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{{#Wiki_filter:~ccax,z~ | {{#Wiki_filter:~ccax,z~rzo DOCmmxra<ST>UBUTION SYSTEM~REGULA1CINFORMATION DZSTRIBUTIOZSTEM | ||
.(RIDE)ACCESSION NBR:9212180049 DOC.DATE: | |||
92/12/16NOTARIZED: | |||
YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E. | |||
AmericanElectricPowerServiceCorp.RECIP.NAME RECIPIENT AFFILIATION COOK,D.C. | |||
DocumentControlBranch(Document ControlDesk)DOCKET0500031505000316 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application foramendstolicensesDPR-58&DPR-74,consisting ofproposedTSpages.IDISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR gENCL!SIZE:P+'TITLE:ORSubmittal: | |||
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LADEANFWCOPIESLTTRENCL1122RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11INTERNAL: | |||
NRR/DET/ESGB NRR/DST/SELB 7ENRR/DST/SRXB 8EOC/LFMBR8GF01EXTERNAL: | |||
NRCPDR111111101111NRR/DOEA/OTSB11 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB NSIC111111101111RNOTETOALL"RIDSRECIPIENTS: | |||
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK.ROOMPl-S7(EXT.504-2065) | |||
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: | |||
LTTR16ENCL14 | |||
AmericanElectricPowerServiceCorporati~ | AmericanElectricPowerServiceCorporati~ | ||
1Riverside Plaza~Columbus, OH432156142231000ÃAEP'NRC:1159C DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74REACTORPROTECTION SYSTEMMODIFICATION U,S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attention: | |||
T.E,MurleyDecember16,1992 | |||
==DearDr.Murley:== | ==DearDr.Murley:== | ||
AnupgradetotheDonaldC.CookNuclearPlant' | AnupgradetotheDonaldC.CookNuclearPlant'sreactorprotection systeminstrumentation isnecessary duetotheincreased maintenance requiredontheexistingFoxboroprotection systemandthedifficulty inobtaining qualified replacement parts.Theupgradeinvolvestheinstallation ofFoxboro's SPEC200andSPEC200MICROlinesofinstrumentation. | ||
Dr,T.E,Murley-2-AEP:NRC: | Webelievethatthismodification willenhanceoverallplantsafetyduetothereduceddrift,enhancedreliability, andgreaterflexibility providedbymicroprocessor-based hardware. | ||
Dr.T.E.Murley-3-AEP:NRC: | Thislineofinstrumentation hasbeenapprovedbytheNRCforuseinthereactorprotection systematHaddamNeckin1990,anditisusedinnuclearandnon-nuclear applications throughout theworld.OnApril21,1992ameetingwasheldamongpersonnel fromAmericanElectricPowerServiceCorporation (AEPSC),Foxboro,andyourstafftodiscusstheplans,schedules, andinterfaces tosupportanupgradetothereactorprotection systemforCookNuclearPlantUnits1and2.Atthatmeeting,weagreedtosubmitthemajorityoftheengineering information andalicensechangerequesttosupportthisupgradebyNovember30,1992'etailsofthismeetingwerereiterated inourletterAEP:NRC:1159B datedMay1,1992.OnDecember1,1992ameetingwasheldamongAEPSC,Foxboro,andtheNRCtodiscusstheformatoftheinformation tobesubmitted, Duringthismeeting,yourstaffadvisedusthatthemajorityoftheengineering information shouldbemadeavailable fortheiraudit,currently anticipated totakeplaceinJanuary1993atFoxboro's officesinFoxboro,Massachusetts. | ||
9212180049 921216PDRADOCK05000315PPDR C' | |||
Dr,T.E,Murley-2-AEP:NRC:1159C Inaddition, wewererequested tosubmitourrequestforalicenseamendment, aswellasvarioussummaryreports,byDecember15,1992.Assuch,thisletterservestotransmitalicenseamendment requestandtherequested summaryreports.Itshouldbestatedthat,whilemostofthedocumentation delineating andsupporting theengineering designandapplication ofthenewinstrumentation iscomplete, severalitemsstillremainopen.Asindicated inourMay1,1992submittal, thefactoryacceptance testreportisscheduled tobecompleted inApril1993.Inaddition, thefinalelectromagnetic interference/radio frequency interference (EMI/RFI) testreportwillnotbecompleted untilJanuary1993.Allofthesedocuments willbemadeavailable foryourstaff'sreviewupontheircompletion. | |||
Attachment 1tothisletterprovidesourrequestforalicenseamendment andourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistinglicensepagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedlicensepages.Attachment 4providesanexplanation ofhowthedetailedengineering datathatAEPSCwillprovidethestaffduringtheirauditofthisprojectisorganized. | |||
Specifically, Attachment 4containstheIssuesTrackingListandtheDocumentation TrackingList,aspresented attheDecember1,1992meeting.Attachment 5providessummaries ofthereportsthathavebeenwrittenonthemajortopicsassociated withthisinstrumentation upgrade.Theseincludereportsonthesubjectsofhardwareandfirmware, environmental effects,seismicqualification, EMI/RFI,powersupply/electrical, independence, failuremodesandeffects,reliability, functional requirements, performance requirements, verification andvalidation, testing,anddiversity. | |||
Thesesummarystatements arebeingsubmitted inresponsetoyourstaff'srequestduringtheDecember1,1992meeting.Itisourunderstanding thatyourstaffwillbeabletosupportareviewschedulethatwillallowshipmentofequipment inMay1993.Wewillprovidewhateversupportisneededinordertomeetthisschedule. | |||
Webelievethattheproposedinstrumentation upgradeandtheassociated licenseamendment willnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | |||
Dr.T.E.Murley-3-AEP:NRC:1159C Incompliance withtherequirements of10CFR50.91(b)(1),copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.54(f)and,assuch,anoathstatement isenclosed. | |||
Sincerely, pmE,E.Fitzpatrick VicePresident ragAttachments CC:D.H.Williams, Jr.A.A.Blind-BridgmanJ.R.PadgettG.CharnoffNFEMSectionChiefA.B.Davis-RegionIIINRCResidentInspector | |||
-Bridgman Dr.T.E.Murley-4-AEP:NRC:11590 be:S.J.BrewerM.L.Horvath-BridgmanJ.B.Kingseed/V. | |||
VanderBurg/R. | |||
A.GreenD.H.Malin/K.J.TothJ.B.ShinnockW.G.Smith,Jr.W.M.Dean,NRC-Washington, D.C.AEP:NRC:1159C DC-N-6015.1 STATEOFOHIO)COUNTYOFFRANKLIN) | |||
E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingReactorProtection SystemModification andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribdayofandsworntobeforemethis19NOTARYPcC(pAm~taD~ | |||
Attachment 1toAEP:NRC:1159C 10CFR50.92AnalysisforChangestoTheDonaldC.CookNuclearPlantOperating License | |||
Attachment 1toAEP:NRC:1159C | |||
==1.0 ReuestforLicenseAmendment== | |||
Page1Thissubmittal constitutes arequestforanamendment totheCookNuclearPlantUnits1and2operating licenses. | |||
Theseamendments willallowtheuseoftheproposeddigitalinstrumentation inthereactorprotection system,Inamemorandum datedJuly1,1991toAshokC.Thadani,Director-DivisionofSystemsTechnology, Mr.StevenA.Varga,Director-DivisionofReactorProjects-I/II, states:Afterreviewing 50.59,itshistory,andtheNRCendorsedguidance(NSAC125),itisouropinionthatthistypeoftechnology replacement | |||
[useofdigitalinstrumentation inthereactorprotection system]cannotbeperformed under50.59.Asnotedinthismemo,weareawareoftheDCCookRPSreplacement projectandwedonotbelievethismodification shouldbeperformed underthe50.59rule.Subsequently, duringtheApril21,1992meeting,AEPSCwasadvisedthatthisinstrumentation changewouldrequirealicenseamendment. | |||
Specifically, weareproposing toaddthefollowing condition asitemnumber2.KtotheUnit1licenseanditem2.LtotheUnit2license:Thelicenseeisauthorised tousedigitalsignalprocessing instrumentation inthereactorprotection system.2.0ScoeofReactorProtection SstemInstrumentation UradeTheproposeddesignchangewillinstallthefollowing equipment inthereactorprotection systemsofbothCookNuclearPlantunits.Thisequipment willperformthesamefunctions astheequipment itreplaces. | |||
FoxboroSPEC200typeanaloginputsignalconditioning equipment, whichchangesthevarioustypesandvaluesofinputsignalsfromthesensorsintoacommontypeofanalogoutputsignalthatrepresents theinputvaluesatthechannellevel. | |||
Attachment 1toAEP:NRC:1159C Page22.FoxboroSPEC200MICROdigitalsignalprocessing equipment, whichtakestheanalogsignalfromtheSPEC200analoginputequipment atthechannelleveland:a~Changestheanalogsignalstodigitalsignals.b.Processes thedigitalsignalsandcomparesthemagainstpredetermined limits,aswellasperformsdynamicfunctions andcalculations. | |||
c.Changestheprocessed digitalsignalsbacktoanalogoutputsignals'. | |||
FoxboroSPEC200analogoutputsignalconditioning equipment, whichtakestheanalogoutputsignalsfromtheSPEC200MICROandconditions themforuseinthecontrolsystem,aswellasforindication andrecording use.4.FoxboroSPEC200typecontactoutputequipment, whichproducesdiscretetripsignalsfromtheSPEC200MICROandprovidestripsignalsforinputtothereactorprotection logicequipment (SSPS).FoxboroSPEC200typepowerdistribution equipment, whichpowersthesignalconditioning andprocessing equipment discussed abo~e.6.75VDCmulti-loop and+15VDCmulti-nest powersupplies, whichprovidepowerforthefieldtransmitters andSPEC200equipment | |||
~3.0Justification Thismodification isnecessary duetotheincreased maintenance requiredontheexistingFoxboroprotection systemandthedifficulty inobtaining qualified replacement parts.Inaddition, thechangesdescribed aboverepresent acompilation ofmodifications andenhancements tothereactorprotection systemthatwillimprovethesystem'sreliability andavailability. | |||
Anearlyidentical systemwasapprovedforusebytheNRCattheHaddamNeckPlantin1990.Inaddition, digitalinstrumentation wasapprovedforuseinboththeSequoyahNuclearPlantandZionStationreactorprotection systems. | |||
Attachment 1toAEP:NRC:1159C Page34.0NoSinificantHazardsConsideration Wehaveevaluated theproposedinstrumentation changesandhavedetermined thatthesechangeswillnotinvolveasignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c). | |||
Operation oftheCookNuclearPlantinaccordance withtheproposedchangeswillnot:Involveasinificantincreaseintherobabilit orconseuencesofanaccidentreviouslevaluated. | |||
TheFoxboroSPEC200andSPEC200MICROlinesofinstrumentation aredesignedtomitigateanticipated operational occurrences anddesignbasisaccidents byactuating thereactortripandengineered safeguards signalscreditedintheCookNuclearPlantsafetyanalyses(seeAttachment 5,ReportNo.2985-WGS-03, "SPEC200/SPEC200MICROHardwareandFirmwareSystemDescription" | |||
).Thisinstrumentation isdesignedtomonitorandprocesssignalsfortemperature, | |||
: pressure, fluidflow,andfluidlevel(seeAttachment 5,ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations," | |||
andReportNo.2985-SKF-01, "Technical Specification Compliance Assessment" | |||
).Whileitisaform,fitandfunctional replacement fortheexistingFoxbororeactorprotection systeminstrumentation, itsreliability andavailability isbetterthanthatofthepresentinstrumentation (seeAttachment 5,ReportNo.2985-HEI-15,"Reliability andMTBFAnalysis" | |||
).Assuch,inthehighlyunlikelyeventthatthenewinstrumentation experiences afailure,theconsequences willnotexceedthosecausedbyafailureoftheexistingsystem.Thenewinstrumentation's failuremodesandeffectsarediscussed inAttachment 5inReportNo.2985-HEI-14, "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200."Sincetheabilityofthereactorprotection syst:emtodetectfaultsandinitiateprotective actionisnotreducedandsincetheFSARanalysesremainboundingasindicated above,theprobability orconsequences ofaccidents previously analyzedarenotincreased. | |||
Createtheossibilit ofanewordifferent kindofaccidentfromanreviouslanalzed.TheFoxboroSPEC200andSPEC200MICROinstrumentation isdesignedtomitigateanticipated operational occurrences anddesignbasiseventsbyactuating reactortriporengineered safeguards signalscreditedinthesafetyanalyses. | |||
Theinstrumentation isdesignedtomonitorandprocesssignals Attachment 1toAEP:NRC:1159C Page4fortemperature, | |||
: pressure, fluidflow,andfluidlevels.Itisaform,fitandfunctional replacement fortheexistingFoxboroanaloginstrumentation. | |||
Toensurethattheequipment willperformasrequired, extensive measureshavebeentakentoensurethattheresponseofthenewinstrumentation isenveloped bythedesignbasisaccidentanalysescontained inChapter14oftheCookNuclearPlantFSAR.Thisisdemonstrated, inpart,inreportsthataresummarized inAttachment 5including: | |||
ReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment;" | |||
ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations;" | |||
andReportNo.2985-SKF-01,"Technical Specification Compliance Assessment." | |||
Application oftheFoxboroinstrumentation intheCookNuclearPlantreactorprotection systemincludes, amongotherthings,suchconsiderations assinglefailure,independence, functional diversity, andseparation criteria. | |||
Inaddition, theresponseoftheinstrumentation duringeventssuchasstationblackoutanddesignbasisearthquake wasassessed. | |||
Thereportscontained inAttachment 5summarize theseefforts,Ananalysisoftheresponsetimesoftheinstrumentation indicates thattheywillbeboundedbytheexistingFSARanalysesandtheexistingCookNuclearPlanttechnical specification limits(seeAttachment 5,ReportNo.2985-HEI-01,"SummaryReportforResponseTimeEvaluations" | |||
).Withregardtotheapplication ofdigitaltechnology intheCookNuclearPlantreactorprotection system,abatteryofEMI/RFIevaluations wasperformed, asdiscussed inReportNo.2985-HEI-03, "Preliminary EMI/RFIEvaluation." | |||
Theseevaluations concluded thattheEMI/RFIenvironment atCookNuclearPlantissuitablefortheapplication ofthistypeofequipments TheSPEC200andSPEC200MICROhavebeendesigned, | |||
: verified, andvalidated tobeincompliance withtheprotection systemfunctional requirements. | |||
Thisstatement issupported byReportNo.2985-DPS-01, "Functional Requirement Summary," | |||
andReportNo.2985-HHH-01, "Qualification Compliance," | |||
bothofwhichareprovidedinAttachment 5.Additionally, reliability studiesoftheinstrumentation, aswellastheverification andvalidation studiesandtheequipment qualification | |||
: programs, indicatethatthesusceptibility ofthereactorprotection systemto Attachment 1toAEP:NRC:1159C Page5commonmodefailuremechanisms willbereduced.(SeeAttachment 5,ReportNo.2985-HEI-15, "Reliability andMTBFAnalysis.") | |||
Afailureofthedigitalinstrumentation willnotcreateanewordifferent accident. | |||
Inthehighlyunlikelyeventthatthenewreactorprotection systeminstrumentation shouldfail,theconsequences experienced wouldbeequivalent tothoseexperienced iftheexistingequipment failed.(SeeAttachment 5,ReportNo.2985-HEI-14, "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200,"andReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment.") | |||
Consequently, thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated fortheCookNuclearPlant.3.Involveasinificantreduction inamarinofsafetTheproposedchangewillnot,reducethemarginofsafety,Theaccuracyandreliability ofthereactorprotection systemwillbeimprovedwiththeinstallation oftheFoxboroSPEC200andSPEC200MICROinstrumentation (seeAttachment 5,ReportNo.2985-HEI-15, "Reliability andMTBFAnalysis" | |||
).The~ariousreactortripandengineered safeguard actuation circuitscontinuetoprovidesignalstoautomatically openthereactortripbreakersoractuateengineered safeguards equipment, asapplicable, wheneveracondition monitored bythereactorprotection systemortheengineered safeguards featuresactuation systemreachesapresetorcalculated level.Inadditiontoredundant channelsandtrains,theprotection systemwillcontinuetomonitornumeroussystemvariables, therebyproviding protection systemfunctional diversity (seeAttachment 5,ReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment" | |||
).Inaddition, sinceitisassumedthatouroverallresponsetimesandsetpointandallowable valueswillcontinuetoremainbounding(SeeAttachment 5,ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations," | |||
andReportNo.2985-SKF-01, "Technical Specification Compliance Assessment" | |||
),theresultsandconclusions oftheaccidentanalysesremainvalid,assupported byReportNo.2985-VDV-01,"ReactorProtection Functional Diversity Assessment," | |||
contained inAttachment 5.Responsetimetestingperformed aspartofthefactoryacceptance testingwillverifythattheresponsetimesassumedintheaccidentanalysesarenotexceeded. | |||
Attachment 2toAEP:NRC:1159C ExistingLicensesforDonaldC.CookNuclearPlantUnits1and2MarkedtoReflectProposedChanges Unit1marked-up license DocketNo.315Page6of6*2.IIodineMonitorin Amendment No.49Thelicenseshallimplement aprogramwhichwillensurethecapability toaccurately determine theairborneconcentration invitalareasunderaccidentcondition's. | |||
Thisprogramshallincludethefollowing: | |||
1.Trainingofpersonnel, 2.Procedures formonitoring, and3.Provisions formaintenance ofsamplingandanalysisequipment. | |||
Amendment No.114Amendment No.1572.J3.Inallplacesofthislicense,thereference totheIndianaandMichiganElectricCompanyisamendedtoread"IndianaMichiganPowerCompany." | |||
gS.~se.~&QThisamendedlicenseiseffective asofthedateofissuanceandshallexpireatmidnightOctober25,2014.*Amendment No.70superseded thefollowing Amendments fornumbering: | |||
Nos.33,45and49'ORTHENUCLEARREGULATORY COMMISSION RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation | |||
==Enclosure:== | ==Enclosure:== | ||
AppendixA- | |||
Unit2marked- | AppendixA-Technical Specifications DateofIssuance: | ||
March30,1976 InsertA:Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system. | |||
Unit2marked-up license Docket:No.316Page9of11~g,L.('Zn.s~c4A$Amendment 3.No.141Thislicenseiseffective asofthedateofissuanceandshallexpireatmidnight, December23,2017.RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation Attachments: | |||
1.Preoperational Tests,Start-upTestsandOtherItemsWhichMuse-beCompleted PriortoProceeding toSucceeding Operational Modes.2.AppendixA-Technical Specifications DateofIssuance: | |||
December23,1977 InsertA:Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system. | |||
Attachment 3toAEP;NRC:1159C ProposedLicensesforDonaldCDCookNuclearPlantUnits1and2 DocketNo.315Page6of62.IIodineMonitorin Amendment No.49Thelicenseshallimplement aprogramwhichwillensurethecapability toaccurately determine theairborneconcentration invitalareasunderaccidentconditions. | |||
Thisprogramshallincludethefollowing: | |||
1.Trainingofpersonnel, 2~Procedures formonitoring, and3.Provisions formaintenance ofsamplingandanalysisequipment. | |||
Amendment No.1142.JInallplacesofthislicense,thereference reference totheIndianaandMichiganElectricCompanyisamendedtoreadIndianaMichiganPowerCompany." | |||
Amendment No.1572.K3.Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.Thisamendedlicenseiseffective asofthedateofissuanceandshallexpireatmidnightOctober25,2014.Amendment No.70superseded thefollowing Amendments fornumbering: | |||
Nos.33,45and49'ORTHENUCLEARREGULATORY COMMISSION RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation | |||
==Enclosure:== | ==Enclosure:== | ||
AppendixA-Technical Specifications DateofIssuance: | |||
March30,1976 DocketNo.316Page9ofll2.LThelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.Amendment 3.No.141Thislicenseiseffective asofthedateofissuanceandshallexpireatmidnight, December23,2017.RogerS,Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation Attachments: | |||
1.Preoperational Tests,Start-upTestsandOtherItemsWhichMustbeCompleted PriortoProceeding toSucceeding Operational Modes.2.AppendixA-Technical Specifications DateofIssuance: | |||
December23,1977 Attachment 4toAEP:NRC:1159C Organization oftheEngineering Data Attachment 5toAEP:NRC:1159C Requested SummaryReports.9212180049 Attachment 5toAEP:NRC;1159C Page1Thisattachment containsthesummaryreportsforeachofthetopicalareaslistedbelow.Thedetailedinformation supporting thesereportswillbemadeavailable totheNRCstaffduringtheirauditoftheinstrumentation upgrade,asdiscussed attheDecember1,1992meeting.SystemSummaryReportNo,2985-WGS-03 "SPEC200/SPEC200MICROHardwareandFirmwareSystemDescription" Environmental ReportNo~2985-HEI-12 "Engineering AnalysisofTemperature andHumidityEffectsonFoxboroSPEC200Instrumentation" SeismicReportNo,2985-HEI-07 "SeismicQualification Assessment ofFoxboroSPEC200Equipment" EMI/RFIReportNo.2985-HEI-03 "Preliminary EMI/RFIEvaluation" PowerSupply/Electrical ReportNo.2985-HEI-06 "SummaryReportforSystemPowerQualityEvaluation" ReportNo.2985-HEI-02 "Engineering AnalysisofGrounding Issues"Independence ReportNo.2985-NCF-01 "Regulatory Requirements andIndustryStandards Associated withtheReactorProtection andControlProcessInstrumentation Replacement Project" | |||
Attachment 5toAEP:NRC:1159C Page2FailureModesandEffectsReportNo.2985-HEI-14 "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200"Reliability ReportNo.2985-HEI-15 "Reliability andMTBFAnalysis" Functional Requirements ReportNo~2985-DPS-01 "Functional Requirement Summary"Performance Requirements ReportNo.2985-HEI-01 "SummaryReportforResponseTimeEvaluations" ReportNo.2985-SKF-01 "Technical Specification Compliance Assessment" Verification andValidation ReportNo.2985-HHH-01 "Qualification Compliance" TestingReportNo,2985-BJB-Ol "TestProgramSummary"Diversity ReportNo.2985-VDV-01 "ReactorProtection Functional Diversity Assessment"}} |
Revision as of 07:22, 29 June 2018
ML17334B451 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 12/16/1992 |
From: | FITZPATRICK E AMERICAN ELECTRIC POWER SERVICE CORP. |
To: | COOK D C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17329A705 | List: |
References | |
AEP:NRC:1159C, NUDOCS 9212180049 | |
Download: ML17334B451 (30) | |
Text
~ccax,z~rzo DOCmmxra<ST>UBUTION SYSTEM~REGULA1CINFORMATION DZSTRIBUTIOZSTEM
.(RIDE)ACCESSION NBR:9212180049 DOC.DATE:
92/12/16NOTARIZED:
YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
AmericanElectricPowerServiceCorp.RECIP.NAME RECIPIENT AFFILIATION COOK,D.C.
DocumentControlBranch(Document ControlDesk)DOCKET0500031505000316
SUBJECT:
Application foramendstolicensesDPR-58&DPR-74,consisting ofproposedTSpages.IDISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR gENCL!SIZE:P+'TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LADEANFWCOPIESLTTRENCL1122RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11INTERNAL:
NRR/DET/ESGB NRR/DST/SELB 7ENRR/DST/SRXB 8EOC/LFMBR8GF01EXTERNAL:
NRCPDR111111101111NRR/DOEA/OTSB11 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB NSIC111111101111RNOTETOALL"RIDSRECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK.ROOMPl-S7(EXT.504-2065)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR16ENCL14
AmericanElectricPowerServiceCorporati~
1Riverside Plaza~Columbus, OH432156142231000ÃAEP'NRC:1159C DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74REACTORPROTECTION SYSTEMMODIFICATION U,S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attention:
T.E,MurleyDecember16,1992
DearDr.Murley:
AnupgradetotheDonaldC.CookNuclearPlant'sreactorprotection systeminstrumentation isnecessary duetotheincreased maintenance requiredontheexistingFoxboroprotection systemandthedifficulty inobtaining qualified replacement parts.Theupgradeinvolvestheinstallation ofFoxboro's SPEC200andSPEC200MICROlinesofinstrumentation.
Webelievethatthismodification willenhanceoverallplantsafetyduetothereduceddrift,enhancedreliability, andgreaterflexibility providedbymicroprocessor-based hardware.
Thislineofinstrumentation hasbeenapprovedbytheNRCforuseinthereactorprotection systematHaddamNeckin1990,anditisusedinnuclearandnon-nuclear applications throughout theworld.OnApril21,1992ameetingwasheldamongpersonnel fromAmericanElectricPowerServiceCorporation (AEPSC),Foxboro,andyourstafftodiscusstheplans,schedules, andinterfaces tosupportanupgradetothereactorprotection systemforCookNuclearPlantUnits1and2.Atthatmeeting,weagreedtosubmitthemajorityoftheengineering information andalicensechangerequesttosupportthisupgradebyNovember30,1992'etailsofthismeetingwerereiterated inourletterAEP:NRC:1159B datedMay1,1992.OnDecember1,1992ameetingwasheldamongAEPSC,Foxboro,andtheNRCtodiscusstheformatoftheinformation tobesubmitted, Duringthismeeting,yourstaffadvisedusthatthemajorityoftheengineering information shouldbemadeavailable fortheiraudit,currently anticipated totakeplaceinJanuary1993atFoxboro's officesinFoxboro,Massachusetts.
9212180049 921216PDRADOCK05000315PPDR C'
Dr,T.E,Murley-2-AEP:NRC:1159C Inaddition, wewererequested tosubmitourrequestforalicenseamendment, aswellasvarioussummaryreports,byDecember15,1992.Assuch,thisletterservestotransmitalicenseamendment requestandtherequested summaryreports.Itshouldbestatedthat,whilemostofthedocumentation delineating andsupporting theengineering designandapplication ofthenewinstrumentation iscomplete, severalitemsstillremainopen.Asindicated inourMay1,1992submittal, thefactoryacceptance testreportisscheduled tobecompleted inApril1993.Inaddition, thefinalelectromagnetic interference/radio frequency interference (EMI/RFI) testreportwillnotbecompleted untilJanuary1993.Allofthesedocuments willbemadeavailable foryourstaff'sreviewupontheircompletion.
Attachment 1tothisletterprovidesourrequestforalicenseamendment andourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistinglicensepagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedlicensepages.Attachment 4providesanexplanation ofhowthedetailedengineering datathatAEPSCwillprovidethestaffduringtheirauditofthisprojectisorganized.
Specifically, Attachment 4containstheIssuesTrackingListandtheDocumentation TrackingList,aspresented attheDecember1,1992meeting.Attachment 5providessummaries ofthereportsthathavebeenwrittenonthemajortopicsassociated withthisinstrumentation upgrade.Theseincludereportsonthesubjectsofhardwareandfirmware, environmental effects,seismicqualification, EMI/RFI,powersupply/electrical, independence, failuremodesandeffects,reliability, functional requirements, performance requirements, verification andvalidation, testing,anddiversity.
Thesesummarystatements arebeingsubmitted inresponsetoyourstaff'srequestduringtheDecember1,1992meeting.Itisourunderstanding thatyourstaffwillbeabletosupportareviewschedulethatwillallowshipmentofequipment inMay1993.Wewillprovidewhateversupportisneededinordertomeetthisschedule.
Webelievethattheproposedinstrumentation upgradeandtheassociated licenseamendment willnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
Dr.T.E.Murley-3-AEP:NRC:1159C Incompliance withtherequirements of10CFR50.91(b)(1),copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.54(f)and,assuch,anoathstatement isenclosed.
Sincerely, pmE,E.Fitzpatrick VicePresident ragAttachments CC:D.H.Williams, Jr.A.A.Blind-BridgmanJ.R.PadgettG.CharnoffNFEMSectionChiefA.B.Davis-RegionIIINRCResidentInspector
-Bridgman Dr.T.E.Murley-4-AEP:NRC:11590 be:S.J.BrewerM.L.Horvath-BridgmanJ.B.Kingseed/V.
VanderBurg/R.
A.GreenD.H.Malin/K.J.TothJ.B.ShinnockW.G.Smith,Jr.W.M.Dean,NRC-Washington, D.C.AEP:NRC:1159C DC-N-6015.1 STATEOFOHIO)COUNTYOFFRANKLIN)
E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingReactorProtection SystemModification andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribdayofandsworntobeforemethis19NOTARYPcC(pAm~taD~
Attachment 1toAEP:NRC:1159C 10CFR50.92AnalysisforChangestoTheDonaldC.CookNuclearPlantOperating License
Attachment 1toAEP:NRC:1159C
1.0 ReuestforLicenseAmendment
Page1Thissubmittal constitutes arequestforanamendment totheCookNuclearPlantUnits1and2operating licenses.
Theseamendments willallowtheuseoftheproposeddigitalinstrumentation inthereactorprotection system,Inamemorandum datedJuly1,1991toAshokC.Thadani,Director-DivisionofSystemsTechnology, Mr.StevenA.Varga,Director-DivisionofReactorProjects-I/II, states:Afterreviewing 50.59,itshistory,andtheNRCendorsedguidance(NSAC125),itisouropinionthatthistypeoftechnology replacement
[useofdigitalinstrumentation inthereactorprotection system]cannotbeperformed under50.59.Asnotedinthismemo,weareawareoftheDCCookRPSreplacement projectandwedonotbelievethismodification shouldbeperformed underthe50.59rule.Subsequently, duringtheApril21,1992meeting,AEPSCwasadvisedthatthisinstrumentation changewouldrequirealicenseamendment.
Specifically, weareproposing toaddthefollowing condition asitemnumber2.KtotheUnit1licenseanditem2.LtotheUnit2license:Thelicenseeisauthorised tousedigitalsignalprocessing instrumentation inthereactorprotection system.2.0ScoeofReactorProtection SstemInstrumentation UradeTheproposeddesignchangewillinstallthefollowing equipment inthereactorprotection systemsofbothCookNuclearPlantunits.Thisequipment willperformthesamefunctions astheequipment itreplaces.
FoxboroSPEC200typeanaloginputsignalconditioning equipment, whichchangesthevarioustypesandvaluesofinputsignalsfromthesensorsintoacommontypeofanalogoutputsignalthatrepresents theinputvaluesatthechannellevel.
Attachment 1toAEP:NRC:1159C Page22.FoxboroSPEC200MICROdigitalsignalprocessing equipment, whichtakestheanalogsignalfromtheSPEC200analoginputequipment atthechannelleveland:a~Changestheanalogsignalstodigitalsignals.b.Processes thedigitalsignalsandcomparesthemagainstpredetermined limits,aswellasperformsdynamicfunctions andcalculations.
c.Changestheprocessed digitalsignalsbacktoanalogoutputsignals'.
FoxboroSPEC200analogoutputsignalconditioning equipment, whichtakestheanalogoutputsignalsfromtheSPEC200MICROandconditions themforuseinthecontrolsystem,aswellasforindication andrecording use.4.FoxboroSPEC200typecontactoutputequipment, whichproducesdiscretetripsignalsfromtheSPEC200MICROandprovidestripsignalsforinputtothereactorprotection logicequipment (SSPS).FoxboroSPEC200typepowerdistribution equipment, whichpowersthesignalconditioning andprocessing equipment discussed abo~e.6.75VDCmulti-loop and+15VDCmulti-nest powersupplies, whichprovidepowerforthefieldtransmitters andSPEC200equipment
~3.0Justification Thismodification isnecessary duetotheincreased maintenance requiredontheexistingFoxboroprotection systemandthedifficulty inobtaining qualified replacement parts.Inaddition, thechangesdescribed aboverepresent acompilation ofmodifications andenhancements tothereactorprotection systemthatwillimprovethesystem'sreliability andavailability.
Anearlyidentical systemwasapprovedforusebytheNRCattheHaddamNeckPlantin1990.Inaddition, digitalinstrumentation wasapprovedforuseinboththeSequoyahNuclearPlantandZionStationreactorprotection systems.
Attachment 1toAEP:NRC:1159C Page34.0NoSinificantHazardsConsideration Wehaveevaluated theproposedinstrumentation changesandhavedetermined thatthesechangeswillnotinvolveasignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).
Operation oftheCookNuclearPlantinaccordance withtheproposedchangeswillnot:Involveasinificantincreaseintherobabilit orconseuencesofanaccidentreviouslevaluated.
TheFoxboroSPEC200andSPEC200MICROlinesofinstrumentation aredesignedtomitigateanticipated operational occurrences anddesignbasisaccidents byactuating thereactortripandengineered safeguards signalscreditedintheCookNuclearPlantsafetyanalyses(seeAttachment 5,ReportNo.2985-WGS-03, "SPEC200/SPEC200MICROHardwareandFirmwareSystemDescription"
).Thisinstrumentation isdesignedtomonitorandprocesssignalsfortemperature,
- pressure, fluidflow,andfluidlevel(seeAttachment 5,ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations,"
andReportNo.2985-SKF-01, "Technical Specification Compliance Assessment"
).Whileitisaform,fitandfunctional replacement fortheexistingFoxbororeactorprotection systeminstrumentation, itsreliability andavailability isbetterthanthatofthepresentinstrumentation (seeAttachment 5,ReportNo.2985-HEI-15,"Reliability andMTBFAnalysis"
).Assuch,inthehighlyunlikelyeventthatthenewinstrumentation experiences afailure,theconsequences willnotexceedthosecausedbyafailureoftheexistingsystem.Thenewinstrumentation's failuremodesandeffectsarediscussed inAttachment 5inReportNo.2985-HEI-14, "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200."Sincetheabilityofthereactorprotection syst:emtodetectfaultsandinitiateprotective actionisnotreducedandsincetheFSARanalysesremainboundingasindicated above,theprobability orconsequences ofaccidents previously analyzedarenotincreased.
Createtheossibilit ofanewordifferent kindofaccidentfromanreviouslanalzed.TheFoxboroSPEC200andSPEC200MICROinstrumentation isdesignedtomitigateanticipated operational occurrences anddesignbasiseventsbyactuating reactortriporengineered safeguards signalscreditedinthesafetyanalyses.
Theinstrumentation isdesignedtomonitorandprocesssignals Attachment 1toAEP:NRC:1159C Page4fortemperature,
- pressure, fluidflow,andfluidlevels.Itisaform,fitandfunctional replacement fortheexistingFoxboroanaloginstrumentation.
Toensurethattheequipment willperformasrequired, extensive measureshavebeentakentoensurethattheresponseofthenewinstrumentation isenveloped bythedesignbasisaccidentanalysescontained inChapter14oftheCookNuclearPlantFSAR.Thisisdemonstrated, inpart,inreportsthataresummarized inAttachment 5including:
ReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment;"
ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations;"
andReportNo.2985-SKF-01,"Technical Specification Compliance Assessment."
Application oftheFoxboroinstrumentation intheCookNuclearPlantreactorprotection systemincludes, amongotherthings,suchconsiderations assinglefailure,independence, functional diversity, andseparation criteria.
Inaddition, theresponseoftheinstrumentation duringeventssuchasstationblackoutanddesignbasisearthquake wasassessed.
Thereportscontained inAttachment 5summarize theseefforts,Ananalysisoftheresponsetimesoftheinstrumentation indicates thattheywillbeboundedbytheexistingFSARanalysesandtheexistingCookNuclearPlanttechnical specification limits(seeAttachment 5,ReportNo.2985-HEI-01,"SummaryReportforResponseTimeEvaluations"
).Withregardtotheapplication ofdigitaltechnology intheCookNuclearPlantreactorprotection system,abatteryofEMI/RFIevaluations wasperformed, asdiscussed inReportNo.2985-HEI-03, "Preliminary EMI/RFIEvaluation."
Theseevaluations concluded thattheEMI/RFIenvironment atCookNuclearPlantissuitablefortheapplication ofthistypeofequipments TheSPEC200andSPEC200MICROhavebeendesigned,
- verified, andvalidated tobeincompliance withtheprotection systemfunctional requirements.
Thisstatement issupported byReportNo.2985-DPS-01, "Functional Requirement Summary,"
andReportNo.2985-HHH-01, "Qualification Compliance,"
bothofwhichareprovidedinAttachment 5.Additionally, reliability studiesoftheinstrumentation, aswellastheverification andvalidation studiesandtheequipment qualification
- programs, indicatethatthesusceptibility ofthereactorprotection systemto Attachment 1toAEP:NRC:1159C Page5commonmodefailuremechanisms willbereduced.(SeeAttachment 5,ReportNo.2985-HEI-15, "Reliability andMTBFAnalysis.")
Afailureofthedigitalinstrumentation willnotcreateanewordifferent accident.
Inthehighlyunlikelyeventthatthenewreactorprotection systeminstrumentation shouldfail,theconsequences experienced wouldbeequivalent tothoseexperienced iftheexistingequipment failed.(SeeAttachment 5,ReportNo.2985-HEI-14, "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200,"andReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment.")
Consequently, thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated fortheCookNuclearPlant.3.Involveasinificantreduction inamarinofsafetTheproposedchangewillnot,reducethemarginofsafety,Theaccuracyandreliability ofthereactorprotection systemwillbeimprovedwiththeinstallation oftheFoxboroSPEC200andSPEC200MICROinstrumentation (seeAttachment 5,ReportNo.2985-HEI-15, "Reliability andMTBFAnalysis"
).The~ariousreactortripandengineered safeguard actuation circuitscontinuetoprovidesignalstoautomatically openthereactortripbreakersoractuateengineered safeguards equipment, asapplicable, wheneveracondition monitored bythereactorprotection systemortheengineered safeguards featuresactuation systemreachesapresetorcalculated level.Inadditiontoredundant channelsandtrains,theprotection systemwillcontinuetomonitornumeroussystemvariables, therebyproviding protection systemfunctional diversity (seeAttachment 5,ReportNo.2985-VDV-01, "ReactorProtection Functional Diversity Assessment"
).Inaddition, sinceitisassumedthatouroverallresponsetimesandsetpointandallowable valueswillcontinuetoremainbounding(SeeAttachment 5,ReportNo.2985-HEI-01, "SummaryReportforResponseTimeEvaluations,"
andReportNo.2985-SKF-01, "Technical Specification Compliance Assessment"
),theresultsandconclusions oftheaccidentanalysesremainvalid,assupported byReportNo.2985-VDV-01,"ReactorProtection Functional Diversity Assessment,"
contained inAttachment 5.Responsetimetestingperformed aspartofthefactoryacceptance testingwillverifythattheresponsetimesassumedintheaccidentanalysesarenotexceeded.
Attachment 2toAEP:NRC:1159C ExistingLicensesforDonaldC.CookNuclearPlantUnits1and2MarkedtoReflectProposedChanges Unit1marked-up license DocketNo.315Page6of6*2.IIodineMonitorin Amendment No.49Thelicenseshallimplement aprogramwhichwillensurethecapability toaccurately determine theairborneconcentration invitalareasunderaccidentcondition's.
Thisprogramshallincludethefollowing:
1.Trainingofpersonnel, 2.Procedures formonitoring, and3.Provisions formaintenance ofsamplingandanalysisequipment.
Amendment No.114Amendment No.1572.J3.Inallplacesofthislicense,thereference totheIndianaandMichiganElectricCompanyisamendedtoread"IndianaMichiganPowerCompany."
gS.~se.~&QThisamendedlicenseiseffective asofthedateofissuanceandshallexpireatmidnightOctober25,2014.*Amendment No.70superseded thefollowing Amendments fornumbering:
Nos.33,45and49'ORTHENUCLEARREGULATORY COMMISSION RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation
Enclosure:
AppendixA-Technical Specifications DateofIssuance:
March30,1976 InsertA:Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.
Unit2marked-up license Docket:No.316Page9of11~g,L.('Zn.s~c4A$Amendment 3.No.141Thislicenseiseffective asofthedateofissuanceandshallexpireatmidnight, December23,2017.RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation Attachments:
1.Preoperational Tests,Start-upTestsandOtherItemsWhichMuse-beCompleted PriortoProceeding toSucceeding Operational Modes.2.AppendixA-Technical Specifications DateofIssuance:
December23,1977 InsertA:Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.
Attachment 3toAEP;NRC:1159C ProposedLicensesforDonaldCDCookNuclearPlantUnits1and2 DocketNo.315Page6of62.IIodineMonitorin Amendment No.49Thelicenseshallimplement aprogramwhichwillensurethecapability toaccurately determine theairborneconcentration invitalareasunderaccidentconditions.
Thisprogramshallincludethefollowing:
1.Trainingofpersonnel, 2~Procedures formonitoring, and3.Provisions formaintenance ofsamplingandanalysisequipment.
Amendment No.1142.JInallplacesofthislicense,thereference reference totheIndianaandMichiganElectricCompanyisamendedtoreadIndianaMichiganPowerCompany."
Amendment No.1572.K3.Thelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.Thisamendedlicenseiseffective asofthedateofissuanceandshallexpireatmidnightOctober25,2014.Amendment No.70superseded thefollowing Amendments fornumbering:
Nos.33,45and49'ORTHENUCLEARREGULATORY COMMISSION RogerS.Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation
Enclosure:
AppendixA-Technical Specifications DateofIssuance:
March30,1976 DocketNo.316Page9ofll2.LThelicenseeisauthorized tousedigitalsignalprocessing instrumentation inthereactorprotection system.Amendment 3.No.141Thislicenseiseffective asofthedateofissuanceandshallexpireatmidnight, December23,2017.RogerS,Boyd,DirectorDivisionofProjectManagement OfficeofNuclearReactorRegulation Attachments:
1.Preoperational Tests,Start-upTestsandOtherItemsWhichMustbeCompleted PriortoProceeding toSucceeding Operational Modes.2.AppendixA-Technical Specifications DateofIssuance:
December23,1977 Attachment 4toAEP:NRC:1159C Organization oftheEngineering Data Attachment 5toAEP:NRC:1159C Requested SummaryReports.9212180049 Attachment 5toAEP:NRC;1159C Page1Thisattachment containsthesummaryreportsforeachofthetopicalareaslistedbelow.Thedetailedinformation supporting thesereportswillbemadeavailable totheNRCstaffduringtheirauditoftheinstrumentation upgrade,asdiscussed attheDecember1,1992meeting.SystemSummaryReportNo,2985-WGS-03 "SPEC200/SPEC200MICROHardwareandFirmwareSystemDescription" Environmental ReportNo~2985-HEI-12 "Engineering AnalysisofTemperature andHumidityEffectsonFoxboroSPEC200Instrumentation" SeismicReportNo,2985-HEI-07 "SeismicQualification Assessment ofFoxboroSPEC200Equipment" EMI/RFIReportNo.2985-HEI-03 "Preliminary EMI/RFIEvaluation" PowerSupply/Electrical ReportNo.2985-HEI-06 "SummaryReportforSystemPowerQualityEvaluation" ReportNo.2985-HEI-02 "Engineering AnalysisofGrounding Issues"Independence ReportNo.2985-NCF-01 "Regulatory Requirements andIndustryStandards Associated withtheReactorProtection andControlProcessInstrumentation Replacement Project"
Attachment 5toAEP:NRC:1159C Page2FailureModesandEffectsReportNo.2985-HEI-14 "FailureModesandEffectsAnalysisProtection Set1FoxboroSPEC200"Reliability ReportNo.2985-HEI-15 "Reliability andMTBFAnalysis" Functional Requirements ReportNo~2985-DPS-01 "Functional Requirement Summary"Performance Requirements ReportNo.2985-HEI-01 "SummaryReportforResponseTimeEvaluations" ReportNo.2985-SKF-01 "Technical Specification Compliance Assessment" Verification andValidation ReportNo.2985-HHH-01 "Qualification Compliance" TestingReportNo,2985-BJB-Ol "TestProgramSummary"Diversity ReportNo.2985-VDV-01 "ReactorProtection Functional Diversity Assessment"