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{{#Wiki_filter: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.
{{#Wiki_filter:ENCLOSURE 2EGG-NTA-7308 TECHNICAL EVALUATION REPORTCONFORMANCE TOGENERICLETTER83-28,ITEM2.2.1--E(UIPMENT CLASSIFICATION FORALLOTHERSAFETY-RELATED COMPONENTS; SUS(UEHANNA-I/-2DocketNos.50-387/50-388 AlanC.UdyPublished September 1989IdahoNationalEngineering Laboratory EGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatory Commission Washington,
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.
-D.C.20555UnderDOEContractNo.DE-AC07-76ID01570 FINNo.D6001TACNos.53723/59515 SUMMARYThisEGEGIdaho,Inc.,reportprovidesareviewofthesubmittals fromUnitNos.1and2oftheSusquehanna SteamElectricStationforconformance toGenericLetter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicensees andapplicants tosubmitadetaileddescription oftheirprogramsforsafety-related equipment classification forstaffreview.Italsodescribes guidelines thattheprogramsshouldencompass.
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.
Thisreviewconcludes thatthelicenseecomplieswiththerequirements ofthisitem.FINNo.D6001BKRNo.20-19-10-11-3, DocketNos.50-387/50-388 TAGNos.53723/59515 11 PREFACEThisreportissuppliedaspartoftheprogramforevaluating licensee/applicant conformance toGenericLetter83-28,"Required ActionsBasedonGenericImplications ofSalemATWSEvents."Thisworkisbeingconducted fortheU.S.NuclearRegulatory Commission, Office'fNuclearReactorRegulation, DivisionofEngineering andSystemTechnology, byEGEGIdaho,Inc.,Regulatory andTechnical Assistance Unit.
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.
CONTENTSSUMMARY........REFACE~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~PINTRODUCTION
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.typo''St~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}}
2.REVIEWCONTENTANDFORMAT.............
~...........
3.ITEM2.2.1-PROGRAM.....................
3.13.23.3Guideline
.........
Evaluation
..~.....Conclusion
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~333ITEH2.2.1.1-IDENTIFICATION CRITERIA...4.14.24.3Guideline
....Evaluation
...Conclusion
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~445.ITEM2.2.1.2-INFORMATION HANDLINGSYSTEM..5.15.25.3~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Guideline
........................
Evaluation Conclusion 5566.ITEM2.2.1.3-USEOFTHEEQUIPMENT CLASSIFICATION LISTING.......6.16.26.3Guideline
..Evaluation Conclusion
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~~~~~7777.ITEM2.2.1.4-MANAGEMENT CONTROLS7.17.27.3uideline...........................
GEvaluation
..........................
Conclusion
~~~~~~~~~~~~~~~~~~~~~~~~~~8888.ITEM2.2.1.5-DESIGNVERIFICATION ANDPROCUREMENT...............
8.18.28.3Guideline
.............
Evaluation
.....,,.....
Conclusion
............
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~9999.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY" COMPONENTS 109.1Guideline
......,....................,.............
1010.CONCLUSION 12iv CONFORMANCE TOGENERICLETTER83-28ITEM2.2.1--EUIPMENTCLASSIFICATION FORALLOTHERSAFETY-RELATED COMPONENTS:
SUSUEHANNA-1
-21.INTRODUCTION OnFebruary25,1983,bothofthescramcircuitbreakersatUnit1oftheSalemGenerating Stationfailedtoopenuponanautomatic reactortripsignalfromthereactorprotection system.Thisincidentwasterminated manuallybytheoperatorabout30secondsaftertheinitiation oftheautomatic tripsignal.Thefailureofthecircuitbreakerswasdetermined toberelatedtothestickingoftheundervoltage tripattachment.
Priortothisincident, onFebruary22,1983,atUnit1oftheSalemGenerating Station,anautomatic tripsignalwasgenerated basedonsteamgenerator low-lowlevelduringplantstartup.Inthiscase,thereactorwastrippedmanuallybytheoperatoralmostcoincidentally withtheautomatic trip.Following theseincidents, onFebruary281983,theNRCExecutive DirectorforOperations (EDO)directedtheNRCstafftoinvestigate andreportonthegenericimplications oftheseoccurrences atUnit1oftheSalemGenerating Station.Theresultsofthestaff'sinquiryintothegenericimplications oftheSalem-1incidents arereportedinNUREG-1000, "GenericImplications oftheATWSEventsattheSalemNuclearPowerPlant."Asaresultofthisinvestigation, theCommission (NRC)requested (byGenericLetter83-28datedJuly8,1983)thatalllicensees ofoperating
: reactors, applicants foranoperating license,andholdersofconstruction permitsrespondtothegenericissuesraisedbytheanalysesofthesetwoATWSevents.Thisreportisanevaluation oftheresponses submitted bythePennsylvania Power8LightCompany,thelicenseefortheSusquehanna SteamElectricStation,forItem2.2.1ofGenericLetter83-28.Thedocuments reviewedasapartofthisevaluation arelistedintheReferences (Section11)attheendofthisreport.
3.ITEN2.2.1-PROGRAN3.1Guideline Licensees shouldconfirmthatanequipment classification programisinplacethatwillprovideassurance thatsafety-related components aredesignated assafety-related onplantdocumentation.
Theprogramshouldprovideassurance thattheequipment classification information handlingsystemisusedsothatactivities thatmayaffectsafety-related components aredesignated safety-related.
Byusingtheinformation handlingsystem,personnel aremadeawarethattheyareworkingonsafety-related components andaredirectedto,andareguidedby,safety-related procedures andconstraints.
Licenseeresponses thataddressthefeaturesofthisprogramareevaluated intheremainder ofthisreport.3.2Evaluation ThelicenseefortheSusquehanna SteamElectricStationresponded totheserequirements withsubmittals datedHovember4,1983,2andNarch1,1984.Thesesubmittals describethelicensee's safety-related equipment classification program.Thelicensee's QualityConsideration Lists(QCLs)andthecomponent Q-list,whichisapartoftheQCL,formtheinformation handlingsystemreferredto.Inthereviewofthelicensee's responsetothisitem,itwasassumedthattheinformation anddocumentation supporting thisprogramisavailable foraudituponrequest.3.3Conclusion Wehavereviewedthelicensee's submittals andfindthatthelicensee's programisacceptable, asindicated inthefollowing sections.
5.ITEN2.2.1.2-INFORHATION HANDLINGSYSTEH5.1Guideline Thelicenseeshouldconfirmthattheprogramforequipment classification includesaninformation handlingsystemthatisusedtoidentifysafety-related components.
Theresponseshouldconfirmthatthisinformation handlingsystemincludesalistofsafety-related equipment andthatprocedures existwhichgovernitsdevelopment andvalidation.
5.2Evaluation ThelicenseestatesthatthegualityConsideration Lists(gCLs),whichincludestheg-list(safety-related itemsonly),fireprotection (F-List),
ASHE-Code, Non-g(A-List),
andqualitygroupDaugmented (D-List),
defineallqualitysystems,components, andstructures.
Thelicenseestatesthattheg-list,whichlistssafety-related systems,structures, andcomponents, isbasedonTable3.2.2oftheFinalSafetyAnalysisReport.ThelicenseestatesthatthegCLswereoriginally developed andarenowcontrolled andupdatedbythenuclearplantengineering department inaccordance withprocedures.
NuclearDepartment Instruction NDI-(A-15.
1.2,"gualityConsideration Lists,"designates themanagerofthenuclearplantengineering department astheresponsible individual forproviding safetyclassifications ofsystems,structures, andcomponents, fordevelopment andupdatingthegCLs,forcontrolling designdocuments anddatabases containing qualityclassifications, andforcontrolling computerprogramsthatareimportant tosafety.ThegCLsareissuedperiodically as,controlled documents bythemanagerofthenuclearadministration department.
Thelicensee's Operational gualityAssurance Programauditstheseprocedures toassurethattheyarefollowedfortheclassification oflisteditems,thatitemsareverifiedcorrectly entered,thatunauthorized changestothegCLsareprevented, andthatthegCLsaremaintained anddistributed asofficial, consistent, andunambiguous documents.
7.ITEM2.2.1.4-MANAGEMENT CONTROLS7.1Guideline Thelicenseeshouldbrieflydescribethemanagement controlsthatareusedtoverifythattheprocedures forthepreparation, validation, androutineutilization oftheinformation handlingsystemhavebeen,andarebeing,followed.
7.2Evaluation Thelicensee's responsestatesthattheirOperational gualityAssurance Programservesasthemethodofmanagerial control.Periodicreviewsandaudits,andotherunspecified management
: controls, areusedtoverifythepreparation, validation, androutineuseofthegCLsandtoassurethatsafety-related activities andtheirimplementation arecorrect.ChangestotheSEISdataarecontrolled byIndexChangeNotice(ICN)Forms15.2.12Athrough15.2.12K,partofNDI-gA-15.2.
12.Thenuclearplantengineering department isresponsible forthepreparation, validation, andupkeepoftheSEIS,byfollowing aSoftwaregualityAssurance Planandusingthesystemandcomputerservicesdepartment fortechnical support.Thenuclearqualityassurance department performsauditsandsurveillances oftheactivities involving thepreparation, validation, andupkeepoftheSEIS.Thesequalityassurance activities informmanagement ofthestatusandperformance oftheequipment classification system.7.3Conclusion Wefindthatthemanagement controlsusedbythelicenseeassurethattheinformation handlingsystemismaintained, iscurrent,andisusedasintended.
Therefore, wefindthelicensee's responses forthisitemacceptable.
9.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY" COMPONENTS 9.1Guideline GenericLetter83-28statesthatthelicensee's equipment classification programshouldinclude(inadditiontothesafety-related components) abroaderclassofcomponents designated as"Important toSafety."However,sincethegenericletterdoesnotrequirethelicenseetofurnishthisinformation aspartoftheirresponse, thisitemwillnotbereviewed.
10 11.REFERENCES 1.Letter,NRC(D.G.Eisenhut) toallLicensees ofOperating
: Reactors, Applicants forOperating License,andHoldersofConstruction Permits,."Required ActionsBasedonGenericImplications ofSalemATWSEvents(GenericLetter83-28),"July8,1983.2.Letter,Pennsylvania Power&LightCompany,(N.W.Curtis)toNRC(0.G.Eisenhut),
"Response toGenericLetter83-28,"November4,1983,ER100450/100508, File841-2,PLA-1827.
3.Letter,Pennsylvania Power8LightCompany,(N.W.Curtis)toNRC(D.G.Eisenhut),
"RevisedResponsetoGenericLetter83-28,"March1,1984,ERS100450/100508, File841-2,PLA-2095.
12 NRCSORM33512SSIttRI~IIO2,)201,220'2U.S.NUCLEARREGULATORY CSIONBIBLlOGRAPHIC OATASHEETISooimtrttctions onthoroycrsol1.RFPORTNUMBERIcttonott ttyNIIC.AddVot.,Svoo.,ltcy.,~nttAootnoomNomttotLIttny,)EGG-NTA-7308 Z.TITLEANOSUBTITLECONFORMANCE TOGENERICLETTER83-28,ITEM2.2.1--EQUIPMENT CLASSIfICATION FARALLOTHERSAfETY-RELATED COMPONENTS:
SUSQUEHANNA-1/-2.
S.AUTHORIS)
AlanC.Udy3.OATEREPOR'ToUBLISlvEO MONTHySAASeptember 19894.FINORGRANTNUMBERD6001B.TYPEOFREPORTTechnical Evaluation Report7.PERIODCOVEREOttnctvv~OttntB,PERFORMING ORGANIZATION
-NAMEANOAOORESSillrtltCpromdrOiyrvon.Ollicrorttrtion,M*iyvcPtorRrovtctoty Commitvon, tndmortinptddrtttitt controctor proriorntrnotndmtrlintaarrotclEG8GIdaho,Inc.P.0.Box1625IdahoFalls,ID834159.SPONSORING ORGANIZATION
-NAMEANOAOORCSSillripe.typo''St~nttoom-.rrcontroctor prontritttCtie~.Orrtcoorrtrcitm.uXrlvctotrtttdvtctory Comnvon.~ndmottindoddtycLIDivisionofSystemsTechnology OfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commissionwashington, DC2055510.SUPPLEMENTARY NOTES11.ABSTRACTt2tipcorotorNttlThisEGSGIdaho,Inc.,reportprovidesareviewofthesubmittals fromtheSusquehanna SteamElectricStationforconformance toGenericletter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicensees andapplicants tosubmitadetaileddescription oftheirprogramsforsafety-related equipment classification forstaffreview.Italsodescribes guidelines thatthelicensee's orapplicant's programsshouldencompass.
Thereviewconcludes thatthelicenseecomplieswiththerequirements ofthisitem.12.KEYWOROS/0ESCRlPTORS ILittwortttorpnrototrttttmttottntrotrorcncrt inlocttmotnrrcport.l)2.AIrAtLAAILITT STATSMSNT unlimttea Distribution 14.SSCUAITYCLASStotCATION IToteptdclUnclassified ttn!sltcportlUnclassified 15.NUMBEROFPAGESIB.PRICENACPOIIM22$I24SI 0C~44C7rr4a}}

Revision as of 02:19, 29 June 2018

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

ENCLOSURE 2EGG-NTA-7308 TECHNICAL EVALUATION REPORTCONFORMANCE TOGENERICLETTER83-28,ITEM2.2.1--E(UIPMENT CLASSIFICATION FORALLOTHERSAFETY-RELATED COMPONENTS; SUS(UEHANNA-I/-2DocketNos.50-387/50-388 AlanC.UdyPublished September 1989IdahoNationalEngineering Laboratory EGKGIdaho,Inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatory Commission Washington,

-D.C.20555UnderDOEContractNo.DE-AC07-76ID01570 FINNo.D6001TACNos.53723/59515 SUMMARYThisEGEGIdaho,Inc.,reportprovidesareviewofthesubmittals fromUnitNos.1and2oftheSusquehanna SteamElectricStationforconformance toGenericLetter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicensees andapplicants tosubmitadetaileddescription oftheirprogramsforsafety-related equipment classification forstaffreview.Italsodescribes guidelines thattheprogramsshouldencompass.

Thisreviewconcludes thatthelicenseecomplieswiththerequirements ofthisitem.FINNo.D6001BKRNo.20-19-10-11-3, DocketNos.50-387/50-388 TAGNos.53723/59515 11 PREFACEThisreportissuppliedaspartoftheprogramforevaluating licensee/applicant conformance toGenericLetter83-28,"Required ActionsBasedonGenericImplications ofSalemATWSEvents."Thisworkisbeingconducted fortheU.S.NuclearRegulatory Commission, Office'fNuclearReactorRegulation, DivisionofEngineering andSystemTechnology, byEGEGIdaho,Inc.,Regulatory andTechnical Assistance Unit.

CONTENTSSUMMARY........REFACE~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~PINTRODUCTION

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

2.REVIEWCONTENTANDFORMAT.............

~...........

3.ITEM2.2.1-PROGRAM.....................

3.13.23.3Guideline

.........

Evaluation

..~.....Conclusion

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~333ITEH2.2.1.1-IDENTIFICATION CRITERIA...4.14.24.3Guideline

....Evaluation

...Conclusion

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~445.ITEM2.2.1.2-INFORMATION HANDLINGSYSTEM..5.15.25.3~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Guideline

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

Evaluation Conclusion 5566.ITEM2.2.1.3-USEOFTHEEQUIPMENT CLASSIFICATION LISTING.......6.16.26.3Guideline

..Evaluation Conclusion

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~~~~~~~7777.ITEM2.2.1.4-MANAGEMENT CONTROLS7.17.27.3uideline...........................

GEvaluation

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

Conclusion

~~~~~~~~~~~~~~~~~~~~~~~~~~8888.ITEM2.2.1.5-DESIGNVERIFICATION ANDPROCUREMENT...............

8.18.28.3Guideline

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

Evaluation

.....,,.....

Conclusion

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

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~9999.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY" COMPONENTS 109.1Guideline

......,....................,.............

1010.CONCLUSION 12iv CONFORMANCE TOGENERICLETTER83-28ITEM2.2.1--EUIPMENTCLASSIFICATION FORALLOTHERSAFETY-RELATED COMPONENTS:

SUSUEHANNA-1

-21.INTRODUCTION OnFebruary25,1983,bothofthescramcircuitbreakersatUnit1oftheSalemGenerating Stationfailedtoopenuponanautomatic reactortripsignalfromthereactorprotection system.Thisincidentwasterminated manuallybytheoperatorabout30secondsaftertheinitiation oftheautomatic tripsignal.Thefailureofthecircuitbreakerswasdetermined toberelatedtothestickingoftheundervoltage tripattachment.

Priortothisincident, onFebruary22,1983,atUnit1oftheSalemGenerating Station,anautomatic tripsignalwasgenerated basedonsteamgenerator low-lowlevelduringplantstartup.Inthiscase,thereactorwastrippedmanuallybytheoperatoralmostcoincidentally withtheautomatic trip.Following theseincidents, onFebruary281983,theNRCExecutive DirectorforOperations (EDO)directedtheNRCstafftoinvestigate andreportonthegenericimplications oftheseoccurrences atUnit1oftheSalemGenerating Station.Theresultsofthestaff'sinquiryintothegenericimplications oftheSalem-1incidents arereportedinNUREG-1000, "GenericImplications oftheATWSEventsattheSalemNuclearPowerPlant."Asaresultofthisinvestigation, theCommission (NRC)requested (byGenericLetter83-28datedJuly8,1983)thatalllicensees ofoperating

reactors, applicants foranoperating license,andholdersofconstruction permitsrespondtothegenericissuesraisedbytheanalysesofthesetwoATWSevents.Thisreportisanevaluation oftheresponses submitted bythePennsylvania Power8LightCompany,thelicenseefortheSusquehanna SteamElectricStation,forItem2.2.1ofGenericLetter83-28.Thedocuments reviewedasapartofthisevaluation arelistedintheReferences (Section11)attheendofthisreport.

3.ITEN2.2.1-PROGRAN3.1Guideline Licensees shouldconfirmthatanequipment classification programisinplacethatwillprovideassurance thatsafety-related components aredesignated assafety-related onplantdocumentation.

Theprogramshouldprovideassurance thattheequipment classification information handlingsystemisusedsothatactivities thatmayaffectsafety-related components aredesignated safety-related.

Byusingtheinformation handlingsystem,personnel aremadeawarethattheyareworkingonsafety-related components andaredirectedto,andareguidedby,safety-related procedures andconstraints.

Licenseeresponses thataddressthefeaturesofthisprogramareevaluated intheremainder ofthisreport.3.2Evaluation ThelicenseefortheSusquehanna SteamElectricStationresponded totheserequirements withsubmittals datedHovember4,1983,2andNarch1,1984.Thesesubmittals describethelicensee's safety-related equipment classification program.Thelicensee's QualityConsideration Lists(QCLs)andthecomponent Q-list,whichisapartoftheQCL,formtheinformation handlingsystemreferredto.Inthereviewofthelicensee's responsetothisitem,itwasassumedthattheinformation anddocumentation supporting thisprogramisavailable foraudituponrequest.3.3Conclusion Wehavereviewedthelicensee's submittals andfindthatthelicensee's programisacceptable, asindicated inthefollowing sections.

5.ITEN2.2.1.2-INFORHATION HANDLINGSYSTEH5.1Guideline Thelicenseeshouldconfirmthattheprogramforequipment classification includesaninformation handlingsystemthatisusedtoidentifysafety-related components.

Theresponseshouldconfirmthatthisinformation handlingsystemincludesalistofsafety-related equipment andthatprocedures existwhichgovernitsdevelopment andvalidation.

5.2Evaluation ThelicenseestatesthatthegualityConsideration Lists(gCLs),whichincludestheg-list(safety-related itemsonly),fireprotection (F-List),

ASHE-Code, Non-g(A-List),

andqualitygroupDaugmented (D-List),

defineallqualitysystems,components, andstructures.

Thelicenseestatesthattheg-list,whichlistssafety-related systems,structures, andcomponents, isbasedonTable3.2.2oftheFinalSafetyAnalysisReport.ThelicenseestatesthatthegCLswereoriginally developed andarenowcontrolled andupdatedbythenuclearplantengineering department inaccordance withprocedures.

NuclearDepartment Instruction NDI-(A-15.

1.2,"gualityConsideration Lists,"designates themanagerofthenuclearplantengineering department astheresponsible individual forproviding safetyclassifications ofsystems,structures, andcomponents, fordevelopment andupdatingthegCLs,forcontrolling designdocuments anddatabases containing qualityclassifications, andforcontrolling computerprogramsthatareimportant tosafety.ThegCLsareissuedperiodically as,controlled documents bythemanagerofthenuclearadministration department.

Thelicensee's Operational gualityAssurance Programauditstheseprocedures toassurethattheyarefollowedfortheclassification oflisteditems,thatitemsareverifiedcorrectly entered,thatunauthorized changestothegCLsareprevented, andthatthegCLsaremaintained anddistributed asofficial, consistent, andunambiguous documents.

7.ITEM2.2.1.4-MANAGEMENT CONTROLS7.1Guideline Thelicenseeshouldbrieflydescribethemanagement controlsthatareusedtoverifythattheprocedures forthepreparation, validation, androutineutilization oftheinformation handlingsystemhavebeen,andarebeing,followed.

7.2Evaluation Thelicensee's responsestatesthattheirOperational gualityAssurance Programservesasthemethodofmanagerial control.Periodicreviewsandaudits,andotherunspecified management

controls, areusedtoverifythepreparation, validation, androutineuseofthegCLsandtoassurethatsafety-related activities andtheirimplementation arecorrect.ChangestotheSEISdataarecontrolled byIndexChangeNotice(ICN)Forms15.2.12Athrough15.2.12K,partofNDI-gA-15.2.

12.Thenuclearplantengineering department isresponsible forthepreparation, validation, andupkeepoftheSEIS,byfollowing aSoftwaregualityAssurance Planandusingthesystemandcomputerservicesdepartment fortechnical support.Thenuclearqualityassurance department performsauditsandsurveillances oftheactivities involving thepreparation, validation, andupkeepoftheSEIS.Thesequalityassurance activities informmanagement ofthestatusandperformance oftheequipment classification system.7.3Conclusion Wefindthatthemanagement controlsusedbythelicenseeassurethattheinformation handlingsystemismaintained, iscurrent,andisusedasintended.

Therefore, wefindthelicensee's responses forthisitemacceptable.

9.ITEM2.2.1.6-"IMPORTANT-TO-SAFETY" COMPONENTS 9.1Guideline GenericLetter83-28statesthatthelicensee's equipment classification programshouldinclude(inadditiontothesafety-related components) abroaderclassofcomponents designated as"Important toSafety."However,sincethegenericletterdoesnotrequirethelicenseetofurnishthisinformation aspartoftheirresponse, thisitemwillnotbereviewed.

10 11.REFERENCES 1.Letter,NRC(D.G.Eisenhut) toallLicensees ofOperating

Reactors, Applicants forOperating License,andHoldersofConstruction Permits,."Required ActionsBasedonGenericImplications ofSalemATWSEvents(GenericLetter83-28),"July8,1983.2.Letter,Pennsylvania Power&LightCompany,(N.W.Curtis)toNRC(0.G.Eisenhut),

"Response toGenericLetter83-28,"November4,1983,ER100450/100508, File841-2,PLA-1827.

3.Letter,Pennsylvania Power8LightCompany,(N.W.Curtis)toNRC(D.G.Eisenhut),

"RevisedResponsetoGenericLetter83-28,"March1,1984,ERS100450/100508, File841-2,PLA-2095.

12 NRCSORM33512SSIttRI~IIO2,)201,220'2U.S.NUCLEARREGULATORY CSIONBIBLlOGRAPHIC OATASHEETISooimtrttctions onthoroycrsol1.RFPORTNUMBERIcttonott ttyNIIC.AddVot.,Svoo.,ltcy.,~nttAootnoomNomttotLIttny,)EGG-NTA-7308 Z.TITLEANOSUBTITLECONFORMANCE TOGENERICLETTER83-28,ITEM2.2.1--EQUIPMENT CLASSIfICATION FARALLOTHERSAfETY-RELATED COMPONENTS:

SUSQUEHANNA-1/-2.

S.AUTHORIS)

AlanC.Udy3.OATEREPOR'ToUBLISlvEO MONTHySAASeptember 19894.FINORGRANTNUMBERD6001B.TYPEOFREPORTTechnical Evaluation Report7.PERIODCOVEREOttnctvv~OttntB,PERFORMING ORGANIZATION

-NAMEANOAOORESSillrtltCpromdrOiyrvon.Ollicrorttrtion,M*iyvcPtorRrovtctoty Commitvon, tndmortinptddrtttitt controctor proriorntrnotndmtrlintaarrotclEG8GIdaho,Inc.P.0.Box1625IdahoFalls,ID834159.SPONSORING ORGANIZATION

-NAMEANOAOORCSSillripe.typoSt~nttoom-.rrcontroctor prontritttCtie~.Orrtcoorrtrcitm.uXrlvctotrtttdvtctory Comnvon.~ndmottindoddtycLIDivisionofSystemsTechnology OfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commissionwashington, DC2055510.SUPPLEMENTARY NOTES11.ABSTRACTt2tipcorotorNttlThisEGSGIdaho,Inc.,reportprovidesareviewofthesubmittals fromtheSusquehanna SteamElectricStationforconformance toGenericletter83-28,Item2.2.1.Item2.2.1ofGenericLetter83-28requireslicensees andapplicants tosubmitadetaileddescription oftheirprogramsforsafety-related equipment classification forstaffreview.Italsodescribes guidelines thatthelicensee's orapplicant's programsshouldencompass.

Thereviewconcludes thatthelicenseecomplieswiththerequirements ofthisitem.12.KEYWOROS/0ESCRlPTORS ILittwortttorpnrototrttttmttottntrotrorcncrt inlocttmotnrrcport.l)2.AIrAtLAAILITT STATSMSNT unlimttea Distribution 14.SSCUAITYCLASStotCATION IToteptdclUnclassified ttn!sltcportlUnclassified 15.NUMBEROFPAGESIB.PRICENACPOIIM22$I24SI 0C~44C7rr4a

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