ML18040A946

Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Susquehanna-1/-2, Final Technical Evaluation Rept

ML18040A946
Person / Time
Site:	Susquehanna
Issue date:	09/30/1989
From:	UDY A C EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML17156B508	List: ML18040A946
References
CON-FIN-D-6001 EGG-NTA-7308, GL-83-28, TAC-53723, TAC-59515, NUDOCS 8909260167
Download: ML18040A946 (12)

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ENCLOSURE2EGG-NTA-7308TECHNICALEVALUATIONREPORTCONFORMANCETOGENERICLETTER83-28,ITEM2.2.1--E(UIPMENTCLASSIFICATIONFORALLOTHERSAFETY-RELATEDCOMPONENTS;SUS(UEHANNA-I/-2DocketNos.50-387/50-388AlanC.UdyPublishedSeptember1989IdahoNationalEngineeringLaboratoryEGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatoryCommissionWashington,-D.C.20555UnderDOEContractNo.DE-AC07-76ID01570FINNo.D6001TACNos.53723/59515 SUMMARYThisEGEGIdaho,Inc.,reportprovidesareviewofthesubmittalsfromUnitNos.1and2oftheSusquehannaSteamElectricStationforconformancetoGenericLetter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicenseesandapplicantstosubmitadetaileddescriptionoftheirprogramsforsafety-relatedequipmentclassificationforstaffreview.Italsodescribesguidelinesthattheprogramsshouldencompass.Thisreviewconcludesthatthelicenseecomplieswiththerequirementsofthisitem.FINNo.D6001BKRNo.20-19-10-11-3,DocketNos.50-387/50-388TAGNos.53723/5951511 PREFACEThisreportissuppliedaspartoftheprogramforevaluatinglicensee/applicantconformancetoGenericLetter83-28,"RequiredActionsBasedonGenericImplicationsofSalemATWSEvents."ThisworkisbeingconductedfortheU.S.NuclearRegulatoryCommission,Office'fNuclearReactorRegulation,DivisionofEngineeringandSystemTechnology,byEGEGIdaho,Inc.,RegulatoryandTechnicalAssistanceUnit.

CONTENTSSUMMARY........REFACE~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~PINTRODUCTION................2.REVIEWCONTENTANDFORMAT.............~...........3.ITEM2.2.1-PROGRAM.....................3.13.23.3Guideline.........Evaluation..~.....Conclusion~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~333ITEH2.2.1.1-IDENTIFICATIONCRITERIA...4.14.24.3Guideline....Evaluation...Conclusion~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~445.ITEM2.2.1.2-INFORMATIONHANDLINGSYSTEM..5.15.25.3~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Guideline........................EvaluationConclusion5566.ITEM2.2.1.3-USEOFTHEEQUIPMENTCLASSIFICATIONLISTING.......6.16.26.3Guideline..EvaluationConclusion~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~~~~~7777.ITEM2.2.1.4-MANAGEMENTCONTROLS7.17.27.3uideline...........................GEvaluation..........................Conclusion~~~~~~~~~~~~~~~~~~~~~~~~~~8888.ITEM2.2.1.5-DESIGNVERIFICATIONANDPROCUREMENT...............8.18.28.3Guideline.............Evaluation.....,,.....Conclusion............~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~9999.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY"COMPONENTS109.1Guideline......,....................,.............1010.CONCLUSION12iv CONFORMANCETOGENERICLETTER83-28ITEM2.2.1--EUIPMENTCLASSIFICATIONFORALLOTHERSAFETY-RELATEDCOMPONENTS:SUSUEHANNA-1-21.INTRODUCTIONOnFebruary25,1983,bothofthescramcircuitbreakersatUnit1oftheSalemGeneratingStationfailedtoopenuponanautomaticreactortripsignalfromthereactorprotectionsystem.Thisincidentwasterminatedmanuallybytheoperatorabout30secondsaftertheinitiationoftheautomatictripsignal.Thefailureofthecircuitbreakerswasdeterminedtoberelatedtothestickingoftheundervoltagetripattachment.Priortothisincident,onFebruary22,1983,atUnit1oftheSalemGeneratingStation,anautomatictripsignalwasgeneratedbasedonsteamgeneratorlow-lowlevelduringplantstartup.Inthiscase,thereactorwastrippedmanuallybytheoperatoralmostcoincidentallywiththeautomatictrip.Followingtheseincidents,onFebruary281983,theNRCExecutiveDirectorforOperations(EDO)directedtheNRCstafftoinvestigateandreportonthegenericimplicationsoftheseoccurrencesatUnit1oftheSalemGeneratingStation.Theresultsofthestaff'sinquiryintothegenericimplicationsoftheSalem-1incidentsarereportedinNUREG-1000,"GenericImplicationsoftheATWSEventsattheSalemNuclearPowerPlant."Asaresultofthisinvestigation,theCommission(NRC)requested(byGenericLetter83-28datedJuly8,1983)thatalllicenseesofoperatingreactors,applicantsforanoperatinglicense,andholdersofconstructionpermitsrespondtothegenericissuesraisedbytheanalysesofthesetwoATWSevents.ThisreportisanevaluationoftheresponsessubmittedbythePennsylvaniaPower8LightCompany,thelicenseefortheSusquehannaSteamElectricStation,forItem2.2.1ofGenericLetter83-28.ThedocumentsreviewedasapartofthisevaluationarelistedintheReferences(Section11)attheendofthisreport.

3.ITEN2.2.1-PROGRAN3.1GuidelineLicenseesshouldconfirmthatanequipmentclassificationprogramisinplacethatwillprovideassurancethatsafety-relatedcomponentsaredesignatedassafety-relatedonplantdocumentation.Theprogramshouldprovideassurancethattheequipmentclassificationinformationhandlingsystemisusedsothatactivitiesthatmayaffectsafety-relatedcomponentsaredesignatedsafety-related.Byusingtheinformationhandlingsystem,personnelaremadeawarethattheyareworkingonsafety-relatedcomponentsandaredirectedto,andareguidedby,safety-relatedproceduresandconstraints.Licenseeresponsesthataddressthefeaturesofthisprogramareevaluatedintheremainderofthisreport.3.2EvaluationThelicenseefortheSusquehannaSteamElectricStationrespondedtotheserequirementswithsubmittalsdatedHovember4,1983,2andNarch1,1984.Thesesubmittalsdescribethelicensee'ssafety-relatedequipmentclassificationprogram.Thelicensee'sQualityConsiderationLists(QCLs)andthecomponentQ-list,whichisapartoftheQCL,formtheinformationhandlingsystemreferredto.Inthereviewofthelicensee'sresponsetothisitem,itwasassumedthattheinformationanddocumentationsupportingthisprogramisavailableforaudituponrequest.3.3ConclusionWehavereviewedthelicensee'ssubmittalsandfindthatthelicensee'sprogramisacceptable,asindicatedinthefollowingsections.

5.ITEN2.2.1.2-INFORHATIONHANDLINGSYSTEH5.1GuidelineThelicenseeshouldconfirmthattheprogramforequipmentclassificationincludesaninformationhandlingsystemthatisusedtoidentifysafety-relatedcomponents.Theresponseshouldconfirmthatthisinformationhandlingsystemincludesalistofsafety-relatedequipmentandthatproceduresexistwhichgovernitsdevelopmentandvalidation.5.2EvaluationThelicenseestatesthatthegualityConsiderationLists(gCLs),whichincludestheg-list(safety-relateditemsonly),fireprotection(F-List),ASHE-Code,Non-g(A-List),andqualitygroupDaugmented(D-List),defineallqualitysystems,components,andstructures.Thelicenseestatesthattheg-list,whichlistssafety-relatedsystems,structures,andcomponents,isbasedonTable3.2.2oftheFinalSafetyAnalysisReport.ThelicenseestatesthatthegCLswereoriginallydevelopedandarenowcontrolledandupdatedbythenuclearplantengineeringdepartmentinaccordancewithprocedures.NuclearDepartmentInstructionNDI-(A-15.1.2,"gualityConsiderationLists,"designatesthemanagerofthenuclearplantengineeringdepartmentastheresponsibleindividualforprovidingsafetyclassificationsofsystems,structures,andcomponents,fordevelopmentandupdatingthegCLs,forcontrollingdesigndocumentsanddatabasescontainingqualityclassifications,andforcontrollingcomputerprogramsthatareimportanttosafety.ThegCLsareissuedperiodicallyas,controlleddocumentsbythemanagerofthenuclearadministrationdepartment.Thelicensee'sOperationalgualityAssuranceProgramauditstheseprocedurestoassurethattheyarefollowedfortheclassificationoflisteditems,thatitemsareverifiedcorrectlyentered,thatunauthorizedchangestothegCLsareprevented,andthatthegCLsaremaintainedanddistributedasofficial,consistent,andunambiguousdocuments.

7.ITEM2.2.1.4-MANAGEMENTCONTROLS7.1GuidelineThelicenseeshouldbrieflydescribethemanagementcontrolsthatareusedtoverifythattheproceduresforthepreparation,validation,androutineutilizationoftheinformationhandlingsystemhavebeen,andarebeing,followed.7.2EvaluationThelicensee'sresponsestatesthattheirOperationalgualityAssuranceProgramservesasthemethodofmanagerialcontrol.Periodicreviewsandaudits,andotherunspecifiedmanagementcontrols,areusedtoverifythepreparation,validation,androutineuseofthegCLsandtoassurethatsafety-relatedactivitiesandtheirimplementationarecorrect.ChangestotheSEISdataarecontrolledbyIndexChangeNotice(ICN)Forms15.2.12Athrough15.2.12K,partofNDI-gA-15.2.12.Thenuclearplantengineeringdepartmentisresponsibleforthepreparation,validation,andupkeepoftheSEIS,byfollowingaSoftwaregualityAssurancePlanandusingthesystemandcomputerservicesdepartmentfortechnicalsupport.Thenuclearqualityassurancedepartmentperformsauditsandsurveillancesoftheactivitiesinvolvingthepreparation,validation,andupkeepoftheSEIS.Thesequalityassuranceactivitiesinformmanagementofthestatusandperformanceoftheequipmentclassificationsystem.7.3ConclusionWefindthatthemanagementcontrolsusedbythelicenseeassurethattheinformationhandlingsystemismaintained,iscurrent,andisusedasintended.Therefore,wefindthelicensee'sresponsesforthisitemacceptable.

9.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY"COMPONENTS9.1GuidelineGenericLetter83-28statesthatthelicensee'sequipmentclassificationprogramshouldinclude(inadditiontothesafety-relatedcomponents)abroaderclassofcomponentsdesignatedas"ImportanttoSafety."However,sincethegenericletterdoesnotrequirethelicenseetofurnishthisinformationaspartoftheirresponse,thisitemwillnotbereviewed.10 11.REFERENCES1.Letter,NRC(D.G.Eisenhut)toallLicenseesofOperatingReactors,ApplicantsforOperatingLicense,andHoldersofConstructionPermits,."RequiredActionsBasedonGenericImplicationsofSalemATWSEvents(GenericLetter83-28),"July8,1983.2.Letter,PennsylvaniaPower&LightCompany,(N.W.Curtis)toNRC(0.G.Eisenhut),"ResponsetoGenericLetter83-28,"November4,1983,ER100450/100508,File841-2,PLA-1827.3.Letter,PennsylvaniaPower8LightCompany,(N.W.Curtis)toNRC(D.G.Eisenhut),"RevisedResponsetoGenericLetter83-28,"March1,1984,ERS100450/100508,File841-2,PLA-2095.12 NRCSORM33512SSIttRI~IIO2,)201,220'2U.S.NUCLEARREGULATORYCSIONBIBLlOGRAPHICOATASHEETISooimtrttctionsonthoroycrsol1.RFPORTNUMBERIcttonottttyNIIC.AddVot.,Svoo.,ltcy.,~nttAootnoomNomttotLIttny,)EGG-NTA-7308Z.TITLEANOSUBTITLECONFORMANCETOGENERICLETTER83-28,ITEM2.2.1--EQUIPMENTCLASSIfICATIONFARALLOTHERSAfETY-RELATEDCOMPONENTS:SUSQUEHANNA-1/-2.S.AUTHORIS)AlanC.Udy3.OATEREPOR'ToUBLISlvEOMONTHySAASeptember19894.FINORGRANTNUMBERD6001B.TYPEOFREPORTTechnicalEvaluationReport7.PERIODCOVEREOttnctvv~OttntB,PERFORMINGORGANIZATION-NAMEANOAOORESSillrtltCpromdrOiyrvon.Ollicrorttrtion,M*iyvcPtorRrovtctotyCommitvon,tndmortinptddrtttittcontroctorproriorntrnotndmtrlintaarrotclEG8GIdaho,Inc.P.0.Box1625IdahoFalls,ID834159.SPONSORINGORGANIZATION-NAMEANOAOORCSSillripe.typoSt~nttoom-.rrcontroctorprontritttCtie~.Orrtcoorrtrcitm.uXrlvctotrtttdvtctoryComnvon.~ndmottindoddtycLIDivisionofSystemsTechnologyOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionwashington,DC2055510.SUPPLEMENTARYNOTES11.ABSTRACTt2tipcorotorNttlThisEGSGIdaho,Inc.,reportprovidesareviewofthesubmittalsfromtheSusquehannaSteamElectricStationforconformancetoGenericletter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicenseesandapplicantstosubmitadetaileddescriptionoftheirprogramsforsafety-relatedequipmentclassificationforstaffreview.Italsodescribesguidelinesthatthelicensee'sorapplicant'sprogramsshouldencompass.Thereviewconcludesthatthelicenseecomplieswiththerequirementsofthisitem.12.KEYWOROS/0ESCRlPTORSILittwortttorpnrototrttttmttottntrotrorcncrtinlocttmotnrrcport.l)2.AIrAtLAAILITTSTATSMSNTunlimtteaDistribution14.SSCUAITYCLASStotCATIONIToteptdclUnclassifiedttn!sltcportlUnclassified15.NUMBEROFPAGESIB.PRICENACPOIIM22$I24SI 0C~44C7rr4a