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| {{#Wiki_filter:REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(BIDS>DISTRIBUTIONFORINCOMINGMATERIAL50-387REC:GRIER8HNRCORG:CURTISNWPAPNR5LIGI-lTDOCDATE:09/15/78DATERCVD:09/22/78DOCTYPE:LETTERNOTARIZED:NOCOPIESRECEIVED | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM(BIDS>DISTRIBUTION FORINCOMINGMATERIAL50-387REC:GRIER8HNRCORG:CURTISNWPAPNR5LIGI-lTDOCDATE:09/15/78DATERCVD:09/22/78DOCTYPE:LETTERNOTARIZED: |
| | NOCOPIESRECEIVED |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LTR1ENCLFURNISHINGSUPPLEMENTTOAPPLICANT"SLTRSOF04/17/73AND07/14/78CONTAININGFINALCONSTRUCTIONDEFICIENCYREPTCONCERNINGDEFICIENCYINEISMICQUALIFICATIONOFMEDIUMVOLTAGEM.TALCLADSAFEGUARDSWITCHGEAR.PLANTNAME:SUSQUEHANNA"<<UNIT1uv%%%%%%%%%%%%%%%DISTRIBUTIONOFTHISMATERIALNOTES:SENDIS(E3CYSFSAR8(ALLAMDTGCONSTRUCTIONDEFICIENCYREPORT<10CFR50.55E)(DISTRIBUTIONCODE8019>REVIEWERINITIAL:XJMDISTRIBUT0BINITIAL~IGASFOLLOWS%%<%%%%%%%%%%%%%%%FORACTION:INTERNAL:EXTERNAL:ASSTDIRVASSALL0%%W/ENCLPRMINER%%W/ENCL.6FILE%%/ENCL0ENCL,GOScSICKRcSTAFF%%W/ENCLDIRECTORDPM%%W/ENCLQAB%%W/ENCLADFORENG%kW/ENCLADFORPLANTSYSTEMS%%W/ENCLSTANDARDSDEV.%%W/ENCLFERDDREHER/IE%%W/ENCLLPDRSNILKESBARREiPA%%M/ENCLTERA<<%W/ENCLNSIC%%W/ENCLACRSCATB%%W/16ENCLBRCI.IIEFLWR03BC%%W/ENCLLICASSTLWR83LA<<W/ENCLNRCPDR%%W/ENCLOELDu~W/ENCLMIPC%%W/ENCLDEPUTYDIRDPM%%W/ENCLDIRECTORDSS%%W/ENCLADFORREACSFTY%%W/ENCLADFORSYS8(PROJ%%W/ENCLKSEYFRIT/IE%%W/ENCLCONTROLNBR:780860147At~THEEND
| | LTR1ENCLFURNISHING SUPPLEMENT TOAPPLICANT"S LTRSOF04/17/73AND07/14/78CONTAINING FINALCONSTRUCTION DEFICIENCY REPTCONCERNING DEFICIENCY INEISMICQUALIFICATION OFMEDIUMVOLTAGEM.TALCLADSAFEGUARDS WITCHGEAR. |
| | PLANTNAME:SUSQUEHANNA |
| | "<<UNIT1uv%%%%%%%%%%%%%%% |
| | DISTRIBUTION OFTHISMATERIALNOTES:SENDIS(E3CYSFSAR8(ALLAMDTGCONSTRUCTION DEFICIENCY REPORT<10CFR50. |
| | 55E)(DISTRIBUTION CODE8019>REVIEWERINITIAL:XJMDISTRIBUT0B INITIAL~IGASFOLLOWS%%<%%%%%%%%%%%%%%% |
| | FORACTION:INTERNAL: |
| | EXTERNAL: |
| | ASSTDIRVASSALL0%%W/ENCL PRMINER%%W/ENCL |
| | .6FILE%%/ENCL0ENCL,GOScSICKRcSTAFF%%W/ENCL DIRECTORDPM%%W/ENCL QAB%%W/ENCL ADFORENG%kW/ENCL ADFORPLANTSYSTEMS%%W/ENCL STANDARDS DEV.%%W/ENCLFERDDREHER/IE%%W/ENCL LPDRSNILKESBARREiPA%%M/ENCL TERA<<%W/ENCL NSIC%%W/ENCL ACRSCATB%%W/16ENCLBRCI.IIEFLWR03BC%%W/ENCL LICASSTLWR83LA<<W/ENCL NRCPDR%%W/ENCL OELDu~W/ENCL MIPC%%W/ENCL DEPUTYDIRDPM%%W/ENCL DIRECTORDSS%%W/ENCL ADFORREACSFTY%%W/ENCL ADFORSYS8(PROJ%%W/ENCL KSEYFRIT/IE%%W/ENCL CONTROLNBR:780860147 At~THEEND |
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| ~g~"~~;-),$)I)~~.(gPg~XKDsesTWONORTHNINTHSTREET,ALLENTOWN,PA.18101/g$ITJNE:(215)821-5151NORMANW,CURTISVicePresidentEngineering8Construction821-5381SeptEmber15,1978Mr.BoyceH.GrierDirector,RegionIU.S.NuclearRegulatoryCczanission631ParkAvenueKingofPrussia,Pennsylvania17406CJo>Irrc's'nv>+mCnrnCllPl<onaP1~CDC)SUSQUEEQKASTEAMELECTRICSTATIONF3'EPORTOFADEFICIENT',CYINSEISMICQUAIZFICATIONOFI%DENVOLTAGE,M'TALCLAD,SM."%GUARDSSWITCHGFARDOCKETNO.:50-387LICENSENO:CPPR-101ER100450FILE840-4PLA289'~=I~4\I | | ~g~"~~;-),$)I)~~.(gPg~XKDsesTWONORTHNINTHSTREET,ALLENTOWN, PA.18101/g$ITJNE:(215)821-5151NORMANW,CURTISVicePresident Engineering 8Construction 821-5381SeptEmber 15,1978Mr.BoyceH.GrierDirector, RegionIU.S.NuclearRegulatory Cczanission 631ParkAvenueKingofPrussia,Pennsylvania 17406CJo>Irrc's'nv>+mCnrnCllPl<onaP1~CDC)SUSQUEEQKA STEAMELECTRICSTATIONF3'EPORTOFADEFICIENT',CY INSEISMICQUAIZFICATION OFI%DENVOLTAGE,M'TALCLAD,SM."%GUARDS SWITCHGFAR DOCKETNO.:50-387LICENSENO:CPPR-101ER100450FILE840-4PLA289'~=I~4\I |
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| ==DearMr.Grier:== | | ==DearMr.Grier:== |
| ThissupplementsPPSZlettersPLA-246,datedApril17,1978andPLA-271,datedJuly14,1978,andprovidesafinalreportofthesubjectdeficiencyasrecpuzedby10CFR50.55(e).Pleaseadviseshouldyourecureadditionalinformation.Verytrulyyours,N.W.CurtisVicePresident-Engineering6ConstructionAttachmentARS:mcbcc:Mr.J.G.Davis(15)ActingDirector-OfficeofInspection6EnforcementU.S.NuclearReyQatoryCcmiission--Washington,D.C.20555Mr.G.MDonald,Director(1)OfficeofManaganent,,Information6~amContxol'U.S.NuclearRegulatoryCcmtissionWashington,D.C.20555PENNSYLVANIAPOWER8,LIGHTCOMPANYt78p86p1479'e~t
| | Thissupplements PPSZlettersPLA-246,datedApril17,1978andPLA-271,datedJuly14,1978,andprovidesafinalreportofthesubjectdeficiency asrecpuzedby10CFR50.55 (e).Pleaseadviseshouldyourecureadditional information. |
| 'Mr.B.H.GrierSept.anber15,1978cc:Mr.RobertM.GalloU.S.NuclearRegulatoryGmxnissionP.O.Box52Shickshinny,Pennsylvania18655 OFADEFICIENCYINSEISMICQUALIFICATIONOFMEDIUMVOLTAGE,MEALCLAD,SAFEGUABDSSWHCHG1RRFORTHESUSQUEHANNASTEAM1KZCTRICSTATICND.P.ParsonsSSESElectricalGroupSupvr.ApprovedBy:..~~~9r~pg.A.M.eSupervisingEngineer-Design-SuscpehannaReviewed:A.R.ScilManager-NuclearQualityAssurancePENNSYLVANIAHMK6LIGHTCCMPANYAL'EZKTQWN,PENNSYLVANIAS1M.'EMBER15,1978 TABLEOFCONTENTSIntroductionDescriptionofDeficiencyAnalysisofSafetyImplicationsCorrectiveActionConclusionPg.lPgs,lg2g3Pg.3Pgs.4,5Pg.5 INTRODUCZIONThisreportispreparedinaccordancewiththerequirementsdescribedinTitle10,CodeofFederalRegulations,Part50,Section50.55(e).PPKwasadvised,throughitsA/E(Bechtel)organization,t1wtWestinghousesupplied,mediumvoltage,metalcladswitchgearwasnotcapableofwithstandingthepostulatedseismiceventforSusquehannaPlant.BechtelwasrequestedtoreviewthesituationandadvisePPsZofitsfindings.OnParch31,1978theNRCwasinformedthatadeficiency,potentiallyreportableunder10CFR50.55(e),wasbeingevaluated,andonApril17,1978,followinganengineeringreview,PALissueditsInterimReportofthedeficiency.Thedeficiencywasdeterminedtobereportableunder10CFR50.55(e)forthefollowingreasons:1.Thedeficiency,wereittoremainuncorrected,couldhaveresultedinasafetyhazardtotheoperationoftheplant.2.Thedeficiencyrepresentedadeficiencyinfinaldesignasapprovedandreleasedforfabricationandinstallation.3.Eightsafety-relatedswitchgearunitshad,beenshippedandacceptedforinstallationbeforethedeficiencywasdiscovered.DJHCRIPTIONOFDEFICIENCYTheSusquehannaPlantwassuppliedeightdeficientsafetyrelatedmediumvoltageswitchgearunitsbyWestinghouse.Fouroftheseswitchgearunitssupplypowerdirectlyto4kvsafetyrelatedequipnent,pumprmtorsandloadcenters,>RichareusedtomitigatetheeffectsofanaccidentinUnitl. | | Verytrulyyours,N.W.CurtisVicePresident-Engineering 6Construction Attachment ARS:mcbcc:Mr.J.G.Davis(15)ActingDirector-Office ofInspection 6Enforcement U.S.NuclearReyQatory Ccmiission-- |
| Likewise,fourswitchgearunitsareusedasthesupplyfor4kvsafetyrelatedloadsonUnit2.Eachswitchgearunit,containsthreepotentialtransformercircuits,oneofthecircuitsconsistsof~potentialtransformersconnectedinanopendelta.Theothertwocircuitseachcontainonepotentialtransformerusedtosensesinglephasepotential.Thepotentialtransformersareusedtoobtain120volt,potentialirr3icationforusewithrelaysontheswitchgearunits'heIIediumVoltageYwtalCladSwitchgear(Safeguards)Specification(8856-E-109)requirestheequipmenttomeetseismicrecpdxementsofProjectSpecification8856-6-10,IEEEStandardM.344,andtoreaeinfunctional,koth,duringandafteranOBEorDBE.WestinghouseadvisedBechtelonJanuary24,1978thatthepotentialtransformersecondarydisconnectingcontactassanbliesonequignentsimilartothatsuppliedforSusquehannahadfailedtowithstandrecentseismictests.Westinghousefurtherstatedthat,underseismicconditions,itispossiblethattheslip-fitsecondarycontactscouldbedislodgedfrantheirnormalpositionsresultinginopenor.shortcircuitingofthesecondarycircuits.WestinghouserequestedthatBechtelevaluatetheconditiontodetaanineifitauldconstituteasafetyhazard..Westinghouseconfirmedthattherewerenofailuresofpotentialtransformercircuitsduringtheoriginalseismicqualificationtests.However,thesecircuitsweresubsequent1yredesignedandthenewdesignwasanalyticallyqualified.Situalseismictestsonswitchgearunitsincorporatingthenewdesignresultedinthepotentialtransformercircuitfailures>M.charethesubjectofthisreport. | | Washington, D.C.20555Mr.G.MDonald,Director(1)OfficeofManaganent,,Information 6~amContxol'U.S.NuclearRegulatory Ccmtission Washington, D.C.20555PENNSYLVANIA POWER8,LIGHTCOMPANYt78p86p147 9'e~t |
| Westinghousealsoconfirmedthattheseianicqualificationofallothercanponentsintheseassembliesremainvalid.MALYSISOFSMOKYIMPLICATIONSTheengineeringevaluationdeterminedthattheopenorshortcircuitingofanyoftheseco~contactscouldresult.inincorrectoperationofaswitchgearunit.Itwasconcludedthattheworstconditionresultsfranthelossofallthreepotentialtransformercircuitsoneachswitchgearbus.Underthiscondition,thetminccmingbusfeedersfrcmthesafeguardtransformers(onefromeachoffsitesource)wouldbeautomaticallydisconnectedfrcmeachswitchgearbusandthedieselgeneratorpowersourceconnectedrestoringpowertothebus.ALOCAoccuringduringorafterthepostulated,seismiceventwouldinitiateaclosingsignaltothemotorfeederbreakersoftheshutdownloads,i.e.RHRandCoreSprayHotors.ThesefeederbreakerswouldcloseandismMiatelytripduetothefalseundervoltageindicationassensedbytheundervoltagerelay.Thecircuitbreakerswouldbeunabletocloseagainbecauseofthepermanentundervoltagetripsignalimposedonthem.Theaboveanalysisassumes'hat,thefailuresconcurrentlyoccuronallredundantm~tchgearhuses.BasedupontheevaluationofBechtelEngineering~itisconcludedthatthisconditionofnotbeingabletosupplypowertotheshutdownloadsunderaDXKconditionconstitutesasafetyhazardtotheoperationoftheplantandrepresentsadeficiencyinfinaldesign.
| | 'Mr.B.H.GrierSept.anber 15,1978cc:Mr.RobertM.GalloU.S.NuclearRegulatory Gmxnission P.O.Box52Shickshinny, Pennsylvania 18655 OFADEFICIENCY INSEISMICQUALIFICATION OFMEDIUMVOLTAGE,MEALCLAD,SAFEGUABDS SWHCHG1RR FORTHESUSQUEHANNA STEAM1KZCTRICSTATICND.P.ParsonsSSESElectrical GroupSupvr.ApprovedBy:..~~~9r~pg.A.M.eSupervising Engineer-Design-Suscpehanna Reviewed: |
| | A.R.ScilManager-Nuclear QualityAssurance PENNSYLVANIA HMK6LIGHTCCMPANYAL'EZKTQWN, PENNSYLVANIA S1M.'EMBER 15,1978 TABLEOFCONTENTSIntroduction Description ofDeficiency AnalysisofSafetyImplications Corrective ActionConclusion Pg.lPgs,lg2g3Pg.3Pgs.4,5Pg.5 INTRODUCZION Thisreportispreparedinaccordance withtherequirements described inTitle10,CodeofFederalRegulations, Part50,Section50.55(e).PPKwasadvised,throughitsA/E(Bechtel) organization, t1wtWestinghouse |
| | : supplied, mediumvoltage,metalcladswitchgear wasnotcapableofwithstanding thepostulated seismiceventforSusquehanna Plant.Bechtelwasrequested toreviewthesituation andadvisePPsZofitsfindings. |
| | OnParch31,1978theNRCwasinformedthatadeficiency, potentially reportable under10CFR50.55(e), |
| | wasbeingevaluated, andonApril17,1978,following anengineering review,PALissueditsInterimReportofthedeficiency. |
| | Thedeficiency wasdetermined tobereportable under10CFR50.55(e) forthefollowing reasons:1.Thedeficiency, wereittoremainuncorrected, couldhaveresultedinasafetyhazardtotheoperation oftheplant.2.Thedeficiency represented adeficiency infinaldesignasapprovedandreleasedforfabrication andinstallation. |
| | 3.Eightsafety-related switchgear unitshad,beenshippedandacceptedforinstallation beforethedeficiency wasdiscovered. |
| | DJHCRIPTION OFDEFICIENCY TheSusquehanna Plantwassuppliedeightdeficient safetyrelatedmediumvoltageswitchgear unitsbyWestinghouse. |
| | Fouroftheseswitchgear unitssupplypowerdirectlyto4kvsafetyrelatedequipnent, pumprmtorsandloadcenters,>RichareusedtomitigatetheeffectsofanaccidentinUnitl. |
| | : Likewise, fourswitchgear unitsareusedasthesupplyfor4kvsafetyrelatedloadsonUnit2.Eachswitchgear unit,containsthreepotential transformer |
| | : circuits, oneofthecircuitsconsistsof~potential transformers connected inanopendelta.Theothertwocircuitseachcontainonepotential transformer usedtosensesinglephasepotential. |
| | Thepotential transformers areusedtoobtain120volt,potential irr3ication forusewithrelaysontheswitchgear units'heIIediumVoltageYwtalCladSwitchgear (Safeguards) |
| | Specification(8856-E-109) requirestheequipment tomeetseismicrecpdxements ofProjectSpecification 8856-6-10, IEEEStandardM.344,andtoreaeinfunctional, koth,duringandafteranOBEorDBE.Westinghouse advisedBechtelonJanuary24,1978thatthepotential transformer secondary disconnecting contactassanblies onequignent similartothatsuppliedforSusquehanna hadfailedtowithstand recentseismictests.Westinghouse furtherstatedthat,underseismicconditions, itispossiblethattheslip-fitsecondary contactscouldbedislodged frantheirnormalpositions resulting inopenor.shortcircuiting ofthesecondary circuits. |
| | Westinghouse requested thatBechtelevaluatethecondition todetaanine ifitauldconstitute asafetyhazard..Westinghouse confirmed thattherewerenofailuresofpotential transformer circuitsduringtheoriginalseismicqualification tests.However,thesecircuitsweresubsequent1y redesigned andthenewdesignwasanalytically qualified. |
| | Situalseismictestsonswitchgear unitsincorporating thenewdesignresultedinthepotential transformer circuitfailures>M.charethesubjectofthisreport. |
| | Westinghouse alsoconfirmed thattheseianicqualification ofallothercanponents intheseassemblies remainvalid.MALYSISOFSMOKYIMPLICATIONS Theengineering evaluation determined thattheopenorshortcircuiting ofanyoftheseco~contactscouldresult.inincorrect operation ofaswitchgear unit.Itwasconcluded thattheworstcondition resultsfranthelossofallthreepotential transformer circuitsoneachswitchgear bus.Underthiscondition, thetminccmingbusfeedersfrcmthesafeguard transformers (onefromeachoffsitesource)wouldbeautomatically disconnected frcmeachswitchgear busandthedieselgenerator powersourceconnected restoring powertothebus.ALOCAoccuringduringorafterthepostulated, seismiceventwouldinitiateaclosingsignaltothemotorfeederbreakersoftheshutdownloads,i.e.RHRandCoreSprayHotors.ThesefeederbreakerswouldcloseandismMiately tripduetothefalseundervoltage indication assensedbytheundervoltage relay.Thecircuitbreakerswouldbeunabletocloseagainbecauseofthepermanent undervoltage tripsignalimposedonthem.Theaboveanalysisassumes'hat, thefailuresconcurrently occuronallredundant m~tchgear huses.Basedupontheevaluation ofBechtelEngineering~it isconcluded thatthiscondition ofnotbeingabletosupplypowertotheshutdownloadsunderaDXKcondition constitutes asafetyhazardtotheoperation oftheplantandrepresents adeficiency infinaldesign. |
| ,IP,t,,~ | | ,IP,t,,~ |
| CORRECTIVE'ACTIONActionTakentoContxol'Deficient.'ItemsTheactionstakenbyBechtelpriortothesuhnittaloftheinterimreportofthedeficiencybyPP&LaredomunentedinPZA-246datedApril17,1978.Inadditiontothemeasurespreviouslyidentified,andintheinterestofobtainingdocumentedevidenceofBechtelPxojectEngineering'sevaluationofthecondition'scause,correctiveactionrequired,andreportabilityunder10CFR50.55(e),BechtelQAgeneratedIhnagerrentCorrectiveActionRequestNo.1-22datedMarch28,1978.CorrectiveActionto'Control'Resolution'of'theDeficienciesWestinghousehassuppliedmodificationkitswhichprovideforeliminatingthestationaxy,secondarydisconnectingcontactassembliesfromthepotentialtransformercircuits.Twenty-four(24)(threekitsforeachoftheeightsafety-relatedswitchgearunits)potentialtransfoxmersecondaryfieMrmdificationkits(WestinghouseStyleNo.628F14G01)havebeenprovided.TheserrodificationkitshavebeeninstalledbyBechtelfieldelectricianspertheinstructionsonWestinghousedrawing628F146.ThesechangesweremadeunderthesupervisionoftheWestinghouseEngineeringServicePersonnel.Themodificationconsistsofhardwiringthesecondaryarablecontacttoatexminalblockviaawiringharness.ThePTsecondarycircuitsarethenconnectedtothefieldsideoftheterminalblock.Thesecondarystationarycontactsareremovedentirely,thuseliminatingthesourceoftheseismicfailure. | | CORRECTIVE |
| ~~I(~Westinghousehasseianicallyqualifiedthepotentialtransformerswiththe@edifiedsecondarycontactarrangement.DonznentedevidenceofthisqualificationhasbeenprovidedtoBechtelthrougharevisiontotheoriginalqualificationreport.COVZIJSXONSl4xlificationshavebeenmadetoaU.theWestinghousesafety-related,medianvoltageswitchgearunitscontainingpotentialtransformersandpurchasedunderP.O.8856-E-109ACforSusquehannaSteamElectricStation.TheBechtelgeneratedhMnconfoxmanceReport(NCRhM.2514)willnotbeclosedoutuntilBechtelQualityContxolhasperformedtheattendantinspectionsandhasverifiedthatthemxlificationkitsrareinstalledaccordingtodesignrequirements-Theandifiedswitchgearunitsarequalifiedtomeetthepostulatedseismicevent.forSusquehannaanddocumentationofthisseismicqualificationhasbeenreceivedandwillbereviewedbyBechtelEngineering.Bechtel'sacceptanceofthisdocumentationwillresultinanacceptablydocumentedrevisiontotheWestinghouseSeianicQualificationReport.Theswitchgearunits~aspresentlymodified,arecompatiblewithpurchaseorder,PSARandFSARrequiranents.}} | | 'ACTIONActionTakentoContxol'Deficient.'Items TheactionstakenbyBechtelpriortothesuhnittal oftheinterimreportofthedeficiency byPP&Laredomunented inPZA-246datedApril17,1978.Inadditiontothemeasurespreviously identified, andintheinterestofobtaining documented evidenceofBechtelPxojectEngineering's evaluation ofthecondition's cause,corrective actionrequired, andreportability under10CFR50.55(e), |
| | BechtelQAgenerated Ihnagerrent Corrective ActionRequestNo.1-22datedMarch28,1978.Corrective Actionto'Control'Resolution |
| | 'of'theDeficiencies Westinghouse hassuppliedmodification kitswhichprovideforeliminating thestationaxy, secondary disconnecting contactassemblies fromthepotential transformer circuits. |
| | Twenty-four (24)(threekitsforeachoftheeightsafety-related switchgear units)potential transfoxmer secondary fieMrmdification kits(Westinghouse StyleNo.628F14G01) havebeenprovided. |
| | Theserrodification kitshavebeeninstalled byBechtelfieldelectricians pertheinstructions onWestinghouse drawing628F146.Thesechangesweremadeunderthesupervision oftheWestinghouse Engineering ServicePersonnel. |
| | Themodification consistsofhardwiringthesecondary arablecontacttoatexminalblockviaawiringharness.ThePTsecondary circuitsarethenconnected tothefieldsideoftheterminalblock.Thesecondary stationary contactsareremovedentirely, thuseliminating thesourceoftheseismicfailure. |
| | ~~I(~Westinghouse hasseianically qualified thepotential transformers withthe@edifiedsecondary contactarrangement. |
| | Donznented evidenceofthisqualification hasbeenprovidedtoBechtelthrougharevisiontotheoriginalqualification report.COVZIJSXONS l4xlifications havebeenmadetoaU.theWestinghouse safety-related, medianvoltageswitchgear unitscontaining potential transformers andpurchased underP.O.8856-E-109AC forSusquehanna SteamElectricStation.TheBechtelgenerated hMnconfoxmance Report(NCRhM.2514)willnotbeclosedoutuntilBechtelQualityContxolhasperformed theattendant inspections andhasverifiedthatthemxlification kitsrareinstalled according todesignrequirements-Theandifiedswitchgear unitsarequalified tomeetthepostulated seismicevent.forSusquehanna anddocumentation ofthisseismicqualification hasbeenreceivedandwillbereviewedbyBechtelEngineering. |
| | Bechtel's acceptance ofthisdocumentation willresultinanacceptably documented revisiontotheWestinghouse SeianicQualification Report.Theswitchgear units~aspresently |
| | : modified, arecompatible withpurchaseorder,PSARandFSARrequiranents.}} |
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Category:Letter
MONTHYEARPLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 2024-09-06
[Table view] Category:Report
MONTHYEARPLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7959, Owner'S Activity Report PLA-79592021-07-15015 July 2021 Owner'S Activity Report PLA-7959 PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 12018-11-27027 November 2018 Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents PLA-7559, Flooding Mitigating Strategies Assessment (MSA) Report2016-12-19019 December 2016 Flooding Mitigating Strategies Assessment (MSA) Report ML16231A5092016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents)(Cac Nos. MF4364 and MF4365) PLA-7491, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident2016-06-30030 June 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application ML15356A2472016-01-20020 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulation Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-08-20020 August 2015 Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 PLA-7311, Negative Blind Specimen Report, PLA-73112015-04-0909 April 2015 Negative Blind Specimen Report, PLA-7311 ML15090A3002015-04-0101 April 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC Nos. MF4364 & MF4365) PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 PLA-7175, (SSES)- 10 CFR 50.46 - Annual Report2014-06-20020 June 2014 (SSES)- 10 CFR 50.46 - Annual Report ML14156A2342014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0288 and MF0289) ML14056A4492014-05-0606 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tacs MF0183, MF0184) ML14113A5552014-04-23023 April 2014 Draft Staff Assessment of Seismic Walkdown Report Near-term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident; PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit 1. Docket No. 50-387 ML14085A3982014-03-26026 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident PLA-7145 ML14085A4262014-03-26026 March 2014 Apendix B IPEEE Adequacy Review ML14010A3712014-01-15015 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Susquehanna Steam Electric Station, Units 1 and 2, TAC Nos.: MF0888 and MF0889 PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-69382012-11-21021 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 PLA-6809, Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady.2012-09-18018 September 2012 Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady. ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML12068A1952012-02-23023 February 2012 Technical Requirements Manual Unit 2 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML13046A1372011-11-30030 November 2011 Enclosure 8 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1102504712011-01-14014 January 2011 Technical Requirements Manual PLA-6657, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments2010-10-0707 October 2010 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments ML1020401442010-05-12012 May 2010 Replacement Steam Dryer Report, Unit 1, Start-Up, 107% Power Test Plateau 05/11/10 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1004801852009-12-31031 December 2009 BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report PLA-6568, Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-65682009-10-0505 October 2009 Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-6568 PLA-6523, Fourteen Refueling Outage Owner'S Activity Report PLA-65232009-07-31031 July 2009 Fourteen Refueling Outage Owner'S Activity Report PLA-6523 ML0921703332009-07-31031 July 2009 Enclosure 2 to PLA-6542 - SSES Replacement Steam Dryer and Flow Induced Vibration Report Unit 2 Start-Up 107.0% Power Test Plateau. (Non-Proprietary) ML0918004602009-06-23023 June 2009 Submittal of Work Environment Improvement Plan, PLA-6528 PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 February 2009 Enclosure 5 to PLA-6484, Susquehanna Replacement Steam Dryer Updated Stress Analysis at Extended Power Uprate Conditions, Non-Proprietary Version Engineering Report 0000-0095-2113-NP-R0 ML0907704482009-02-27027 February 2009 Enclosures 6, 7, 8 and 9 to PLA-6484, Revised Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation, Non-Proprietary Version Engineering Report 0000-0096-5766-NP-R1 PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version2008-10-30030 October 2008 Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version 2024-07-23
[Table view] Category:Technical
MONTHYEARPLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 12018-11-27027 November 2018 Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents PLA-7491, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident2016-06-30030 June 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14010A3712014-01-15015 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Susquehanna Steam Electric Station, Units 1 and 2, TAC Nos.: MF0888 and MF0889 PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-69382012-11-21021 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML1102504712011-01-14014 January 2011 Technical Requirements Manual ML1004801852009-12-31031 December 2009 BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report ML0921703332009-07-31031 July 2009 Enclosure 2 to PLA-6542 - SSES Replacement Steam Dryer and Flow Induced Vibration Report Unit 2 Start-Up 107.0% Power Test Plateau. (Non-Proprietary) PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 February 2009 Enclosure 5 to PLA-6484, Susquehanna Replacement Steam Dryer Updated Stress Analysis at Extended Power Uprate Conditions, Non-Proprietary Version Engineering Report 0000-0095-2113-NP-R0 ML0907704482009-02-27027 February 2009 Enclosures 6, 7, 8 and 9 to PLA-6484, Revised Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation, Non-Proprietary Version Engineering Report 0000-0096-5766-NP-R1 PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version2008-10-30030 October 2008 Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0828300742008-07-31031 July 2008 GE-NE 0000-0085-2413 NP-R0, Susquehanna Unit 1, Replacement Steam Dryer Vibration Instrumentation Program NRC Summary Test Report ML0810105462008-04-0101 April 2008 Attachment 2 to PLA-6346, Non-Proprietary Version of Unit 1 Main Steam Line Limit Curves ML0806602552008-02-22022 February 2008 GE-NE-000-0080-2994-NP-R2, Revision 2, Susquehanna Replacement Steam Dryer Instrumentation Acceptance Criteria - Dryer Mounted Instrumentation. ML0803800892008-01-31031 January 2008 Engineering Report, GE-NE-0000-0079-2250-NP-R0, Susquehanna Replacement Steam Dryer Stress Analysis at Extended Power Uprate Conditions ML0728501222007-10-10010 October 2007 BWRVIP-145NP, BWR Vessel and Internals Project, Evaluation of Susquehanna Unit 2 Top Guide and Core Shroud Material Samples Using RAMA Fluence Methodology ML0720103642007-06-30030 June 2007 GE-Hitachi Nuclear Energy Americas LLC Report GE-NE-0000-0061-0595-NP-R1, Susquehanna Replacement Steam Dryer Fatigue Analysis. ML0700403832006-12-31031 December 2006 GE-NE-OOOO-0061-0595-NP-RO, Engineering Report: Susquehanna Replacement Steam Dryer Fatigue Analysis. PLA-6136, Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-61362006-11-29029 November 2006 Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-6136 PLA-5995, Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI)2005-12-15015 December 2005 Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI) PLA-5983, Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information2005-12-0101 December 2005 Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information PLA-6130, Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA).2005-10-31031 October 2005 Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA). ML0601203532005-10-13013 October 2005 Proposed Amendment No. 281 and Proposed Amendment No. 251: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67 ML0507504332005-03-11011 March 2005 PROJ0704 - BWRVIP-1 17NP: BWR Vessel and Internals Project, RAMA Fluence Methodology Plant Application - Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5 ML0710400422003-08-0101 August 2003 Environmental Studies in the Vicinity of the Susquehanna Steam Electric Station 2002 Water Quality and Fishes. PLA-5616, Annual Personnel Exposure Report PLA-56162003-04-28028 April 2003 Annual Personnel Exposure Report PLA-5616 ML18024A0561978-09-15015 September 1978 Letter Supplementing PP&L Letters Dated April 17, 1978 and July 14, 1978 and Attaching a Final Report of a Deficiency in Seismic Qualification of Medium Voltage, Metal Clad, Safeguards Switchgear ML18026A2181978-04-14014 April 1978 SSES Design Assessment Report, Revision 1 ML18025A6661978-02-28028 February 1978 Structural Integrity Test Report Containment Structure Unit 1 ML18025A6671977-12-30030 December 1977 Final Report on Shear Studs ML18025A1901977-06-22022 June 1977 Letter Enclosing an Interim Report of Reportable Deficiency Regarding Unsatisfied Field Welding and Inspection of Shear Studs ML18026A1191977-03-22022 March 1977 Results of Non-Nuclear Hot Test with the Relief System in the Philippsburg Nuclear Power Plant ML18025A0911976-05-31031 May 1976 Ecological Studies of the North Branch Susquehanna River in the Vicinity of the Susquehanna Steam Electric Station - Progress Report for the Period January-December 1974 ML18023A8811975-08-29029 August 1975 Letter Transmitting Report on Deficiency in Box Column Supports for the Susquehanna Nuclear Plant. ML18025A2011975-08-29029 August 1975 Definitive Report of Deficiencies in Fabricated Structural Steel Members (Box Column Supports) ML18023A8841975-07-25025 July 1975 Letter Regarding an Interim Report of Reportable Deficiency ML18023A8871975-04-0404 April 1975 Letter Attaching an Interim Report on a Potential Deficiency Which Was Discussed on March 6, 1975 ML18026A1181972-12-31031 December 1972 Formation and Oscillations of a Spherical Gas Bubble Under Water 2022-03-29
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM(BIDS>DISTRIBUTION FORINCOMINGMATERIAL50-387REC:GRIER8HNRCORG:CURTISNWPAPNR5LIGI-lTDOCDATE:09/15/78DATERCVD:09/22/78DOCTYPE:LETTERNOTARIZED:
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SUBJECT:
LTR1ENCLFURNISHING SUPPLEMENT TOAPPLICANT"S LTRSOF04/17/73AND07/14/78CONTAINING FINALCONSTRUCTION DEFICIENCY REPTCONCERNING DEFICIENCY INEISMICQUALIFICATION OFMEDIUMVOLTAGEM.TALCLADSAFEGUARDS WITCHGEAR.
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.6FILE%%/ENCL0ENCL,GOScSICKRcSTAFF%%W/ENCL DIRECTORDPM%%W/ENCL QAB%%W/ENCL ADFORENG%kW/ENCL ADFORPLANTSYSTEMS%%W/ENCL STANDARDS DEV.%%W/ENCLFERDDREHER/IE%%W/ENCL LPDRSNILKESBARREiPA%%M/ENCL TERA<<%W/ENCL NSIC%%W/ENCL ACRSCATB%%W/16ENCLBRCI.IIEFLWR03BC%%W/ENCL LICASSTLWR83LA<<W/ENCL NRCPDR%%W/ENCL OELDu~W/ENCL MIPC%%W/ENCL DEPUTYDIRDPM%%W/ENCL DIRECTORDSS%%W/ENCL ADFORREACSFTY%%W/ENCL ADFORSYS8(PROJ%%W/ENCL KSEYFRIT/IE%%W/ENCL CONTROLNBR:780860147 At~THEEND
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~g~"~~;-),$)I)~~.(gPg~XKDsesTWONORTHNINTHSTREET,ALLENTOWN, PA.18101/g$ITJNE:(215)821-5151NORMANW,CURTISVicePresident Engineering 8Construction 821-5381SeptEmber 15,1978Mr.BoyceH.GrierDirector, RegionIU.S.NuclearRegulatory Cczanission 631ParkAvenueKingofPrussia,Pennsylvania 17406CJo>Irrc's'nv>+mCnrnCllPl<onaP1~CDC)SUSQUEEQKA STEAMELECTRICSTATIONF3'EPORTOFADEFICIENT',CY INSEISMICQUAIZFICATION OFI%DENVOLTAGE,M'TALCLAD,SM."%GUARDS SWITCHGFAR DOCKETNO.:50-387LICENSENO:CPPR-101ER100450FILE840-4PLA289'~=I~4\I
DearMr.Grier:
Thissupplements PPSZlettersPLA-246,datedApril17,1978andPLA-271,datedJuly14,1978,andprovidesafinalreportofthesubjectdeficiency asrecpuzedby10CFR50.55 (e).Pleaseadviseshouldyourecureadditional information.
Verytrulyyours,N.W.CurtisVicePresident-Engineering 6Construction Attachment ARS:mcbcc:Mr.J.G.Davis(15)ActingDirector-Office ofInspection 6Enforcement U.S.NuclearReyQatory Ccmiission--
Washington, D.C.20555Mr.G.MDonald,Director(1)OfficeofManaganent,,Information 6~amContxol'U.S.NuclearRegulatory Ccmtission Washington, D.C.20555PENNSYLVANIA POWER8,LIGHTCOMPANYt78p86p147 9'e~t
'Mr.B.H.GrierSept.anber 15,1978cc:Mr.RobertM.GalloU.S.NuclearRegulatory Gmxnission P.O.Box52Shickshinny, Pennsylvania 18655 OFADEFICIENCY INSEISMICQUALIFICATION OFMEDIUMVOLTAGE,MEALCLAD,SAFEGUABDS SWHCHG1RR FORTHESUSQUEHANNA STEAM1KZCTRICSTATICND.P.ParsonsSSESElectrical GroupSupvr.ApprovedBy:..~~~9r~pg.A.M.eSupervising Engineer-Design-Suscpehanna Reviewed:
A.R.ScilManager-Nuclear QualityAssurance PENNSYLVANIA HMK6LIGHTCCMPANYAL'EZKTQWN, PENNSYLVANIA S1M.'EMBER 15,1978 TABLEOFCONTENTSIntroduction Description ofDeficiency AnalysisofSafetyImplications Corrective ActionConclusion Pg.lPgs,lg2g3Pg.3Pgs.4,5Pg.5 INTRODUCZION Thisreportispreparedinaccordance withtherequirements described inTitle10,CodeofFederalRegulations, Part50,Section50.55(e).PPKwasadvised,throughitsA/E(Bechtel) organization, t1wtWestinghouse
- supplied, mediumvoltage,metalcladswitchgear wasnotcapableofwithstanding thepostulated seismiceventforSusquehanna Plant.Bechtelwasrequested toreviewthesituation andadvisePPsZofitsfindings.
OnParch31,1978theNRCwasinformedthatadeficiency, potentially reportable under10CFR50.55(e),
wasbeingevaluated, andonApril17,1978,following anengineering review,PALissueditsInterimReportofthedeficiency.
Thedeficiency wasdetermined tobereportable under10CFR50.55(e) forthefollowing reasons:1.Thedeficiency, wereittoremainuncorrected, couldhaveresultedinasafetyhazardtotheoperation oftheplant.2.Thedeficiency represented adeficiency infinaldesignasapprovedandreleasedforfabrication andinstallation.
3.Eightsafety-related switchgear unitshad,beenshippedandacceptedforinstallation beforethedeficiency wasdiscovered.
DJHCRIPTION OFDEFICIENCY TheSusquehanna Plantwassuppliedeightdeficient safetyrelatedmediumvoltageswitchgear unitsbyWestinghouse.
Fouroftheseswitchgear unitssupplypowerdirectlyto4kvsafetyrelatedequipnent, pumprmtorsandloadcenters,>RichareusedtomitigatetheeffectsofanaccidentinUnitl.
- Likewise, fourswitchgear unitsareusedasthesupplyfor4kvsafetyrelatedloadsonUnit2.Eachswitchgear unit,containsthreepotential transformer
- circuits, oneofthecircuitsconsistsof~potential transformers connected inanopendelta.Theothertwocircuitseachcontainonepotential transformer usedtosensesinglephasepotential.
Thepotential transformers areusedtoobtain120volt,potential irr3ication forusewithrelaysontheswitchgear units'heIIediumVoltageYwtalCladSwitchgear (Safeguards)
Specification(8856-E-109) requirestheequipment tomeetseismicrecpdxements ofProjectSpecification 8856-6-10, IEEEStandardM.344,andtoreaeinfunctional, koth,duringandafteranOBEorDBE.Westinghouse advisedBechtelonJanuary24,1978thatthepotential transformer secondary disconnecting contactassanblies onequignent similartothatsuppliedforSusquehanna hadfailedtowithstand recentseismictests.Westinghouse furtherstatedthat,underseismicconditions, itispossiblethattheslip-fitsecondary contactscouldbedislodged frantheirnormalpositions resulting inopenor.shortcircuiting ofthesecondary circuits.
Westinghouse requested thatBechtelevaluatethecondition todetaanine ifitauldconstitute asafetyhazard..Westinghouse confirmed thattherewerenofailuresofpotential transformer circuitsduringtheoriginalseismicqualification tests.However,thesecircuitsweresubsequent1y redesigned andthenewdesignwasanalytically qualified.
Situalseismictestsonswitchgear unitsincorporating thenewdesignresultedinthepotential transformer circuitfailures>M.charethesubjectofthisreport.
Westinghouse alsoconfirmed thattheseianicqualification ofallothercanponents intheseassemblies remainvalid.MALYSISOFSMOKYIMPLICATIONS Theengineering evaluation determined thattheopenorshortcircuiting ofanyoftheseco~contactscouldresult.inincorrect operation ofaswitchgear unit.Itwasconcluded thattheworstcondition resultsfranthelossofallthreepotential transformer circuitsoneachswitchgear bus.Underthiscondition, thetminccmingbusfeedersfrcmthesafeguard transformers (onefromeachoffsitesource)wouldbeautomatically disconnected frcmeachswitchgear busandthedieselgenerator powersourceconnected restoring powertothebus.ALOCAoccuringduringorafterthepostulated, seismiceventwouldinitiateaclosingsignaltothemotorfeederbreakersoftheshutdownloads,i.e.RHRandCoreSprayHotors.ThesefeederbreakerswouldcloseandismMiately tripduetothefalseundervoltage indication assensedbytheundervoltage relay.Thecircuitbreakerswouldbeunabletocloseagainbecauseofthepermanent undervoltage tripsignalimposedonthem.Theaboveanalysisassumes'hat, thefailuresconcurrently occuronallredundant m~tchgear huses.Basedupontheevaluation ofBechtelEngineering~it isconcluded thatthiscondition ofnotbeingabletosupplypowertotheshutdownloadsunderaDXKcondition constitutes asafetyhazardtotheoperation oftheplantandrepresents adeficiency infinaldesign.
,IP,t,,~
CORRECTIVE
'ACTIONActionTakentoContxol'Deficient.'Items TheactionstakenbyBechtelpriortothesuhnittal oftheinterimreportofthedeficiency byPP&Laredomunented inPZA-246datedApril17,1978.Inadditiontothemeasurespreviously identified, andintheinterestofobtaining documented evidenceofBechtelPxojectEngineering's evaluation ofthecondition's cause,corrective actionrequired, andreportability under10CFR50.55(e),
BechtelQAgenerated Ihnagerrent Corrective ActionRequestNo.1-22datedMarch28,1978.Corrective Actionto'Control'Resolution
'of'theDeficiencies Westinghouse hassuppliedmodification kitswhichprovideforeliminating thestationaxy, secondary disconnecting contactassemblies fromthepotential transformer circuits.
Twenty-four (24)(threekitsforeachoftheeightsafety-related switchgear units)potential transfoxmer secondary fieMrmdification kits(Westinghouse StyleNo.628F14G01) havebeenprovided.
Theserrodification kitshavebeeninstalled byBechtelfieldelectricians pertheinstructions onWestinghouse drawing628F146.Thesechangesweremadeunderthesupervision oftheWestinghouse Engineering ServicePersonnel.
Themodification consistsofhardwiringthesecondary arablecontacttoatexminalblockviaawiringharness.ThePTsecondary circuitsarethenconnected tothefieldsideoftheterminalblock.Thesecondary stationary contactsareremovedentirely, thuseliminating thesourceoftheseismicfailure.
~~I(~Westinghouse hasseianically qualified thepotential transformers withthe@edifiedsecondary contactarrangement.
Donznented evidenceofthisqualification hasbeenprovidedtoBechtelthrougharevisiontotheoriginalqualification report.COVZIJSXONS l4xlifications havebeenmadetoaU.theWestinghouse safety-related, medianvoltageswitchgear unitscontaining potential transformers andpurchased underP.O.8856-E-109AC forSusquehanna SteamElectricStation.TheBechtelgenerated hMnconfoxmance Report(NCRhM.2514)willnotbeclosedoutuntilBechtelQualityContxolhasperformed theattendant inspections andhasverifiedthatthemxlification kitsrareinstalled according todesignrequirements-Theandifiedswitchgear unitsarequalified tomeetthepostulated seismicevent.forSusquehanna anddocumentation ofthisseismicqualification hasbeenreceivedandwillbereviewedbyBechtelEngineering.
Bechtel's acceptance ofthisdocumentation willresultinanacceptably documented revisiontotheWestinghouse SeianicQualification Report.Theswitchgear units~aspresently
- modified, arecompatible withpurchaseorder,PSARandFSARrequiranents.