ML17334B451

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Application for Amends to Licenses DPR-58 & DPR-74, Consisting of Proposed TS Pages Re Reactor Protection Sys Instrumentation
ML17334B451
Person / Time
Site: Cook  American Electric Power icon.png
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)
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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"

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