypetubesupportstructures,remainedinserviceifsizedaslessthantheTechnicalSpecificationlimitof40%ofthenominaltube-wallthickness.IGA/SCCindicationsatotherlocationsinthesteam St.LucieUnits1and2'ocketNos.50-335and50-389L-98-73AttachmentPage2generators(i.e.,tubeexpansiontransitions,freespans,anddrilledholetubesupports)werepluggedondetectionwithoutregardtosizing.TheSt.LucieUnit1steamgeneratorswerereplacedinDecember1997.Therefore,thereisnoserviceinduceddegradationknowntoexistinthecurrentcycleofoperation.ThefirstinserviceinspectionofthereplacementsteamgeneratorsisscheduledfortheFall1999refuelingoutage(SL1-16),andaplugondetectionapproachisplannedforIGA/SCCtypeindications.AtSt.LucieUnit2,sizingofIGA/SCCindicationswaslastconductedduringtheFall1995inspection.Inthe1995inspection,asmallnumberofpossibleIGA/SCCindications(i.e.,approximately43)weresizedaslessthantheTechnicalSpecificationlimitof40%ofthenominaltubewallthicknessandremainedinservice.SizingofIGA/SCCindicationswasnotdoneduringtheSpring1997inspection,andaplugondetectionapproachwasused.Therefore,noIGA/SCCindicationswereleftinservicebasedonsizingforthecurrentcycleofoperationatSt.LucieUnit2.NRCRequestPart2:Iftheresponsetoitem(I)isafhrmative,thoselicenseesshouldsubmitavvrittenreportthatincludes,foreachtypeofindication,adescriptionoftheassociatednondestructiveexaminationmethodbeingusedandthetechnicalbasisfortheacceptabilityofthetechniqueused.FPLResponsePart2:B~kd-ThIpidylydpdiiiiqadighillyimplementtheguidanceofNEI97-06,SteamGeneratorProgramGuidelines,nolaterthanthefirstrefuelingoutagestartingafterJanuary1,1999.AsspecifiedinNEI97-06,eachutilityistofollowtheinspectionguidelinescontainedinthelatestrevisionoftheEPRIPWRSteamGeneratorExaminationGuidelines.AppendixH,"PerformanceDemonstrationforEddyCurrentExamination,"ofEPRIPWRSteamGeneratorExaminationGuidelines,Revisions3through5,provideguidanceonthequalificationofsteamgeneratortubingexaminationtechniquesandequipmentusedtodetectandsizeflaws.Revision4oftheEPRIguidelinesisapplicabletothemostrecentinserviceinspectionsatSt.LuciePlant.PerEPRIguidelines,damagemechanismsaredividedintothefollowingcategoriesforqualification:thinning,pitting,wear,outsidediameterintergranularattack/stress-corrosioncracking(IGA/SCC),primary-sideSCC,andimpingementdamage. | | DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: |
| St.LucieUnits1and2DocketNos.50-335and50-389L-98-73AttachmentPage3Forqualificationpurposes,testsamplesareusedtoevaluatedetectionandsizingcapabilities.Whilepulledtubesamplesarepreferred,fabricatedsamplesmaybeused.Iffabricatedtestsamplesareused,thesamplesareverifiedtoproducesignalssimilartothoseobservedinthefieldintermsofsignalcharacteristics,signalamplitude,andsignal-to-noiseratio.SamplesareexaminedtodeterminetheactualthroughwalldefectmeasurementsaspartoftheAppendixHqualificationprocess.ProceduresdevelopedinaccordancewithAppendixHspecifytheessentialvariablesforeachtechnique.Essentialvariablesareassociatedwithanindividualinstrument,probe,cable,oron-siteequipmentconfiguration.Additionally,certaintechniqueshaveundergonetestingandreviewtoquantifysizingperformance.Thesizingdatasetincludesthedetectiondatasetforthetechniqueusedwithadditionalrequirementsfornumberandcompositionofthegradingunits.SizinTechniues-ForthecurrentcycleofoperationforSt.LucieUnit2,sizingtechniqueswereusedduringsteamgeneratorinspectionstoleavetubeswithmechanicalwearindicationsinservicebasedonsizing.Forpreviouscyclesofoperation,asdiscussedintheresponsetoitem(1)above,sizingtechniqueswerealsousedtoleaveIGA/SCCindicationsinservicebasedonsizing.TheSt.LucieUnit1steamgeneratorswerereplacedinDecember1997,andforthecurrentcycleofoperationatSt.LucieUnit2,aplugondetectionapproachforIGA/SCCindicationswasused.Therefore,mechanicalwearistheonlytypeofserviceinduceddegradationwhichremainsinservicebasedonsizingforthecurrentcycleofoperation.ThebasisforapplicationofthesizingtechniquesistheconductoftheexaminationsundertheSt.LuciePlantQualityAssuranceProgramfollowingtherequirementsofSectionsXIandVoftheASMECode,1989EditionandRegulatoryGuide1.83.Additionalsupportforsizingdegradation-specificmechanismsisprovidedbythequalificationdatasetsinAppendixHtotheEPRIPWRSteamGeneratorExaminationGuidelines.*MechanicalWear-Formechanicalwearatverticalanddiagonalstrapsandothersupportstructures,sizingisaccomplishedusingthe400/100Khzdifferentialmixorthe400/100Khzabsolutemixofthebobbinprobe.Acalibrationcurveforverticalmaximumamplitudeisdeterminedbasedonapplicablestandardswhichreplicatethedamagemechanismtypeandquantity.Thecalibrationcurverepresentsthefullrangeofexpecteddepths.Thesizingqualificationisbasedon64sampledatapointswhichwereusedfortheAppendixHtechniquequalificationprovidedintheEPRIguidelines.Thesamplesrangedindepthfrom4%to78%throughwalldepth.Thistechniquehasagreaterthan80%probabilityofdetectionata90%confidencelevel,andarootmeansquaresizingerroroflessthan5%through-wall. | | GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD2-3LAGLEAVES,W COPIESLTTRENCL1.111RECIPIENT IDCODE/NAME PD2-3PDCOPIESLTTRENCL11E0INTERNAL: |
| St.LucieUnits1and2DocketNos.50-335and50-389L-98-73AttachmentPage4IGA/SCCatSludePileReionsandEcrateTeSuorts-ForSt.LucieUnit1,adetailedtechnicalbasisfortheacceptabilityofthetechniqueforsizingIGA/SCCtypeindicationswasprovidedtotheNRCinFPLlettersL-96-166,SteamGeneratorTubeInspection,RequestforAdditionalInformation(RAI)Response,L-96-273,SteamGeneratorRunTimeAnalysisforCycle14andL-97-141,DoseAssessmentCorrection,Cycle14SteamGeneratorRunTimeAnalysis.ThiscorrespondenceprovidesaruntimeanalysisforSt.LucieUnit1inaccordancewithguidanceprovidedintheDraftRegulatoryGuide,SteamGeneratorTubeIntegrity,DraftRegulatoryGuide1.121,BasesforPluggingDegradedPWRSteamGeneratorTubesandGenericLetter95-05,Voltage-BasedRepairCriteriafor)WestinghouseSteamGeneratorTubesA@ectedbyOutsideDiameterStressCorrosionCracking.ForsteamgeneratortubeinspectionsthroughtheFall1995atSt.LucieUnit2,atechnicalbasisfortheacceptabilityofthetechniqueforsizingIGA/SCCtypeindicationsisprovidedinEPRINP-5397-LD,LaboratoryEvaluationofSteamGeneratorTubes120/12,79/9,and59/95FromSt.LucieUnit1,August,1987.TheEPRIreportconcludesthatthefieldeddy-currentresultsshowedgoodcorrelationwiththedefectdepthsandisconservativeinsizingthedefects.InspectionandsizingtechniquesusedatSt.LucieUnit2werethesameasthoseusedatSt.LucieUnit1fordetectionandsizingofIGA/SCCindications.Asdiscussedintheresponsetoitem(I)above,sizingofIGA/SCCindicationswasabandonedaftertheFall1995inspectionatSt.LucieUnit2,andaftertheSpring1996inspectionatSt.LucieUnit1.TheSt.LucieUnit1steamgeneratorswerereplacedinDecember1997.Therefore,mechanicalwearistheonlytypeofserviceinduceddegradationwhichremainsinservicebasedonsizingforthecurrentcycleofoperationattheSt.LuciePlant. | | ACRS.NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3EXTERNAL: |
| | NOAC111111111011ILECENRRDE/EMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR1111111111DNNOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATIONi CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR14ENCL13 Jt1I FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34S57March11,1998L-98-7310CFR50.410CFR50.54(0U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555RE:St.LucieUnits1and2DocketNos.50-335and50-389GenericLetter97-05-ResonseTheFloridaPowerandLightCompany(FPL)responses toGenericLetter(GL)97-05,SteamGenerator TubeInspection Techniques, forSt.LucieUnits1and2isattached. |
| | Thegenericletterrequested, within90days,thatlicensees providecurrentinformation regarding theuseofsizingtechniques attheirfacilities. |
| | OnDecember17,1997,theNRCissuedGL97-05requesting licensees toverifycompliance withAppendixBto10CFR50andthetechnical specifications, andtomaintainareasonable levelofassurance thatstructural andleakageintegrity marginsforsteamgenerator tubesaresatisfied. |
| | TheNRCconcluded thatitisappropriate forthelicensees toreviewthetypesofsteamgenerator tubeindications thatarebeingleftinservicebasedonsizing,theinspection methodbeingusedtoperformthesizingforeachtypeofindication, andthetechnical basisfortheacceptability ofeachinspection method..Theattachedinformation isprovidedpursuanttotherequirements ofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f). |
| | Thislettercontainsnonewregulatory commitments. |
| | Pleasecontactusifthereareanyquestions aboutthissubmittal. |
| | Verytrulyyours,*;v<.iRajiv.Kundalkar VicePresident NuclearEngineering RSK/GRMAttachment cc:RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant9803i900b9 9803iiPDRADOCK05000335PPDRanFPLGroupcompanyll!ill!ffff!lflllfllllNffff flJfffffff rIf' |
| | 'MSt,LucieUnits1and2DocketNos.50-335and50-389L-98-73Page2STATEOFFLORIDACOUNTYOFST.LUCIERajivS.Kundalkar beingfirstdulysworn,deposesandsays:ThatheisVicePresident, Engineering, fortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee. |
| | ajivS.Kundalkar STATEOFFLORIDACOUNTYQF~Sworntoandsubscribed beforemehiIIdyf~IYlC,19~8byR.S.Kundalkar, whoispersonally knowntome.NameofNotaryPubic-StateofFloridaLeslloJ.WhlbNell.a..*!MYCOMMISSION fCCQ6f83B(PIAESMay12,200f"~igni'"'ONOTOTHRUTROYFAlNNSURANCE, INC.(Print,typeorstampCommissioned NameofNotaryPublic) hIjIIINihil'.lt'h |
| | ~j!lI)("j,h)hl"f-')hII)hIL' ISt.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page1NRCRequest:Within90daysofthedateofthisgenericletter,addressees aretosubmitawrittenresponsethatincludesthefollowing information: |
| | (1)whetheritistheirpracticetoleavesteamgenerator tubeswithindications inservicebasedonsizing,(2)iftheresponsetoitem(1)isaffirmative, thoselicensees shouldsubmitawrittenreportthatincludes, foreachtypeofindication, adescription oftheassociated nondestructive examination methodbeingusedandthetechnical basisfortheacceptability ofthetechnique used.NRCRequestPartI:Whetheritistheirpracticetoleavesteamgenerator tubeswithindications inservicebasedonsizingFPLResponsePart1:TheUnit1steamgenerators areBWIreplacement units,andtheUnit2steamgenerators areCombustion Engineering Series3410.Itiscurrently thepracticeforSt.LucieUnits1and2toleavesteamgenerator tubeswithmechanical wearindications atsupportstructures inservicebasedonsizing.Noothertypeofserviceinduceddegradation isinservicebasedonsizingforthecurrentcycleofoperation forSt.LucieUnits1and2.Specifically, steamgenerator tubeswithmechanical wearindications whichcanbesizedaslessthantheTechnical Specification valueof40%ofthenominaltubewallthickness areleftinservice.Steamgenerator tubeinspections forpreviousoperating cyclesincludedsizingofIGA/SCCindications inadditiontomechanical wearindications, asdiscussed above.SizingofIGA/SCCindications waslastconducted duringtheSpring1996inspection atSt.LucieUnit1.Inthe1996inspection, IGA/SCCindications whichwerelocatedinthesludgepileregion,orateggcratetypetubesupportstructures, remainedinservice ifsizedaslessthantheTechnical Specification limitof40%ofthenominaltube-wall thickness. |
| | IGA/SCCindications atotherlocations inthesteam St.LucieUnits1and2'ocketNos.50-335and50-389L-98-73Attachment Page2generators (i.e.,tubeexpansion transitions, freespans,anddrilledholetubesupports) werepluggedondetection withoutregardtosizing.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997.Therefore, thereisnoserviceinduceddegradation knowntoexistinthecurrentcycleofoperation. |
| | Thefirstinservice inspection ofthereplacement steamgenerators isscheduled fortheFall1999refueling outage(SL1-16), |
| | andaplugondetection approachisplannedforIGA/SCCtypeindications. |
| | AtSt.LucieUnit2,sizingofIGA/SCCindications waslastconducted duringtheFall1995inspection. |
| | Inthe1995inspection, asmallnumberofpossibleIGA/SCCindications (i.e.,approximately 43)weresizedaslessthantheTechnical Specification limitof40%ofthenominaltubewallthickness andremainedinservice.SizingofIGA/SCCindications wasnotdoneduringtheSpring1997inspection, andaplugondetection approachwasused.Therefore, noIGA/SCCindications wereleftinservicebasedonsizingforthecurrentcycleofoperation atSt.LucieUnit2.NRCRequestPart2:Iftheresponsetoitem(I)isafhrmative, thoselicensees shouldsubmitavvrittenreportthatincludes, foreachtypeofindication, adescription oftheassociated nondestructive examination methodbeingusedandthetechnical basisfortheacceptability ofthetechnique used.FPLResponsePart2:B~kd-ThIpidylydpdiiiiqadighillyimplement theguidanceofNEI97-06,SteamGenerator ProgramGuidelines, nolaterthanthefirstrefueling outagestartingafterJanuary1,1999.Asspecified inNEI97-06,eachutilityistofollowtheinspection guidelines contained inthelatestrevisionoftheEPRIPWRSteamGenerator Examination Guidelines. |
| | AppendixH,"Performance Demonstration forEddyCurrentExamination," |
| | ofEPRIPWRSteamGenerator Examination Guidelines, Revisions 3through5,provideguidanceonthequalification ofsteamgenerator tubingexamination techniques andequipment usedtodetectandsizeflaws.Revision4oftheEPRIguidelines isapplicable tothemostrecentinservice inspections atSt.LuciePlant.PerEPRIguidelines, damagemechanisms aredividedintothefollowing categories forqualification: |
| | : thinning, pitting,wear,outsidediameterintergranular attack/stress-corrosion cracking(IGA/SCC), |
| | primary-side SCC,andimpingement damage. |
| | St.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page3Forqualification |
| | : purposes, testsamplesareusedtoevaluatedetection andsizingcapabilities. |
| | Whilepulledtubesamplesarepreferred, fabricated samplesmaybeused.Iffabricated testsamplesareused,thesamplesareverifiedtoproducesignalssimilartothoseobservedinthefieldintermsofsignalcharacteristics, signalamplitude, andsignal-to-noise ratio.Samplesareexaminedtodetermine theactualthroughwalldefectmeasurements aspartoftheAppendixHqualification process.Procedures developed inaccordance withAppendixHspecifytheessential variables foreachtechnique. |
| | Essential variables areassociated withanindividual instrument, probe,cable,oron-siteequipment configuration. |
| | Additionally, certaintechniques haveundergone testingandreviewtoquantifysizingperformance. |
| | Thesizingdatasetincludesthedetection datasetforthetechnique usedwithadditional requirements fornumberandcomposition ofthegradingunits.SizinTechniues-Forthecurrentcycleofoperation forSt.LucieUnit2,sizingtechniques wereusedduringsteamgenerator inspections toleavetubeswithmechanical wearindications inservicebasedonsizing.Forpreviouscyclesofoperation, asdiscussed intheresponsetoitem(1)above,sizingtechniques werealsousedtoleaveIGA/SCCindications inservicebasedonsizing.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997,andforthecurrentcycleofoperation atSt.LucieUnit2,aplugondetection approachforIGA/SCCindications wasused.Therefore, mechanical wearistheonlytypeofserviceinduceddegradation whichremainsinservicebasedonsizingforthecurrentcycleofoperation. |
| | Thebasisforapplication ofthesizingtechniques istheconductoftheexaminations undertheSt.LuciePlantQualityAssurance Programfollowing therequirements ofSectionsXIandVoftheASMECode,1989EditionandRegulatory Guide1.83.Additional supportforsizingdegradation-specific mechanisms isprovidedbythequalification datasetsinAppendixHtotheEPRIPWRSteamGenerator Examination Guidelines. |
| | *Mechanical Wear-Formechanical wearatverticalanddiagonalstrapsandothersupportstructures, sizingisaccomplished usingthe400/100Khzdifferential mixorthe400/100Khzabsolutemixofthebobbinprobe.Acalibration curveforverticalmaximumamplitude isdetermined basedonapplicable standards whichreplicate thedamagemechanism typeandquantity. |
| | Thecalibration curverepresents thefullrangeofexpecteddepths.Thesizingqualification isbasedon64sampledatapointswhichwereusedfortheAppendixHtechnique qualification providedintheEPRIguidelines. |
| | Thesamplesrangedindepthfrom4%to78%throughwalldepth.Thistechnique hasagreaterthan80%probability ofdetection ata90%confidence level,andarootmeansquaresizingerroroflessthan5%through-wall. |
| | St.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page4IGA/SCCatSludePileReionsandEcrateTeSuorts-ForSt.LucieUnit1,adetailedtechnical basisfortheacceptability ofthetechnique forsizingIGA/SCCtypeindications wasprovidedtotheNRCinFPLlettersL-96-166, SteamGenerator TubeInspection, RequestforAdditional Information (RAI)Response, L-96-273, SteamGenerator RunTimeAnalysisforCycle14andL-97-141, DoseAssessment Correction, Cycle14SteamGenerator RunTimeAnalysis. |
| | Thiscorrespondence providesaruntimeanalysisforSt.LucieUnit1inaccordance withguidanceprovidedintheDraftRegulatory Guide,SteamGenerator TubeIntegrity, DraftRegulatory Guide1.121,BasesforPluggingDegradedPWRSteamGenerator TubesandGenericLetter95-05,Voltage-Based RepairCriteriafor)Westinghouse SteamGenerator TubesA@ectedbyOutsideDiameterStressCorrosion Cracking. |
| | Forsteamgenerator tubeinspections throughtheFall1995atSt.LucieUnit2,atechnical basisfortheacceptability ofthetechnique forsizingIGA/SCCtypeindications isprovidedinEPRINP-5397-LD, Laboratory Evaluation ofSteamGenerator Tubes120/12,79/9,and59/95FromSt.LucieUnit1,August,1987.TheEPRIreportconcludes thatthefieldeddy-current resultsshowedgoodcorrelation withthedefectdepthsandisconservative insizingthedefects.Inspection andsizingtechniques usedatSt.LucieUnit2werethesameasthoseusedatSt.LucieUnit1fordetection andsizingofIGA/SCCindications. |
| | Asdiscussed intheresponsetoitem(I)above,sizingofIGA/SCCindications wasabandoned aftertheFall1995inspection atSt.LucieUnit2,andaftertheSpring1996inspection atSt.LucieUnit1.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997.Therefore, mechanical wearistheonlytypeofserviceinduceddegradation whichremainsinservicebasedonsizingforthecurrentcycleofoperation attheSt.LuciePlant. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML20217F6171999-10-0808 October 1999
Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML20212M1601999-09-28028 September 1999
Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML20209F1541999-07-0606 July 1999
Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
ML20195F3871999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
IA-99-247, Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)1999-06-11011 June 1999
Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5)
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML20207C7531999-05-17017 May 1999
Discusses Issue Identified by FPL in Feb 1998 Involving Potential for Fire to Cause Breach of Rc Sys High/Low Pressure Interface Boundary & NRC Decision for Exercise of Enforcement Discretion
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML20205M0431999-04-13013 April 1999
Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
1999-09-28
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17241A5001999-10-21021 October 1999
Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C
ML17309A9981999-10-19019 October 1999
Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points
ML17241A4811999-10-0101 October 1999
Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a
ML17241A4701999-09-25025 September 1999
Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant
ML17241A4721999-09-24024 September 1999
Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999
ML17241A4681999-09-22022 September 1999
Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17241A4671999-09-20020 September 1999
Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams.
ML17241A4581999-09-13013 September 1999
Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program
ML17241A4531999-08-31031 August 1999
Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006
ML17241A4521999-08-31031 August 1999
Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval
ML17241A4501999-08-26026 August 1999
Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached
ML17241A4371999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d)
ML17241A4461999-08-11011 August 1999
Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure
L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999
Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)
ML17309A9911999-07-26026 July 1999
Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified
ML17241A4221999-07-22022 July 1999
Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates.
ML17241A4471999-07-22022 July 1999
Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure
ML17241A4151999-07-22022 July 1999
Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2
ML17241A4101999-07-16016 July 1999
Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17309A9881999-07-0707 July 1999
Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager
ML17241A4011999-06-30030 June 1999
Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604
ML17241A3971999-06-30030 June 1999
Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17241A3951999-06-29029 June 1999
Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML17241A3731999-06-17017 June 1999
Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16)
ML17241A3641999-06-14014 June 1999
Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139
L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999
Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)
ML17241A3601999-06-0707 June 1999
Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998
ML17241A3561999-06-0707 June 1999
Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209
ML20195F3941999-05-27027 May 1999
FOIA Request That Memo from J Calvo to Fl Lebdon Re TIA - St Lucie,Unit 1 Environ Qualification of Woodward Governor Controls Be Placed in PDR
ML17241A3461999-05-24024 May 1999
Forwards Revised Relief Request 22 to Clarify Several Areas of Relief.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17241A3371999-05-20020 May 1999
Forwards Util Suppl to GL 95-07 Response Re pressure-locking & Thermal Binding of safety-related power-operated Gate Valves,In Response to NRC Second RAI Dtd 990225
ML17241A3391999-05-20020 May 1999
Forwards Notification of Change to Small Break LOCA ECCS Evaluation Model Used for St Lucie Unit 1.Anomaly Was Discovered & Corrected That Resulted in Reducing Calculated PCT for Limiting SBLOCA by More than 50 F
ML17241A3301999-05-17017 May 1999
Forwards LER 99-004-00 Re as Found Cycle 10 Psv Setpoints Outside TS Limits,Which Occurred on 990415.Root Cause Determination Not Yet Complete.Suppl to Include Root Cause & Corrective Actions Will Be Submitted
ML17309A9821999-05-10010 May 1999
Forwards Rev 36 to St Lucie Emergency Plan, Per 10CFR50.54(q).Executive Summary & Summary of Changes Incorporated by Rev,Encl
ML17241A3221999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
IR 05000335/19980141999-04-29029 April 1999
Provides Confirmation of NRC Staff Conclusions Re Cited & non-cited Violations in Insp Rept 50-335/98-14 & 50-389/98-14.Utils Position Re Consideration of Multiple Spurious Actuations in Event of Fire,Reiterated
ML17229B1071999-04-28028 April 1999
Forwards 1998 Annual Environ Operating Rept for St Lucie Unit 2. Rept Includes Discussions of 5-inch Barrier Net Maint & Taprogge Condenser Tube Cleaning Sys Ball Loss,As Agreed at First Biennial Sea Turtle Meeting Held on 980120
ML17229B1051999-04-22022 April 1999
Requests That Listed Individuals Be Placed on Official Serve List for Nuclear Matl Safety & Safeguards Info Notices
ML17229B1061999-04-21021 April 1999
Notifies NRC of Change in Medical Status of Licensed Operator Pf Farnsworth (Docket 55-21285,license SOP-21094). NRC Form 3996, Medical Exam Certification, Encl.Encl Withheld Per 10CFR2.790(a)(6)
ML17309A9851999-04-15015 April 1999
Requests That NRC Review Denial of Appeal from Assessment of Fees Assessed in 981101 Invoice RS0062-99 & Assessment of Fees in Invoice RS0182-99 Which Was Also Denied in 990305 Ltr.Both Invoices Are for Fees Re Inspector GG Warnick
ML17229B0951999-04-0808 April 1999
Requests Approval of Encl Revised Relief Request 6,in Response to 990322 Telcon with NRC & 10CFR55.55a(a)(3). Request States That Visual VT-3 Exams Will Be Conducted IAW IWA-2213 & Repairs Will Be IAW Util ASME Section IX Program
ML17229B0821999-04-0707 April 1999
Requests Approval of Interim Relief Request 26 Re Repair Requirements for Class 2 ECCS Piping,Per 10CFR50.55a(a)(3) & 50.55a(g)(iii).Alternative Actions Apply Guidance of GLs 91-18 & 90-05 & ASME Code Case N-513.Evaluation,encl
ML17229B0851999-04-0505 April 1999
Requests Approval of Encl Relief Request 25 Which Proposes to Use Alternative Requirements of ASME Code Case N-613 in Lieu of Requirements of ASME Section XI Figures IWB-2500-7(a) & IWB-2500-7(b).Action Requested by Aug 1999
ML17309A9791999-03-31031 March 1999
Forwards Revised EPIPs Including Rev 2 to EPIP-00,rev 2 to EPIP-09,rev 2 to EPIP-10 & Rev 10 to HP-207.Summary of Revs Listed
ML17309A9761999-03-23023 March 1999
Forwards Revised Epips,Including Rev 4 to EPIP-03, Er Organization Notification/Staff Augmentation, Rev 3 to EPIP-05, Activation & Operation of OSC & Rev 14 to HP-200, HP Emergency Organization. Changes to Epips,Discussed
ML17229B0691999-03-19019 March 1999
Transmits TS Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity,Per Soluble Boron Credit
ML17229B0721999-03-16016 March 1999
Requests Approval of Enclosed Relief Requests 23 & 24 Re ISI Plan for Second ten-year Interval.Nrc Action Is Requested to Be Complete by Aug 1999 to Support Planning for Spring 2000 Unit 2 Refueling Outage
ML17355A2631999-03-12012 March 1999
Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit
ML17229B0481999-03-10010 March 1999
Informs That Util Delivered Matls Requested in Encl 1 of NRC Ltr by Hand on 990308,as Requested by NRC Ltr Dtd 990218
1999-09-25
[Table view] |
Text
/'CATEGORY1REGULATRYINFORMATION DISTRIBUTXO SYSTEM(RXDS)IACCESSION NBR:98FACXL:50-335 St50~389StAUTH.NAMEKUNDALKAR,R.S.
RECIP.NAME03190069DOC.DATE:
98/03/11'OTARIZED:
YESLuciePlant,Unit1,FloridaPowerELightCo.LuciePlant,Unit2,FloridaPower6LightCo.AUTHORAFFILIATION FloridaPower&.LightCo.RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET¹0500033505000389
SUBJECT:
Submits90-dayresponsetoGL97-05;"SteamGenerator TubeInspTechniques."
DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD2-3LAGLEAVES,W COPIESLTTRENCL1.111RECIPIENT IDCODE/NAME PD2-3PDCOPIESLTTRENCL11E0INTERNAL:
ACRS.NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3EXTERNAL:
NOAC111111111011ILECENRRDE/EMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR1111111111DNNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATIONi CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR14ENCL13 Jt1I FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34S57March11,1998L-98-7310CFR50.410CFR50.54(0U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555RE:St.LucieUnits1and2DocketNos.50-335and50-389GenericLetter97-05-ResonseTheFloridaPowerandLightCompany(FPL)responses toGenericLetter(GL)97-05,SteamGenerator TubeInspection Techniques, forSt.LucieUnits1and2isattached.
Thegenericletterrequested, within90days,thatlicensees providecurrentinformation regarding theuseofsizingtechniques attheirfacilities.
OnDecember17,1997,theNRCissuedGL97-05requesting licensees toverifycompliance withAppendixBto10CFR50andthetechnical specifications, andtomaintainareasonable levelofassurance thatstructural andleakageintegrity marginsforsteamgenerator tubesaresatisfied.
TheNRCconcluded thatitisappropriate forthelicensees toreviewthetypesofsteamgenerator tubeindications thatarebeingleftinservicebasedonsizing,theinspection methodbeingusedtoperformthesizingforeachtypeofindication, andthetechnical basisfortheacceptability ofeachinspection method..Theattachedinformation isprovidedpursuanttotherequirements ofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f).
Thislettercontainsnonewregulatory commitments.
Pleasecontactusifthereareanyquestions aboutthissubmittal.
Verytrulyyours,*;v<.iRajiv.Kundalkar VicePresident NuclearEngineering RSK/GRMAttachment cc:RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant9803i900b9 9803iiPDRADOCK05000335PPDRanFPLGroupcompanyll!ill!ffff!lflllfllllNffff flJfffffff rIf'
'MSt,LucieUnits1and2DocketNos.50-335and50-389L-98-73Page2STATEOFFLORIDACOUNTYOFST.LUCIERajivS.Kundalkar beingfirstdulysworn,deposesandsays:ThatheisVicePresident, Engineering, fortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
ajivS.Kundalkar STATEOFFLORIDACOUNTYQF~Sworntoandsubscribed beforemehiIIdyf~IYlC,19~8byR.S.Kundalkar, whoispersonally knowntome.NameofNotaryPubic-StateofFloridaLeslloJ.WhlbNell.a..*!MYCOMMISSION fCCQ6f83B(PIAESMay12,200f"~igni'"'ONOTOTHRUTROYFAlNNSURANCE, INC.(Print,typeorstampCommissioned NameofNotaryPublic) hIjIIINihil'.lt'h
~j!lI)("j,h)hl"f-')hII)hIL' ISt.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page1NRCRequest:Within90daysofthedateofthisgenericletter,addressees aretosubmitawrittenresponsethatincludesthefollowing information:
(1)whetheritistheirpracticetoleavesteamgenerator tubeswithindications inservicebasedonsizing,(2)iftheresponsetoitem(1)isaffirmative, thoselicensees shouldsubmitawrittenreportthatincludes, foreachtypeofindication, adescription oftheassociated nondestructive examination methodbeingusedandthetechnical basisfortheacceptability ofthetechnique used.NRCRequestPartI:Whetheritistheirpracticetoleavesteamgenerator tubeswithindications inservicebasedonsizingFPLResponsePart1:TheUnit1steamgenerators areBWIreplacement units,andtheUnit2steamgenerators areCombustion Engineering Series3410.Itiscurrently thepracticeforSt.LucieUnits1and2toleavesteamgenerator tubeswithmechanical wearindications atsupportstructures inservicebasedonsizing.Noothertypeofserviceinduceddegradation isinservicebasedonsizingforthecurrentcycleofoperation forSt.LucieUnits1and2.Specifically, steamgenerator tubeswithmechanical wearindications whichcanbesizedaslessthantheTechnical Specification valueof40%ofthenominaltubewallthickness areleftinservice.Steamgenerator tubeinspections forpreviousoperating cyclesincludedsizingofIGA/SCCindications inadditiontomechanical wearindications, asdiscussed above.SizingofIGA/SCCindications waslastconducted duringtheSpring1996inspection atSt.LucieUnit1.Inthe1996inspection, IGA/SCCindications whichwerelocatedinthesludgepileregion,orateggcratetypetubesupportstructures, remainedinservice ifsizedaslessthantheTechnical Specification limitof40%ofthenominaltube-wall thickness.
IGA/SCCindications atotherlocations inthesteam St.LucieUnits1and2'ocketNos.50-335and50-389L-98-73Attachment Page2generators (i.e.,tubeexpansion transitions, freespans,anddrilledholetubesupports) werepluggedondetection withoutregardtosizing.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997.Therefore, thereisnoserviceinduceddegradation knowntoexistinthecurrentcycleofoperation.
Thefirstinservice inspection ofthereplacement steamgenerators isscheduled fortheFall1999refueling outage(SL1-16),
andaplugondetection approachisplannedforIGA/SCCtypeindications.
AtSt.LucieUnit2,sizingofIGA/SCCindications waslastconducted duringtheFall1995inspection.
Inthe1995inspection, asmallnumberofpossibleIGA/SCCindications (i.e.,approximately 43)weresizedaslessthantheTechnical Specification limitof40%ofthenominaltubewallthickness andremainedinservice.SizingofIGA/SCCindications wasnotdoneduringtheSpring1997inspection, andaplugondetection approachwasused.Therefore, noIGA/SCCindications wereleftinservicebasedonsizingforthecurrentcycleofoperation atSt.LucieUnit2.NRCRequestPart2:Iftheresponsetoitem(I)isafhrmative, thoselicensees shouldsubmitavvrittenreportthatincludes, foreachtypeofindication, adescription oftheassociated nondestructive examination methodbeingusedandthetechnical basisfortheacceptability ofthetechnique used.FPLResponsePart2:B~kd-ThIpidylydpdiiiiqadighillyimplement theguidanceofNEI97-06,SteamGenerator ProgramGuidelines, nolaterthanthefirstrefueling outagestartingafterJanuary1,1999.Asspecified inNEI97-06,eachutilityistofollowtheinspection guidelines contained inthelatestrevisionoftheEPRIPWRSteamGenerator Examination Guidelines.
AppendixH,"Performance Demonstration forEddyCurrentExamination,"
ofEPRIPWRSteamGenerator Examination Guidelines, Revisions 3through5,provideguidanceonthequalification ofsteamgenerator tubingexamination techniques andequipment usedtodetectandsizeflaws.Revision4oftheEPRIguidelines isapplicable tothemostrecentinservice inspections atSt.LuciePlant.PerEPRIguidelines, damagemechanisms aredividedintothefollowing categories forqualification:
- thinning, pitting,wear,outsidediameterintergranular attack/stress-corrosion cracking(IGA/SCC),
primary-side SCC,andimpingement damage.
St.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page3Forqualification
- purposes, testsamplesareusedtoevaluatedetection andsizingcapabilities.
Whilepulledtubesamplesarepreferred, fabricated samplesmaybeused.Iffabricated testsamplesareused,thesamplesareverifiedtoproducesignalssimilartothoseobservedinthefieldintermsofsignalcharacteristics, signalamplitude, andsignal-to-noise ratio.Samplesareexaminedtodetermine theactualthroughwalldefectmeasurements aspartoftheAppendixHqualification process.Procedures developed inaccordance withAppendixHspecifytheessential variables foreachtechnique.
Essential variables areassociated withanindividual instrument, probe,cable,oron-siteequipment configuration.
Additionally, certaintechniques haveundergone testingandreviewtoquantifysizingperformance.
Thesizingdatasetincludesthedetection datasetforthetechnique usedwithadditional requirements fornumberandcomposition ofthegradingunits.SizinTechniues-Forthecurrentcycleofoperation forSt.LucieUnit2,sizingtechniques wereusedduringsteamgenerator inspections toleavetubeswithmechanical wearindications inservicebasedonsizing.Forpreviouscyclesofoperation, asdiscussed intheresponsetoitem(1)above,sizingtechniques werealsousedtoleaveIGA/SCCindications inservicebasedonsizing.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997,andforthecurrentcycleofoperation atSt.LucieUnit2,aplugondetection approachforIGA/SCCindications wasused.Therefore, mechanical wearistheonlytypeofserviceinduceddegradation whichremainsinservicebasedonsizingforthecurrentcycleofoperation.
Thebasisforapplication ofthesizingtechniques istheconductoftheexaminations undertheSt.LuciePlantQualityAssurance Programfollowing therequirements ofSectionsXIandVoftheASMECode,1989EditionandRegulatory Guide1.83.Additional supportforsizingdegradation-specific mechanisms isprovidedbythequalification datasetsinAppendixHtotheEPRIPWRSteamGenerator Examination Guidelines.
- Mechanical Wear-Formechanical wearatverticalanddiagonalstrapsandothersupportstructures, sizingisaccomplished usingthe400/100Khzdifferential mixorthe400/100Khzabsolutemixofthebobbinprobe.Acalibration curveforverticalmaximumamplitude isdetermined basedonapplicable standards whichreplicate thedamagemechanism typeandquantity.
Thecalibration curverepresents thefullrangeofexpecteddepths.Thesizingqualification isbasedon64sampledatapointswhichwereusedfortheAppendixHtechnique qualification providedintheEPRIguidelines.
Thesamplesrangedindepthfrom4%to78%throughwalldepth.Thistechnique hasagreaterthan80%probability ofdetection ata90%confidence level,andarootmeansquaresizingerroroflessthan5%through-wall.
St.LucieUnits1and2DocketNos.50-335and50-389L-98-73Attachment Page4IGA/SCCatSludePileReionsandEcrateTeSuorts-ForSt.LucieUnit1,adetailedtechnical basisfortheacceptability ofthetechnique forsizingIGA/SCCtypeindications wasprovidedtotheNRCinFPLlettersL-96-166, SteamGenerator TubeInspection, RequestforAdditional Information (RAI)Response, L-96-273, SteamGenerator RunTimeAnalysisforCycle14andL-97-141, DoseAssessment Correction, Cycle14SteamGenerator RunTimeAnalysis.
Thiscorrespondence providesaruntimeanalysisforSt.LucieUnit1inaccordance withguidanceprovidedintheDraftRegulatory Guide,SteamGenerator TubeIntegrity, DraftRegulatory Guide1.121,BasesforPluggingDegradedPWRSteamGenerator TubesandGenericLetter95-05,Voltage-Based RepairCriteriafor)Westinghouse SteamGenerator TubesA@ectedbyOutsideDiameterStressCorrosion Cracking.
Forsteamgenerator tubeinspections throughtheFall1995atSt.LucieUnit2,atechnical basisfortheacceptability ofthetechnique forsizingIGA/SCCtypeindications isprovidedinEPRINP-5397-LD, Laboratory Evaluation ofSteamGenerator Tubes120/12,79/9,and59/95FromSt.LucieUnit1,August,1987.TheEPRIreportconcludes thatthefieldeddy-current resultsshowedgoodcorrelation withthedefectdepthsandisconservative insizingthedefects.Inspection andsizingtechniques usedatSt.LucieUnit2werethesameasthoseusedatSt.LucieUnit1fordetection andsizingofIGA/SCCindications.
Asdiscussed intheresponsetoitem(I)above,sizingofIGA/SCCindications wasabandoned aftertheFall1995inspection atSt.LucieUnit2,andaftertheSpring1996inspection atSt.LucieUnit1.TheSt.LucieUnit1steamgenerators werereplacedinDecember1997.Therefore, mechanical wearistheonlytypeofserviceinduceddegradation whichremainsinservicebasedonsizingforthecurrentcycleofoperation attheSt.LuciePlant.
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