ML18026A449

Forwards Request That NRC Take Actions Re 10CFR2.206 to Protect Public from Undue Risk from Spent Fuel Storage

ML18026A449
Person / Time
Site:	Susquehanna
Issue date:	11/28/1994
From:	LOCHBAUM D A, PREVATTE D C AFFILIATION NOT ASSIGNED
To:	TAYLOR J M NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
References
2.206, NUDOCS 9412190197
Download: ML18026A449 (61)

Text

CpitgCeDavidA.Lochbaum80TuttleRoadWatchung, NJ07060(908)754-3577November28,1994DonaldC.Prevatte7924Woodsbluff RunFogelsville, PA18051(215)398-9277Mr.JamesTaylorExecutive DirectorforOperations UnitedStatesNuclearRegulatory Commission Washington, DC205554001

SUBJECT:

10CFR2.206RequestforNRCAction

DearMr.Taylor:

.InalenerdatedOctober13,1994,Mr.GaryM,Holohan,Director-DivisionofSystemsSafetyandAnalysis, transmitted theTaskActionPlanforSpentFuelStoragePoolSafetytoMr.AshokC.Thadani,Associate DirectorforTechnical Assessment.

ThisactionplanoutlinedtheNRCplanstoevaluatethegenericimplications ofthenuclearsafetyconcernsweidentified intheSusquehanna SteamElectricStationandsubmitted totheNRCina10CFR21reportdatedNovember27,1992.Thedraftofthisactionplanwasdescribed inapublicmeetingonSeptember 6,1994.Theapprovedactionplanwastransmitted byaletterdatedOctober24,1994,anddiscussed inapublicmeetingonOctober25,1994.Theactionplaninvolvesteaminspections atselectedsites,industryexperience reportreviews,andriskassessments todevelopacourseofactionforpotential genericactions.Theactionplanindicates thatthiscourseofactionisscheduled tobedeveloped byNovember1995andthecourseofactionimplemented byDecember1996.Pursuanttotheprovisions ofSection2.206ofTitle10oftheCodeofFederalRegulations, werespectfully requestthattheNRCtaketheactionsspecified ontheenclosure toprotectthepublicfromundueriskfromspentfuelstorage.Theseactionsareonlyintendedtopreventanylicenseefromincreasing theprobability ofand/orconsequences fromthespentfuelpoolcoolingproblemswhilethestaffisevaluating thegenericimplications ofthe10CFR21issues.Theserequested actionsonlyapplytotheinterimperiodwhilethestaffdefinesacourseofactionandterminate uponimplementation ofthecourseofaction.Inaccordance withPartIIofNRCDirective 8.11,ReviewProcessfor10CFR2.206Petitions",

wehavecarefully structured theserequested actionssoasnotto"...avoid orcircumvent..."

thestaff'sstatedactionplan.Pleasenotethattherequested actionsweresubmitted togetherforconvenience, andtherequested actionsshouldbeacceptedordeniedbasedontheirindividual merits.Pleasefeelfreetocontactusforadditional information orclarification regarding thisrequestforaction.Wearenotrequesting aninformalpublichearingforthispetitionsincethestaffshouldhavesufficient understanding oftheunderlying concerns.

Sincerely, Enclosure DavidA.hbaumCtuu/r.g,.DonaldC.vatteVihvgagggpgEnclosure 3

CC:Mr.NoelDudleyAdvisoryCommittee onReactorSafeguards UnitedStatesNuclearRegulatory Commission Washington, DC20555Mr.SamHollandOfficeoftheInspector GeneralUnitedStatesNuclearRegulatory Commission Washington, DC20555Dr.JohnT.LarkinsExecutive

Director, AdvisoryCommittee onReactorSafeguards UnitedStatesNuclearRegulatoty Commission Washington, DC20555Mr.RichardA.MatakasUnitedStatesNuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406-1415 Mr.WilliamRussellDirector, OfficeofNuclearReactorRegulation UnitedStatesNuclearRegulatory Commission Washington, DC205554001 Mr.IvanSelinChairmanUnitedStatesNuclearRegulatory Commission Washington, DC205554001 Mr.JosephW.Shea,ProjectManagerOfficeofNuclearReactorRegulation UnitedStatesNuclearRegulatory Commission Washington, DC205554001 Mr.DavidC.WilliamsInspector GeneralUnitedStatesNuclearRegulatory Commission Washington, DC20555 TheHonorable JosephI.Lieberman

Chairman, SenateEnvironment andPublicWorksCommittee, Subcommittee ofCleanAirandNuclearRegulation SD458Washington, DC20510TheHonorable RichardH.LehmanChairman, HouseNaturalResources Committee, Subcommittee onEnergyandMineralResources 818O'eillBuilding300NewJerseyAvenue,S.E.Washington, DC20515TheHonorable PhilipR.SharpChairman, HouseEnergyandCommerceCommittee, Subcommittee onEnergyandPower331FordBuilding2"andDStreets,S.W.Washington, DC20515Ms.LeslieGreerMassachusetts Assistant AttorneyGeneral1Ashburton PlaceBoston,MA02108Mr.PaulGunterNuclearInformation andResourceService142416~StreetNWWashington, DC20036Dr.JudithJohnsrud433OrlandoAvenueStateCollege,PA16803Mr.RobertD.PollardUnionofConcerned Scientists 1616PStreetNWWashington, DC20036Ms.JoanneRoyceGovernment Accountability Project810PStreetNE,Suite630Washington, DC20002-3633

'I IasNovember28,1994Enclosure Page1of3ActionsRequested underSection2.206ofTMe10oftheCodeofFederalRegulations 1)Requested ActionWithRespecttoIssuanceofOperathgLicensesofFederalRegulations toanyapplicant (e.g.Tennessee ValleyAuthority forthe%'attsBarNuclearPlant)untilthecourseofactiondeveloped bytheTaskActionPlanforSpentFuelStoragePoolSafetydatedOctober13,1994isimplemented unlessthatapplicant evaluates thespentfuelpoolcoolingsafetyconcernsidentified inthe10CFR21reportdatedNovember27,1992andaddressed inthestaffsSafetyEvaluation (scheduled tobeissuedinDecember1994)andtheapplicant's evaluation isformallyreviewedandacceptedbythestaffaspartofthelicensing process.Theapplicant's evaluation shallexplicitly addresshowtherequirements ofSection100ofTitle10oftheCodeofFederalRegulations aresatisfied forspentfuelhandlingandstorageduringnormaloperation andQaldesignbasisevents.Justification Thestaffissuedanoperating ticenmfortheSusquehanna SteamElectricStationwhhoutrequiring,its licenseetobeinfullcompliance withetdstingregulations suchasIOCFRSO,AppendixA,GeneralDesignCriterion 61becausedesignbasiseventscenarios identified hthe10CFR21reportdatedNovember27,1992hadnotbeenconsidered atthetimeofinitiallicensing.

Previousstaffevaluations coveringthehandlingandstorageofspentfuel,including NUREG4404 andNUREG-1353, determined thatcompliance withexistingregulations providedreasonable assurance thatpublichealthandsafetywouldbeprotected.

Thisrequested actionisintendedtoprovidereasonable assurance thatanotheroperating licenseisnotgrantedwithouttheapplicant demonstrating fullcompliance withallapplicable regulations onspentfuelstorage.Thisrequested actionisterminated bythestaffsimplementation ofthecourseofactionresulting fromitsdetermination ofgenericimplications associated withspentfuelstoragesinceappropriate measures(i.e.ruiemaking orgenericbulletins) willbeinplacetoprovidereasonable assurance, 2)Requested ActionWithRespecttoAmendments ofOperating Licenses50.92ofTitle10oftheCodeofFederalRegulations toanylicenseeinanyoftheareaslistedbelowuntilthecourseofactiondeveloped bytheTaskActionPlanforSpentFuelStoragePoolSafetydatedOctober13,1994isimplemented unlessthatlicenseeevaluates thespentfuelpoolcoolingsafetyconcernsidentifiied inthe10CFR21reportdatedNovember27,1992andaddressed inthestaffsSafetyEvaluation (scheduled tobeissuedinDecember1994)andthelicensee's evaluation isformallyreviewedandacceptedbythestaffaspartoftheamendment process.Thelicensee's evaluation shallexplicitly addresshowtherequirements ofSection100ofTitle10oftheCodeofFederalReguhrions aresatisfied forspentfuelhandlingandstorageduringnormaloperation and+aldesignbasisevents.Operating licenseamendments whichinvolveoneormoreofthefollowing subjectsarecoveredbythisrequested action:2.1increased capacityofspentfuelstoragepool2.2increased licensedreactorpowerlevel ActionsRequested underSection2.206ofTitle10oftheCodeofFedemlRegulations November28,1994Enclosure Page2of3Justification Thestaffissuedanoperating liceasefortheSusquehanna SteamElectricStationwithoutrequiring itslicenseetobeinfullcompliance withexistingregulations suchas10CFR50,AppendixA,GeneralDesignCriterion 61becausedesignbasiseventscenarios identified inthe10CFR21reportdatedNovember27,1992hadnotbeenconsidered atthetimeofinitiallicensing.

Thestaffmayhaveissuedoperating licensesforotherfacilities whichalsofailedtocomplywithallapplicable regulations onspentfuelstorage.Previousstaffevaluations coveringthehandlingandstorageofspentfuel,including NUREG4404 andNUREG-1353, determined thatcompliance withexistingregulations providedreasonable assurance thatpublichealthandsafetywouldbeprotected.

Thisrequested actiontheeisintendedtoprovidereasonable assurance thatanoperating licenseamendment foranyactihy'thofanyvlhywlepotential forincreasing spentfuelstorageriskisnotgrantedwithoutthelicenseedemonstratin fullcompliance withallapplicable regulations onspentfuelstorage.Increasing thecapacityofthespentnsgfuelpoolorthereactorthermalpowerlevelhasthepotential forincreasing thedecayheatgeneration rateandsourceterminventory inthespentfuelpoolwhichareprimaryfactorsinspentfuelstoragerisk.Thisrequested actionisterminated bythestaff'simplementation ofthecourseofactionresulting fromitsdetermination ofgenericimplications associated withspentfuelstoragesinceappropriate measures(i.e.rulemaking orgenericbulletins) wBIbeinplace.toprovidereasonable assurance.

3)Requested ActionWithRespecttoRenewalsofOperating LicensesTitle10oftheCodeofFederalRegulations toanylicenseeuntilthecourseofactiondeveloped bytheTaskActionPlanforSpentFuelStoragePoolSafetydatedOctober13,1994isimplemented unlessthatlicenseeevaluates thespentfuelpoolcoolingsafetyconcernsidentified inthe10CFR21reportdatedNovember27,1992andaddressed inthestaffsSafetyEvaluation (scheduled tobeissuedinDecember1994)andthelicensee's evaluation isformallyreviewedandacceptedbythestaffaspartofthelicenserenewal/extension process.Thelicensee's evaluation shallexplicitly addresshowtherequirements ofSection100ofTitle10oftheCodeofFederalRegulations aresatisfied forspentfuelhandlingandstorageduringnormaloperation and+aldesignbasisevents.Jcstlgcstion Thestaffissuedanoperatiog licensefortheSusquehanna SteamElectricStadonwithoutrequiring itslicenseetobeinfullcompliance withexistingregulations suchas10CFR50,AppendixdA,GeneralDesignCriterion 61becausedesignbasiseventscenarios identified inthe10CFR21atedNovember27,1992hadnotbeenconsidered atthetimeofinitiallicensing.

Thestaffmayhaveissuoperating licensesforotherfacilities whichalsofailedtocomplywithallapplicable regulations onspentfuelstorage.Previousstaffevaluations coveringthehandlingandstorageofspentfuel,including NUREG4404 andNUREG-1353, determined thatcompliance withexistingregulations providedreasonable assurance thatpublichealthandsafetywouldbeprotected, Thisrequested actionisintendedtoprovidereasonable assurance thatanoperating licenserenewal/extension isnotgrantedwithoutthelicenseedemonstrating fullcompliance withallapplicable regulations onspentfuelstorage.icenserenewal/extension hasthepotential forincreasing thedecayheatgeneration rateandsourceterminventoty inthespentfuelpoolwhichareprimaryfactorsinspentfuelstoragerisk.Thisrequested actionisterminated bythestaffliimplementation ofthecourseofactionresulting fromitsdetermination ofgenericimplications associated withspentfuelstoragesinceappropriate measures(i.e.rulemaking orgenericbulletins) willbeinplacetoprovidereasonable assurance.

November28,1994Enclosure Page3of3ActionsRequested underSection2.206ofTitle10oftheCodeofFederalRegulations 4)Requested ActionWithRespecttoIndependent SpentPeelStorageLicensesissuedunderPart72ofTitle10oftheCodeofFederalRegulations toanylicenseeuntilthecourseofactiondeveloped bytheTaskActionPlanforSpentFuelStoragePoolSafetydatedOctober13,1994isimplemented unlessthatlicensee(orapplicant) evaluates thespentfuelpoolcoolingsafetyconcernsidentified inthe10CFR21reportdatedNovember27,1992andaddressed inthestaffsSafetyEvaluation (scheduled tobeissuedinDecember1994)andthelicensee's (orapplicant's) evaluation isformallyreviewedandacceptedbythestaffaspartofthelicensing process.Thelicensee's (orapplicant's) evaluation shallexplicitly addresshowtherequirements ofSection100ofTitle10ofthe~CodeofFederalRegulations aresatisfied forspentfuelhandlingandstorageduringnormaloperation andalldesignbasisevents.Justification

'ihestaffissuedanoperating licensefortheSusquehanna SteamElectricStationwithoutrequiring itslicenseetobeinfullcompliance withexistingregulations suchas10CFR50,AppendixA,GeneralDesignCriterion 61becausedesignbasiseventscenarios identified inthe10CFR21reportdatedNovember27,1992hadnotbeenconsidered atthetimeofinitiallicensing.

Thestaffmayhaveissuedoperating licensesforotherfacilities whichalsofailedtocomplywithallapplicable regulations onspentfuelstorage,Previousstaffevaluations coveringthehandlingandstorageofspentfuel,including NUREG4404 andNUREG-1353, determined thatcompliance withexistingregulations providedreasonable assurance thatpublichealthandsafetywouldbeprotected.

Thisrequested actionisintendedtoprovidereasonable assurance thatalicenseforindependent spentfuelstorageisnotgrantedwithoutthelicenseedemonstrating fullcompliance withallapplicable regulations onspentfuelstorage.Independent spentfuelstorageactivities involvethemovementofheavyloadsinandaroundtherefueling floorarea.OneoftheelementsoftheTaskActionPlanistore-assess therisksassociated withheavyloadsonlossofspentfuelpoolcoolingevents.NUREG4612 allowedlicensees toresolvetheheavyloadissuethroughrelianceondesignated pathwayswhichavoidedtransporting heavyloadsoversafetyrelatedequipment.

Inmanynuclearpowerplants,thespentfuelpoolcoolingsystemsarenon-safety relatedsystemsandthusmaynotbeprotected fromthepostulated dropofaheavyload.Thisrequested actionisterminated bythestaffsimplementation ofthecourseofactionresulting fromitsdetermination ofgenericimplications associated withspentfuelstoragesinceappropriate measures(i.e.rulemaking orgenericbulletins) willbeinplacetoprovidereasonable assulailce.

5'~-.2~7'

-Mr.UlrichMuellerMs.UeliMuellerGreenpeace PostfachCH-8031Zurich,Switzerland

+/U/60536'/I

/galMarch15,2000+~f1NP=O<d

DearMr.andMs.Mueller:

Iamresponding toyourelectronic mailofJanuary17,2000,totheU.S.NuclearRegulatory Commission's (NRC)OfficeofPublicAffairsrequesting information ontheDecember17,1999,shutdownoftheSusquehanna SteamElectricStation,Unit2.YoureferredtoaDecember23,1999,Nucleonics Weekarticlethatindicated thattheNRCwouldevaluatetheshutdowntodetermine ifagenericissueexists.Yourequested information regarding theshutdown, whetherotherfacilites haveexperienced similarproblems, andwhethertheNRChasinitiated genericactionrelatedtotheseissues.Responses toyourquestions areprovidedintheenclosure tothisletter.Itrustthatyouwillfindtheenclosedinformation responsive toyourquestions.

Shouldyouhaveanyquestions orcommentsregarding thesematters,pleasecontactMr.RobertSchaaf,theNRCProjectManagerfortheSusquehanna SteamElectricStation,at1-301-415-1312, orviaelectronic mailatrgsnrc.gov.

Sincerely,

/RA/ElinorG.Adensam,DirectorProjectDirectorate 1DivisionofLicensing ProjectManagement OfficeofNuclearReactorRegulation

Enclosure:

Responses toQuestions ccw/encl:Mr.Sabyasachi Chakraborty HeadofSafetyResearchandInternational ProgramsSwissFederalNuclearSafetyInspectorate PostfachCH-5232Villigen-HSK, Switzerland DISTRIBUTION FileCenter(50-388)w/original incomingPUBLIC(w/incoming)

(PDI-1Reading(w/incoming)

'.Collins/R.

Zimmerman B.Sheron/J.

JohnsonE.AdensamM.Gamberoni R.Schaaf(w/incoming)

R.Norsworthy, DLPMM.O'rienNRRMailRoom(YT¹020000010)

(05/E/7)M.King,,',C.Cowgill,RlM.CullingfordaaDOCUMENTNAME:G:>PDI-1)Sus 1&23t20-010A.w d*seereviousconcurrence OFFICEPM:PDI-1LA:PjTA:NRR.AS.I-1PD:DNAMEDATERSchaafMO'Bren'3/5/00,//00MCullinford*3/9/00MGeroniEAdenam/1/004//00OFFICIALRECORDCOPYP)<ayQ 0IllII'IIII,ItIIl)n1III

~y**4y~lfUNITEDSTATESNUCLEARREGULATORY COMMISSION WASHINGTON, D.C.20555-0001 P@~0~sgrrrrsMarch15,2000Mr.UlrichMuellerMs.UeliMuellerGreenpeace PostfachCH-8031Zurich,Switzerland

DearMr.andMs.Mueller:

'Iamresponding toyourelectronic mailofJanuary17,2000,totheU.S.NuclearRegulatory Commission's (NRC)OfficeofPublicAffairsrequesting information ontheDecember17,1999,shutdownoftheSusquehanna SteamElectricStation,Unit2.YoureferredtoaDecember23,1999,Nucleonics Weekarticlethatindicated thattheNRCwouldevaluatetheshutdowntodetermine ifagenericissueexists.Yourequested information regarding theshutdown, whetherotherfacilites haveexperienced similarproblems, andwhethertheNRChasinitiated genericactionrelatedtotheseissues.Responses toyourquestions areprovidedintheenclosure tothisletter.Itrustthatyouwillfindtheenclosedinformation responsive toyourquestions.

Shouldyouhaveanyquestions orcommentsregarding thesematters,pleasecontactMr.RobertSchaaf,theNRCProjectManagerfortheSusquehanna SteamElectricStation,at1-301-415-1312, orviaelectronic mailatrgsnrc.gov.

Sincerely, ElinorG.Adensam,DirectorProjectDirectorate 1DivisionofLicensing ProjectManagement OfficeofNuclearReactorRegulation

Enclosure:

Responses toQuestions ccw/encl:Mr.Sabyasachi Chakraborty HeadofSafetyResearchandInternational ProgramsSwissFederalNuclearSafetyInspectorate PostfachCH-5232Villigen-HSK, Switzerland ResonsetoQuestions ReaidintheDecember171999ShutdownoftheSusuehannaSteamElectricStationUnit2Question1Whatkindofmaterialwasaffected?

~ResonseTheSusquehanna SteamElectricStationFinalSafetyAnalysisReportidentifies theinstrumentation linematerialasaustenitic stainless steel.Question2HastheNRCreleasedapublication addressing thisspecificevent?~ResonseNRCInspection ReportNo.05000387/1 999012,05000388/1999012, issuedonJanuary24,2000,providesasummaryoftheUnit2shutdownandthelicensee's actionstoidentifyandcorrectthesourceoftheleak.Acopyoftheinspection reportisattachedtothisresponse.

Thesummaryoftheshutdownandlicenseeactionsisonpage2ofthereport.Question3WhatfindingscausedtheNRCtoexaminetheeventforpotential genericimplications?

~ResonseItisthepolicyoftheNRCtosystematically reviewoperating datafromarangeofsourcestoidentifypotential genericissues.Operational dataisscreenedeachbusinessdaytoevaluatetheneedforadditional review.Sourcesofoperational dataincludelicenseeeventnotifications submitted inaccordance with10CFR50.72,dailyreportsfromNRCregionaloffices,anddailyplantoperating statusreportsobtainedthroughtheNRC'sHeadquarters Operations Center.Theinitialreviewincludesconsideration ofthelossofmarginassociated withregulatory requirements andthepotential risksignificance oftheevent.Riskinsightsandstaffengineering judgement areusedtoselectissuesthatwarrantfollow-up effort.TheSusquehanna shutdownwasnotselectedforfurtherreview.Question4Isthedetailedcauseoftheproblemknownandisitrelatedtopowerupratingofboilingwagnerreactors(BWRs)?ENCIOSURE

~ResonseAsnotedinourinspection report,thelicenseedetermined thecauseoftheleaktobeacrackinaninstrumentation lineweldcausedbyhigh-cycle fatigueduetovibration.

Nolinkhasbeenidentified betweentheinstrumentation lineleakandtheSusquehanna poweruprate.Question5HaveotherU.S.BWRsexperienced similarproblems?

Ifso,hasNRCtakenanyactiontoobligefacilities toaddresstheproblem?~ResenseAreviewofhistorical data,including licenseereportsfiledinaccordance w'ith10CFR50.72and50.73andNRCpreliminary notifications ofunusualevents,identified anumberofinstances whereplantsexperienced minorleaksattributed tomechanical orflow-induced vibration.

Thesefailurestypically occurredinsmallpipingandusuallyresultedinminorleaksoflessthan1gallonperminute.Severalinstances ofvibration attributed tohighrecirculation floworrecirculation systemharmonicresonances haveoccurredatU.S.BWRfacilities.

Theaffectedlicensees typically instituted administrative controlstolimitrecirculation flow,ortomonitorvibration andreducerecirculation flowifexcessive vibration isdetected.

TheNRCissuedInformation Notice95-16,"Vibration CausedbyIncreased Recirculation FlowinaBoilingWaterReactor,"

onMarch9,1995,tonotifytheindustryoftheseoccurrences.

Information noticesareaformofgenericcommunication usedbytheNRCtoinformthenuclearindustryofsignificant operating experience.

Information noticesdonotconveyorimplynewrequirements anddonotrequestinformation oractions.Nogenericactionhasbeentakentorequirelicensees toaddresstheseoccurrences becausetheexistingregulatory structure affecting thedesignandoperation ofnuclear,powerplants.effectively directslicenseeactions.TheNRCrecognizes thatcompletereliancecannotbeplacedonanysingleelementofthedesign,maintenance, oroperation ofanuclearpowerplanttoassuresafeoperation.

Therefore, thedefense-in-depth philosophy isappliedinlicensing nuclearpowerplants.Inthedefense-in-depth philosophy, protection isprovidedbyseverallayersofdefenseinvolving accidentprevention, accidentmitigation, radiation protection, andemergency preparedness.

Designfeaturesaddressing eachoftheseareasforeachoperating reactorhavebeenreviewedandapprovedbythestaff.Controlsto'support accidentprevention includedesigncontrolstopreventpipingdegradation duetooperational

stresses, procedures todetectpipingdegradation priortodevelopment ofleaks,systemsandprocedures toenablepromptidentification ofminorleaks,andprocedures toensurethatprompt,effective corrective actionisimplemented tocorrectandpreventrecurrence ofidentified deficiencies.

Question6Havesimilarproblemscausedbyincreased materialstressduetopowerupratingoccurredpreviously inU.S.BWRs?

~ResenseNoneoftheidentified examplesofvibration inducedleaksnotedwereattributed topower.uprating.TheNRCwillcontinuetoroutinely evaluateoperating reactoreventsforgenericsignificance inaccordance withourpolicy.Theseevaluations includeconsideration ofthedefense-in-depth philosophy discussed above.

Attachment:

Inspection Report January24,2000Mr.RobertG.ByramSeniorVicePresident, NuclearPP&L,Inc.2NorthNinthStreetAllentown, PA18101

SUBJECT:

NRCINTEGRATED INSPECTION REPORT05000387/1999012 and05000388/1 999012

DearMr.ByramOnJanuary1,

'000,theNRCcompleted aninspection attheSusquehanna SteamElectricStation(SSES)Unit1&2reactorfacilities.

Theenclosedreportcoveredroutineactivities bytheresidentinspectors andannounced inspections ofyourSecurityandSafeguards, andRadiological Controls-External andInternalExposureprogramsbyR'egionIspecialists.

Theinspectors discussed thefindingsoftheseinspections withMr.R.Saunders, VicePresident NuclearOperations, Mr.B.Shriver,GeneralManagerSSES,andothermembersofyourstaff,atanexitmeetingatthecompletion oftheinspections.

Overall,yourstaffsafelyoperatedthefacilityduringthisperiod.PlantManagement's decisions toperformacontrolled shutdownofUnit2toaddresstheincreaseinprimarycontainment unidentified waterleakageandtocorrectadditional knownequipment problemspriortorestartwasapositiveinitiative.

Inaccordance with10CFR2.790oftheNRC's"RulesofPractice,"

acopyofthisletter,itsenclosure(s),

andyourresponsewillbeplacedintheNRCPublicDocumentRoom(PDR).Areplytothisletterisnotrequired, butshouldyouhaveanyquestions regarding thispleasecontactmeat610-337-5322.

Sincerely, ORIGINALSIGNEDBYCurtisJ.Cowgill,ChiefProjectsBranch4DivisionofReactorProjectsDocketNos:05000387, 05000388LicenseNos:NPF-14,NPF-22

Enclosure:

Inspection Report05000387/1 999012,05000388/1 999012ATTACHMENT

Mr.RobertG.Byramccw/encl:R.F.Saunders, VicePresident

-NuclearSiteOperations G.T.Jones,VicePresident

-NuclearEngineering andSupportB.L.Shriver,GeneralManager-SSESR.M.Peal,Manager,NuclearTrainingG.D.Miller,GeneralManager-NuclearAssurance R.R.Wehry,NuclearLicensing

-SSESM.M.Golden,Manager-NuclearSecurityP.Nederostek, NuclearServicesManager,GeneralElectricW.H.Lowthert, Manager,NuclearPlantServicesA.M.Male,Manager,QualityAssurance H.D.Woodeshick, SpecialAssistant tothePresident G.DallaPalu, PP&LNuclearRecordsR.W.Osborne,VicePresident, Supply&Engineering Allegheny ElectricCooperative, Inc.Commonwealth ofPennsylvania

U.S.NUCLEARREGULATORY COMMISSION REGIONIDocketNos:LicenseNos:05000387, 05000388NPF-14,NPF-22ReportNo.05000387/1999012, 05000388/1999012 Licensee:

PP&L,Inc.2NorthNinthStreetAllentown, PA19101Facility:

Susquehanna SteamElectricStationLocation:

P.O.Box35Berwick,PA18603-0035 Dates:November20,1999throughJanuary1,2000Inspectors:

S.Hansell,SeniorResidentInspector J.Richmond, ResidentInspector A.Blarney,ResidentInspector P.Frechette, SecuritySpecialist J.McFadden, Radiation Specialist Approvedby:CurtisJ.Cowgill,ChiefProjectsBranch4DivisionofReactorProjects EXECUTIVE SUMMARYSusquehanna SteamElectricStation(SSES),Units1&2NRCInspection Report05000387/1 999012,05000388/1 999012Thisinspection includedaspectsofPP&L'soperations, maintenance, engineering andplantsupportatSSES.Thereportcoversafive-week periodofroutineresidentinspection activities andannounced inspections byregionalspecialists.

~Qerattone

~PP8Lmadeconservative andeffective decisions inresponsetoincreasing primarycontainment leakageonUnit2.(Section04.1)1~Tworecentequipment failuresrelatedtotheUnit2maintransform'er andUnit1reactorcoreisolation coolingtemperature switchmodulewereattributed toinadequate follow-up actionsrelatedtoindustryeventinformation thathadbeenpreviously reviewedbyPP&Linthe1986and1990timeframes.(Section08.1)Maintenance IAfterPPBLmanagement established anEventReviewTeam,PP&Lsuccessfully resolvedthenumerousproblemsthatoccurredfollowing the2yearpreventive maintenance onthe"A"emergency dieselgenerator.

(SectionM1.2)Duringtheplannedreplacement oftwoemergency servicewater(ESW)pumps,PP&L'smaintenance department exhibited excellent workperformance andgoodmanagement oversight.

(SectionM1.3)~Enineerin~TheIndependent SafetyEngineering Groupreportresultswer'eindicative ofthorough.investigation andanalysisofplantissuesandpersonnel performance.

Thereportswereobjective andcontained meaningful feedbacktoplantmanagement.

(SectionE7.1)PlantSuortPP8Limplemented effective appliedradiological controls.

Theradiation workpermitprogramwasadequately implemented.

Personnel occupational exposurewasmaintained withinapplicable regulatory limitsandaslowasreasonably achievable.

Accesscontrolstoradiologically controlled areaswereeffective, andappropriate occupational exposuremonitoring deviceswereprovidedandused.(SectionR1.1)PP&Limplemented overalleffective surveys,monitoring, andcontrolofradioactive materials andcontamination.

HealthPhysicstechnicians properlydocumented surveyresults.Ingeneral,radiological housekeeping conditions wereacceptable.

(SectionR1.2) t' Executive SummaryoSecurityandsafeguards activities withrespecttoalarmstationcontrols, communications, andprotected areaaccesscontrolofpersonnel, packagesandvehicleswereeffectively implemented.

(SectionS1)Securityandsafeguards procedures anddocumentation wereproperlyimplemented.

Eventlogswereproperlymaintained andeffectively usedtoanalyze,track,andresolvesafeguards events.(SectionS3)Thesecurityforcemembers(SFMs)wereprovidedeffective trainingandadequately demonstrated thattheyhadtherequisite knowledge necessary toeffectively implement theirdutiesandresponsibilities.

(Sections S4andS5)CManagement supportwasadequatetoensureeffective implementation ofthesecurityprogram,asevidenced byadequatestaffinglevelsandtheallocations ofresources tosupportprogrammatic needs.(SectionS6)

TABLEOFCONTENTSI.Operations 01020408ConductofOperations

..01.1UnitOperations andOperatorActivities Operational StatusofFacilities andEquipment 02.1Operational SafetySystemAlignment

.OperatorKnowledge andPerformance

.04.1Unit2ReactorShutdownandPlantRestartMiscellaneous Operations Issues08.1LicenseeEventReport(LER)ReviewII.Maintenance

..IM1ConductofMaintenance

~~~~~~~~~~~~~P~~~~~~~~~M1.1Surveillance andPre-Planned Maintenance ActivityReview....

M1.2"A"Emergency DieselGenerator Restoration following 2-YearInspection r"..3..3..3M1.3"C"and"D"Emergency ServiceWaterPumpOverhauls

...~...~....5III.Engineering

..E7QualityAssurance inEngineering Activities E7.1Oversight ofStationActivities

....66..6IV.PlantSupport.R1Radiological Protection andChemistry (RP&C)ControlsR1.1Radiological Controls-External andInternalExposureR1.2Radiological Controls-Radioactive Materials, Contamination, Surveys,666R7S1S2S3S4S5S6S7S8ConductofSecurityandSafeguards Activities StatusofSecurityFacilities andEquipment SecurityandSafeguards Procedures andDocumentation 10SecurityandSafeguards StaffKnowledge andPerformance..............

12SecurityandSafeguards StaffTrainingandQualification

.12SecurityOrganization andAdministration...................

13QualityAssurance (QA)inSecurityandSafeguards Activities.............

13Miscellaneous SecurityandSafeguards Issues...........

14S8.1(Closed)LER50-387/99-005-00, Safeguards EventandMonitoring

..'.7R1.3Radiological Controls-As LowAsReasonably Achievable (ALARA)..~~8QualityAssurance inRP&CActivities 9V.Management Meetings..X1ExitMeetingSummary.INSPECTION PROCEDURES USED.ITEMSOPENED,CLOSED,ANDDISCUSSED LISTOFACRONYMSUSED....14,.14..15..15..16IV ReortDetailsSummaofPlantStatusSusquehanna SteamElectricStation(SSES)Unit1operatedat100%powerthroughout theinspection periodwithtwoexceptions.

OnDecember4,powerwasreducedto75%tochangecontrolrodpositions andtoperformcontrolrodinsertion timeandmainsteamisolation valvetesting,thenreturnedto100%power.OnDecember31,powerwasreducedto80%asayear2000contingency, thenreturnedto100%onJanuary1,2000.SSESUnit2operatedat100%powerthroughout theinspection periodwiththreeexceptions.

OnDecember11,powerwasreducedto85%tochangecontrolrodpositions andperformcontrolrodinsertion timetesting,thenreturnedto100%power.OnDecember17,anormalshutdownwasperformed torepairaleakinginstrument lineforthe"A"reactorrecirculation pump.TheUnitwasrestarted onDecember23,andreached100%poweronDecember25.OnDecember31,powerwasreducedto80%asayear2000contingency, thenreturnedto100%onJanuary1,2000.l.0erations01ConductofOperations

'1.1Unit0erationsand0eratorActivities (71707)Theinspectors determined routineoperatoractivities weresatisfactorily established, communicated andconservatively performed inaccordance withSSESprocedures.

Controlroomlogsaccurately reflected plantactivities.

Duringtoursofthemaincontrolroom,theinspectors observedgoodturn-over briefings andformalcommunications.

02Operational StatusofFacilities andEquipment 02.10erational SafeSstemAIinment(71707)Duringroutine/lant tours,theproperalignment andoperability ofvarioussafetysystems,engineered safetyfeatures, andon-sitepowersourceswereverified.

Partialwalkdowns wereperformed fortheemergency servicewater,"A"emergency dieselgenerator, con'trolroddrive,andreactorrecirculation systems.Noequipment problemswerenoted.Topicalheadingssuchas01,MB,etc.,areusedinaccordance viiththeNRCstandardized reactorinspection reportoutline.Individual reportsarenotexpectedtoaddressailoutlinetopics.

04OperatorKnowledge andPerformance 04.1Unit2ReactorShutdownandPlantRestartTheinspectors reviewedPP8L'sresponsetoanincreaseinprimarycontainment unidentified waterleakage;themanagement evaluation anddecisiontoperformacontrolled reactorshutdown; andtheassessment oftheoperatoractionsduringtheplantshutdown, equipment repairs,andsubsequent reactorstartup.Cb.Observations andFindinsInresponsetoanincreasing primarycontainment unidentified waterleakage,operators startedreducingreactorpoweronUnit2onDecember16,toallo'wforinspection insidetheprimarycontainment

.Primarycontainment unidentified waterleakagehadincreased to0.87gallonsperminute(gpm.)TheTechnical Specification (TS)limitwas5gpm.ThePP8Linspection discovered asmallwaterleakona3/4inchinstrument pipeassociated withthepressureindication forthe"A"reactorrecirculation pumpseal.Theleakwaslocatedatawelded45degreeelbowconnection.

PP8Ldetermined thattheweldcrackedduetohighcyclefatiguecausedbyvibrational stresses.

Thelinewasreplacedwithamodifiedpipethateliminated the45degreeelbowweld.Inaddition, apipehangerwasaddedtoprovideaddedsupport.PP8Lins'pected the"B"pumppipeandothersimilarreactorrecirculation pipesandfoundnoadditional problems.

The"A"reactorrecirculation pumppiperepairswerecompleted December20,1999.PP8Lmanagement decidedtokeeptheunitshutdowntorepair.severalotherequipment reliability problemspriortoplantrestart.Thedecisiontocorrectadditional knownequipment problemspriortorestartwasinlinewithPP&L'snewpolicyconcerning improvement inequipment reliability.

Unit2wasrestarted safelyonDecember23,andreachedfullpoweronDecember25.C.Conclusions PP&Lmadeconservative andeffective decisions inresponsetoincreasing primarycontainment leakageonUnit2.08Miscellaneous Operations Issues'8.1LicenseeEventReortLERReview(71707,92700)

ClosedLER50-387/99-004-00 ReactorCoreIsolation Cooling(RCIC)ManuallyIsolatedduetoFailureofSteamLeakDetectorTemperature Switch OnAugust8,1999,operators manuallyisolatedRCICinresponsetoasteamleakdetection pipingareahightemperature alarm.Thealarmwascausedbyafailureofatemperature switchmodulewhichhadbeeninstalled 3daysearlier.ThemodulewasreplacedandRCICreturnedtoservicewithin4hours.PP8Lanalysisfoundthatafaultypowersupplycapacitor causedthemoduletofail.Thesemoduleswerethesubjectofa1986GeneralElectricServiceInformation Letterwhichrecommended thatthe7yearshelflifeforthemoduleshouldnotbeextendedunlessthecapacitors werereplacedwithupgradedcomponents.

Thefailedmodule,althoughnew,hadbeenstoredinthewarehouse since1984andhadnotbeenupgraded.

PP&Lconcluded thatthevendornoticehadbeenproperlyprocessed inaccordance withtheSSESIndustryEventReviewProgram(IERP);but inadequate actionhadbeentakenfortheIERPrecommendations.

Theinspectors notedthatthiswasasecondexamplewhereInduhtryeventinformation hadbeenpreviously reviewedbyPP8Lwithoutadequatefollow-up action.NRCIR50-387,388/99-06 discussed theJune1999Unit2maintransformer failurewhichresultedfromamanufacturing defectidentified in1990.Theinspectors determined thatthePP8Ldocumentation ofthiseventwasappropriate andrelettherequirements of10CFR50.73.ThiseventwasreviewedinmoredetailinNRCIR050000387/1 999012and050000388/1 999012.ThisLERisclosed.II.Maintenance M1ConductofMaintenance M1.1Surveillance andPre-Planned Maintenance ActiviReviewTheinspectors observedandreviewedselectedportionsofpre-planned maintenance andsurveillance activities, todetermine whethertheactivities wereconducted inaccordance withNRCrequirements andSSESprocedures.

b.Observations andFindinsTheinspectors observedportionsofthefollowing workactivities andsurveillances:

WorkAuthorizations

~PCWO205801PCWO214659PCWO215235PCWO218447PCWO105153PCWO106084PCWO202805Unit2ControlRodDriveDischarge ValveInspection andRepair"A"Emergency DieselGenerator Troubleshooting ExcessFlowCheckValveXV-142-F059G Rework"2B"RecircM-GScopeTubeLockupInvestigation "C"ESWPumpOverhaul"C"ESWPumpMotorBearingReplacement "D"Emergency ServiceWaterPumpRebuild Surveillances CH-SY-004 OP-264-001 TP-024-145 SI-264-305 SO-015-002 SE-024-B01 SO-024-A01 Functional TestofthePostAccidentSamplingStation(PASS)Unit2Recirculation PumpScoopTubeUnlocking 4"A"Emergency DieselGenerator PostMaintenance TestRecircM-GMechanical StopVerification

'SWValveStrokeTesting"B"EDG24-hourSurveillance Run"A"EDGMonthlySurveillance RunInaddition, selectedportionsofprocedures anddrawingsassociated withthemaintenance andsurveillance activities werealsoreviewedanddetermined tobeacceptable.

Ingeneral,maintenance personnel wereknowledgeable oftheirassignedactivities.

M1.2"A"EmerencDieselGenerator Restoration followin2-YearIn'ctionTheinspectors observedandreviewedselectedportionsoftHe"A"Emergency DieselGenerator (EDG)restoration andsurveillance activities.

Theactivities andworkdocuments werereviewedtodetermine whethertheactivities wereconducted inaccordance withNRCrequirements andSSESprocedures.

b.Observations andFindinsOnOctober4,1999,the"A"EDGwasremovedfromservicetoperformthe2yearpreventative maintenance inspection.

The"E"EDGwassubstituted forthe"A"EDG.Restoration ofthe"A"EDGinitially commenced onNovember5,following completion oftheplannedmaintenance.

Duringthepostmaintenance testing,numerousproblemswereencountered including anairstartfailure,gasketleakage(starting airheadertocylinder),

governorinstability, andanunexpected dieselstartwhenswitching fromlocaltoremotecontrol.Afterapproximately 2weeksoftroubleshooting andreworkfailedtorestoreEDGoperability, PP8LformedanEventReviewTeam(ERT)toreviewthe"A"EDGissuesandpostmaintenance testingmethodology.

OnDecember3,PP&Ldetermined thatanewAgastatrelayinstalled duringtherestoration troubleshooting hadamanufacturing defectintheinternalwiring.Theinternally mis-wired relayaccounted forseveraloftheproblemsobservedduringtheinitialrestoration attempt.TheERTtroubleshooting activities werethoroughandthecorrective actionadequately resolvedidentified deficiencies.

The"A"EDGwassuccessfully testedandreturnedtoserviceonDecember6.PP&Lisevaluating themis-wired Agastatrelayinaccordance with10CFR50.21,"Reporting ofDefectsandNoncompliance."

c.Conclusions AfterPP8Lmanagement established anEventReviewTeam,PP8Lsuccessfully resolvedthenumerousproblemsthatoccurredfollowing the2yearpreventive maintenance onthe"A"emergency dieselgenerator.

M1.3"C"and"D"EmerencServiceWaterPumOverhauls Theinspectors observedandreviewedselectedportionsofthe"C"and"D"Emergency ServiceWater(ESW)pumpoverhauls todetermine whethertheactivities wereconducted inaccordance withNRCrequirements andSSESprocedures.

IObservations andFindinsDuringDecember13to16,anESWsystemmaintenance outage.,%as performed toreplacethe"C"and"D"ESWpumpswithrebuiltpumpsandreplacethe"C"pumpmotorbearings.

The"D"ESWpumpwasreturnedtoserviceonDecember14.The"C"ESWpumpwasreturnedtoserviceonDecember16.Theworkactivities werewellplanned,scheduled, andcoordinated.

Theinspectors observedexcellent workperformance bythemaintenance department underextremeweatherconditions andgoodsupervisory andmanagement oversight.

Theinspectors andaRegionalriskassessment specialist reviewedPP8L'sriskassessment fortheplannedESWworkactivities.

Theinspectors foundthatPP8L'scoredamageriskassessment wasthoroughandconsidered allequipment andadministrative controlsrelatedtostationblackoutandlossofoff-sitepowerscenarios.

Nevertheless, theinspectors notedthatbyperforming maintenance ontwopumpsinparallel, versusonepumpatatime,thepotential foraTechnical Specification drivenplantshutdownappearedtobegreater.Theincreased potential ofaforcedshutdownwasoffsetbytheshorterperiodofpumpoutofservicetimeassociated withtheparallelworkschedule.

C.Conclusions Duringtheplannedreplacement oftwoemergency servicewater(ESW)pumps,PPBL'smaintenance department exhibited excellent workperformance andgoodmanagement oversight.

III.EnineerinE7QualityAssurance inEngineering Activities E7.1OversihtofStationActivities Theinspectors reviewedthreeIndependent SafetyEngineering Group(ISEG)assessment reportsrelatedtothefollowing topics:4ISEGreport7-99,Investigation oftheUnit1ReactorRecirculation RunbackEventofSeptember 4,1999.ISEGreport8-99,Investigation oftheResponsetoEmergency ServiceWater(ESW)FlowAnomalies ofSeptember 20,1999.ISEGreport9-99,Surveillance ofPlantOperations, October1999.b.Observations andFindinsITheselectedISEGreportscontained extensive reviewsofselectedplantissueswhichprovidedrecommended actionstoimproveperformance inadministrative andtechnical areas.TheISEGreportswereindicative ofthoroughinvestigation andanalysis.

The1999evaluations werethoroughandselfcriticaloftheevaluated areas.Thereportscontained candidfeedbacktostationmanagement andweredocumented inthecorrective actionprogram.c.Conclusions TheIndependent SafetyEngineering Groupreport.resultswereindicative ofthoroughinvestigation andanalysisofplantissuesandpersonnel performance.

Thereportswereobjective andcontained meaningful feedbacktoplantmanagement.

IV.PlantSuortR1Radiological Protection andChemistry (RP&C)ControlsR1.1RadioloicalControls-External andInternalExosureTheinspector evaluated theeffectiveness ofselectedaspectsoftheappliedradiological controlprogram.Theevaluation includedaselective reviewoftheadequacyandimplementation ofthefollowing radiological controlprogramelementsandactivities:

implementation oftheradiation workpermit(RWP)programRWPNo.1999-0095 and1999-0109 relatedtothereactorwaterclean-up(RWCU)systemaccesscontrolstoradiologically controlled areas(RCAs) useandadequacyofpersonnel occupational exposuremonitoring devicesmaintenance ofpersonnel occupational radiation exposures (external andinternal) withinapplicable regulatory limitsandaslowasreasonably achievable (ALARA)statusoftheNationalVoluntary Laboratory Accreditation Program(NVLAP)periodicthermoluminescent dosimeters (TLD)qualitycontrol(QC)testingoperation andmaintenance ofawhole-body-counting (WBC)programdosecalculations forskindoseandforinternaluptakesTheinspector evaluated performance intheabove-selected areasviaobservation ofworkactivities, toursoftheradiologically controlled area(RCA),discussions withplantpersonnel, reviewofdocumentation, andevaluation ofapplicable stationprocedures.

Observations andFindinsPP&Lmaintained personnel occupational radiation exposures (external andinternal) withinregulatory limitsandaslowasreasonably achievable (ALARA).PP&Limplemented effective accesscontrolstotheradiologichlly controlled areasofthestationincluding useofRWPs,barcodereaders,andcomputerized log-instations.

Noaccesscontroldeficiencies wereidentified.

Appropriate personnel monitoring devicesforaccesstotheRCAweresuppliedandproperlyused.c.Conclusions PP&Limplemented effective appliedradiological controls.

Theradiation workpermitprogramwasadequately implemented.

Personnel occupational exposurewasmaintained withinapplicable regulatory limitsandaslowasreasonably achievable.

Accesscontrolstoradiologically controlled areaswereeffective, andappropriate occupational exposuremonitoring deviceswereprovidedandused.R1.2RadioloicalControls-Radioactive Materials Contamination SurvesandMonitorin InsectionScoe(83750)Theinspector evaluated theeffectiveness ofPP&L'ssurveys,monitoring, andcontrolofradioactive materials andcontamination.

Theevaluation includedaselective reviewoftheadequacyandeffectiveness ofthefollowing radioactive materialandcontamination controlprogramelements:

surveysandmonitoring ofradioactive materialandcontamination thecalibration statusofsurveyandmonitoring equipment theproperuseofpersonalcontamination monitorsandfriskersthetrackingofpersonnel contamination eventsandgoalsTheinspector evaluated performance intheaboveselectedareasviaobservation ofworkactivities, toursoftheRCA,discussions withpersonnel, reviewofdocumentation, andevaluation ofapplicable stationprocedures.

b.Observations andFindinsIngeneral,radiological housekeeping conditions inthereactorandturbinebuildings wereacceptable.

Theinspector notedseveralexamplesofpoorhousekeeping practices inlockedareasofthereactorandturbinebuildings.

Generally, radioactive materialandradioactive wastewereclearlylabeled,segregated, andstoredinanorderlymanner.PP&Limplemented aneffective radioactive materialandcontamination controlprogram.Continuous airmonitorswereusedintheRCA.Areviewofinstrument calibration recordsindicated thatthecalibration programwasimplemented inaccordance withprocedures andonlyoneminordiscrepancy wasnoted.~'Goalstoassistinmonitorirfg andtrackingpersonnel andareacontamination ratesandpercentrecoverable contaminated areacontinued tobemaintained andusedtogaugetheoveralleffectiveness ofthestation's programsinthisarea.c.Conclusions IPP&Limplemented effective surveys,monitoring, andcontrolofradioactive materials andcontamination.

HealthPhysicstechnicians properlydocumented surveyresults.Ingeneral,radiological housekeeping conditions wereacceptable.

R1.3RadioloicalControls-As LowAsReasonabl Achievable ALARATheinspector evaluated theeffectiveness ofPP&L'sprogramtomaintainoccupational radiation exposureaslowasisreasonably achievable.

The.evaluation includedaselective reviewoftheadequacyandeffectiveness ofthefollowing ALARAprogramelements/documents:

April1999HPPerformance Indicator Report1998ALARAAssessment DraftYear2000Person-Rem GoalBreakdown HPUnit2(U2)NinthRefueling andInspection Outage(9RIO)ReportSiteALARACommittee (SAC)AgendaforNovember8,1999Theinspector evaluated performance intheaboveselectedareasviaobservation ofworkactivities, toursoftheRCA,discussions withpersonnel, reviewofdocumentation andstationprocedures.

Observations andFindinsTheALARAprogramcontinued tobewellstaffedandwasbeingimplemented inaccordance withprocedural controls.

Post-jobreviewswerebeingusedtogenerateexposurereduction plan(ERP)itemsforimproving theALARAeffort.Annualandoutageperson-rem goalsforthesitewereestablished, andperson-rem goalsforeachworkgroupweredeveloped.

Onaregularperiodicbasis,actualperson-rem accumulated forthesiteandforeachworkgroupwascomparedtotheprojections basedontheestablished goals.Lessons-learned from1999werebeingusedinthedevelopment oftheannualandoutagegoalsfortheyear2000.Tothisend,theSiteALARACommittee (SAC)established actionstoimprovedosecontrolfortheremainder of1999andwasinvolvedinthedevelopment oflongerrangeexposurereduction activities irtcluding improvedhighradiation areacontrolsandevaluation ofremotemonitoring methods.Additionally, theSACinitiated corrective actionstoaddresslong-standing employeeconcernsand,exposure reduction planitems.Conclusions TheALARAprogramremainsacceptable.

QualityAssurance inRP&CActivities Theinspector evaluated theeffectiveness ofPP&L'sself-identification andcorrective action'processes intheRP&Carea.Theevaluation includedaselective reviewofthevarioussurveillance, audit,andcondition reports.Theinspector alsodiscussed theprocesswithseveralcognizant personnel.

Observations andFindinsTheHealthPhysicsProgramSRC/NASAuditNo.99-007wasbroadinscopeanddetailed.

ThesevenQualitySurveillance Reportsreviewedweredetailed.

Fourassessments werereviewedwhichcoveredradiation protection management, externaldoseassessment, thevendor-provided TLDirradiation service,andavendor-provided instrumentation service.Thebreadthvaried,buteachwasdetailedandresultedinrecommendations forimprovement.

Approximately 160Radiological Protection condition reportswereissuedintheperiodfromDecember31,1998toNovember22,1999.Anumberofcondition reportsrelatedtoHPwerereviewedandfoundtoincludelowthreshold items.Theinspector foundthatforthoseHPcondition reportsreviewed, theissueswereelevatedtoanadequatemanagement level,evaluated, andadequately corrected.

Additional inspection ofPP&L'scorrective actionprogramisdiscussed inInspection Reports05000387/1999013 and05000388/1 999013.

10c.Conclusions PP8L'sself-identification processintheareaofradiation protection wasgenerally, effective.

S1ConductofSecurityandSafeguards Activities Determine whethertheconductofsecurityandsafeguards activities metPP8L'scommitments intheNRC-approved securityplan(thePlan)andNRCregulatory requirements.

Thesecurityprogramwasinspected duringtheperiodofNovember29-December3,1999.Areasinspected included:

alarmstations; communications; protected area(PA)accesscontrolofpersonnel, packagesandvehicles.

b.Observations andFindinsAlarmStationsTheinspector verifiedthatthealarmstationswereequippedwithappropriate alarms,surveillance andcommunications capabilities.

Theinspector determined ininterviews withthealarmstationoperators, thattheywereknowledgeable oftheirdutiesandresponsibilities.

Theinspector alsoverified, throughobservations andinterviews, thatthealarmstationswerecontinuously manned,independent, anddiverse.Thealarmstationsdidnotcontainanyoperational activities thatcouldinterfere withtheexecution ofthedetection, assessment, andresponsefunctions.

Communications Theinspector determined bydocumentreviewsanddiscussions withalarmstationoperators, thatthealarmstationswerecapableofmaintaining continuous intercommunications andcommunications witheachsecurityforcemember(SFM)ondutyandwereexercising communication methodswiththelocallawenforcement

=agenciesascommitted tointhePlan.PAAccessControlofPersonnel VehiclesandHand-Carried PackaesandMaterialOnNovember30,andDecember1,1999,theinspector observedpersonnel andpackagesearchactivities atthepersonnel accessportal.Theinspector determined thatpositivecontrolswereinplacetoensureonlyauthorized individuals weregrantedaccesstothePA,thatallpersonnel andhand-carried itemsenteringthePAwereproperlysearchedandthatvehiclesenteringthePAwereproperlycontrolled, andsearched.

C.Conclusions Securityandsafeguards activities withrespecttoalarmstationcontrols, communications, andprotected areaaccesscontrolofpersonnel, packagesandvehicleswereeffectively implemented andmetPP&Lcommitments andNRCrequirements.

11S2StatusofSecurityFacilities andEquipment (81ŽM)Areasinspected were:PAassessment aids,PAdetection aids,personnel searchequipment andtesting,maintenance andcompensatory measures.

b.Observations andFindinsPAAssessment AidsOnDecember2,1999,theinspector assessedtheeffectiveness oftheassessment aids'byobserving, onclosedcircuittelevision, twoSFMsconducting awalkdownoftheperimeter ofthePA.Theassessment aidshadgenerally goodpicturequalityandzoneoverlap.Additionally, toensurePlancommitments aresatisfied, PP&Lhadprocedures inplacerequiring theimplementation ofcompensatory m'easures intheeventthealarmstationoperators areunabletoproperlyassessthecauseofanalarm.Personnel andPackaeSearchEuimentOnDecember1,1999,theinspector observedbothroutineuseandperformance testingofPP&LPersonnel andpackagesearchequipment.

Theinspector determined thatthesearchequipment performed inaccordance withPP&Lprocedures andPlancommitments.

PADetection AidsTheinspector observedanSFMconducting performance testingoftheperimeter intrusion detection system(PIDS).Thetestingconsisted ofintrusion attemptsinnumerousrandomlyselectedzonesduringthecamerawalkdown.

Theappropriate alarmsweregenerated ineachattempt.Theequipment wasfunctional andeffective andmettherequirements ofthePlan.Conclusions PP&L'ssecurityfacilities andequipment weredetermined tomeettheircommitments andNRCrequirements.

S3SecurityandSafeguards Procedures andDocumentation a.InsectionScoe(81700)Areasinspected were:implementing procedures andsecurityeventlogs.b.Observations andFindinsSecuriProramProcedures Theinspector determined thattheprocedures wereconsistent withthePlancommitments, andwereproperlyimplemented andaccomplished basedonreviewofselectedimplementing procedures associated withPAaccesscontrolofpersonnel, packagesandmaterials, testingandmaintenance ofpersonnel searchequipment, andperformance testingofPAdetection aids.

12SecuritEventLosTheinspector reviewedtheSecurityEventLogsfortheprevioustwelvemonths.Basedonthisreview,anddiscussion withsecuritymanagement, theinspector determined thatPP&Lappropriately

analyzed, tracked,resolvedanddocumented safeguards eventsthatPP8Ldetermined didnotrequireareporttotheNRCwithin1hour.Conclusions S4Securityandsafeguards procedures anddocumentation wereproperlyimplemented.

EventLogswereproperlymaintained andeffectively usedtoanalyze,track,andresolvesafeguards events.1SecurityandSafeguards StaffKnowledge andPerformance

~.(B'M)Areainspected was:securitystaffrequisite knowledge.

b.Obs'ervations andFindinsSecuritForceReuisiteKnowledeTheinspector observedanumberofSFMsintheperformance oftheirroutineduties.Theseobservations includedalarmstationoperations, personnel, vehicleandpackagesearches, andperformance testingofthePIDS.Additionally, interviews ofSFMswereconducted.

Basedontheresponses, theinspector determined thattheSFMswereknowledgeable oftheirresponsibilities anddutiesandcouldeffectively carryouttheirassignments.

Conclusions TheSFMsadequately demonstrated thattheyhadtherequisite knowledge necessary toeffectively implement thedutiesandresponsibilities associated withtheirposition.

S5SecurityandSafeguards StaffTrainingandQualification Areasinspected weresecuritytrainingandqualifications, andtrainingrecords.b.Observations andFindinsSecuriTraininandQualifications OnDecember3,1999,theinspectors observed7randomlyselectedtrainingandqualification (T8Q)recordsofSFMs.Physicalandrequalification recordswereinspected forarmedandsupervisory personnel.

Theresultsofthereviewindicated thatthesecurityforcewasbeingtrainedinaccordance withtheapprovedT8Qplan.C.TraininRecordsTheinspector determined thattherecordswereproperlymaintained,

accurate, andreflected thecurrentqualifications oftheSFMs.Conclusions t

Securityforcepersonnel werebeingtrainedinaccordance withtherequirements oftheT&QPlan.Trainingdocumentation wasproperlymaintained andaccurateandthetrainingprovidedbythetrainingstaffwaseffective.

S6SecurityOrganization andAdministration Areasinspected were:management support,effectiveness andstaffinglevels.Observations andFindinsManaementSuortTheinspector determined basedonreviewofprogramimplementation sincethelastprograminspection, thatadequatesupportandresources continued tobeavailable toensureprogramimplementation.

Tiiiidiiyminimumrequirements specified inthePlanandimplementing procedures.

Noperformance issueswerenotedintheareasinspected.

Conclusions Management supportwasadequatetoensureeffective implementation ofthesecurityprogram,asevidenced byadequatestaffinglevelsandtheallocations ofresources tosupportprogrammatic needs.S7QualityAssurance (QA)inSecurityandSafeguards Activities InsectionScoe(81700)Areasinspected were:audits,problemanalyses, corrective actionsandeffectiveness ofmanagement controls.

b.Observations andFindinsAuditsTheinspector reviewedtheannualphysicalsecurityaudit.Theauditwasthoroughandin-depth.

Theauditidentified 4deficiencies.

Thedeficiencies wererelatedtoadministrative

controls, andwereminordocumentation errors.Noneoftheauditfindingswereindicative ofprogrammatic issues.ProblemAnalsesTheinspector revieweddataderivedfromthesecuritydepartment's self-assessment program.Potential weaknesses werebeingproperlyidentified, tracked,andtrended.'orrective ActionsTheinspector reviewedthecorrective actionsimplemented byPP&Linresponsetothe1999QAauditandself-assessment program.Thecorrective actionsweretechnically soundandwereperformed inatimelymanner.Effectiveness ofManaementControlsPP&Lhadprogramsinplaceforidentifying, analyzing andresolving problems.

Theyincludedtheperformance ofannualQAaudits,adepartmental self-assessment programandtheuseofindustrydatasuchasviolations ofregulatory requirements identified bytheNRCatotherfacilities, asacriterion forself-assessment.

c.Conclusions PP8L'sauditprogramwasbeingproperlyadministered.

Inaddition',

theself-assessment programwasbeingeffectively implemented toidentifyandresolvepotential weakness.

SSMiscellaneous SecurityandSafeguards IssuesS8.1ClosedLER50-387/99-005-00 SafeuardsEvent(71750,92700)*OnAugust6,1999,PP8Lidentified thatanobservation whichinadvertently contained safeguards information hadbeendistributed viaanuncontrolled electronic mail(e-mail)system.Areviewwasconducted ofPP8L'scorrective actionsassociated withthisevent,addressing thedissemination ofsafeguards viacompanye-rrfail.

Itwasdetermined thatPP8Limplemented appropriate compensatory

measures, andcorrective actionstoprecluderecurrence wereacceptable.

Noviolation ofNRCrequirements wasidentified.

ThisLERisclosed.V.ManaementMeetinsX1ExitMeetingSummaryARegionIsecurityspecialist presented theresultsoftheSecurityandSafeguards programinspection tomembersofPP8Lmanagement attheconclusion oftheinspection onDecember3,1999.PP8Lacknowledged thefindingspresented.

ARegionIhealthphysicsspecialist presented theresultsoftheRadiological Controls-ExternalandInternalExposureprogramsinspection tomembersofPP8Lmanagement attheconclusion oftheinspection onDecember10,1999.PPBLacknowledged thefindingspresented.

Theinspectors presented theinspection resultstomembersofPP&Lmanagement attheconclusion oftheinspection period,onJanuary7,2000.PP8Lacknowledged thefindingspresented.

Theinspectors askedPP&Lwhetheranymaterials examinedduringtheinspection

~shouldbeconsidered proprietary.

Noproprietary information wasidentified.

15INSPECTION PROCEDURES USEDIP37551IP40500IP61726IP62700IP62707IP71707IP71750IP81700IP83750.IP92700OnsiteEngineering Observations Effectiveness ofLicenseeControlsinIdentifying, Resolving, andPreventing ProblemsSurveillance Observations Maintenance ProgramImplementation Maintenance Observations PlantOperations PlantSupportActivities PhysicalSecurityProgramforPowerReactorsIOccupational Radiation ExposureOnSiteFollowupofReports~OenedNone.0ened/Closed ITEMSOPENED,CLOSED,ANDDISCUSSED None~UdatedNone.Closed50-387/99-004-00 LERReactorCoreIsolation Cooling(RCIC)ManuallyIsolatedduetoFailureofSteamLeakDetectorTemperature Switch(Section08.1)50-387/99-005-00 LERSafeguards Event(SectionS8.1) 16LISTOFACRONYMSUSEDCFRCRCSDCPEALEDG0FFSARIRLCOLERLLRTLPCIMSIVNCVNDAPNOVNRCNUMARCODOSHAPCOPCPRPP8LRCICRHRRPSRP&CscfhSSCsSSESTSCodeofFederalRegulations Condition ReportCoreSprayDesignChangePackageEmergency PlanActionLevelEmergency DieselGenerator Fahrenheit FinalSafetyAnalysisReport[NRC]Inspection ReportLimitingCondition forOperation LicenseeEventReportLocalLeakRateTestLowPressureCoolantInjection Main,SteamIsolation ValveNon-Cited Violation NuclearDepartment Administrative Procedure

[NRC]NoticeofViolation NuclearRegulatory Commission NuclearManagement andResources CouncilOperability Determination Occupational SafetyandHealthAdministration PlantControlOperatorPlantComponent ProblemReportPennsylvania PowerandLightCompanyReactorCoreIsolation CoolingResidualHeatRemovalReactorProtection SystemRadiological Protection andChemistry StandardCubicFeetperHourStructures, Systems,andComponents Susquehanna SteamElectricStationTechnical Specification FROM:VICTORDRICKSORIGINALDUEDT:02/25/00TICKETNO:020000010 l&gD@~4"'g/(y/~g DOCDT'11800NRRRCVDDATE:01/24/00TO:VICTORNERSESFORSIGNATURE OF**+EL**DESC:SUSQUEHANNA-2

SHUTDOWN, DEC99ROUTING:COLLINS/ZIMMERMN g'JOHNSON SHERONNRRMAILROOMASSIGNEDTO:CONTACT:DLPMJ.ZWOLINSKI SPECIALINSTRUCTIONS ORREMARKS:

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Mon,Jan17,20008:36AMSusquehanna-2

Shutdown, Dec.99DearSirsinaNucleonics Weekarticle(23/12/99, p.3)wasmentioned ashutdownofSusquehanna-2 NPPduetoastresswaused weldleakinareactorcirculation pump.OntheNRCwebsiteIcouldn'tfindanymentionoftheevent.Soifyoucouldprovidemewithinformation tofollowing points:-whatkindofmaterialwasaffected(INCONELtype)?-hastheNRCreleasedapublication addressing thisspecificevent'-NRC-spokesman SamHansellisquotedinthearticle,statingthatNRCwillexamineifthereisaBWRgenericissue.Whatfindingsgenerated theexamination oftheSusquehanna-leakV

-IsthedetailedcauseoftheproblemknownandisitrelatedwithpowerupratingofBWR'?-AreotherBWR-owners intheUSconfronted withsimilarproblems'?

Ifso,hasNRCtakenanyactionyettoobligetheownerstoaddresstheproblem'-Havesimilarproblemseventually causedbyincreased materialstressduetopowerupratingoccurredbeforeinBWRintheUS'?Ithankyouinadvanceforyouranswer.Sincerely yoursUlrichMuellerUeliMuellerKoordinator Atomkampagne Greenpeace PostfachCH-8031Zuerich++4114474123Phone++4114474199Fax NoDegbcnaat-Message.tul Page1Received:

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Date:Mon,17Jan200014:36:27+0100 To:opanrc.gov From:UeliMueller<ueli.mueller@ch.greenpeace.org>

Subject:

Susquehanna-2

Shutdown, Dec.99Content-Type:

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format="flowed" DearSirsinaNucleonics Weekarticle(23/12/99, p'.3)wasmentioned ashutdownofSusquehanna-2 NPPduetoastress-caused weldleakinareactorcirculation pump.OntheNRCwebsiteIcouldn'tfindanymentionoftheevent.Soifyoucouldprovidemewithinformation tofollowing points:-whatkindofmaterialwasaffected(INCONELtype)'-hastheNRCreleasedapublication addressing thisspecificevent'-NRC-spokesman SamHansellisquotedinthearticle,statingthatNRCwillexamineifthereisaBWRgenericissue.Whatfindingsgenerated theexamination oftheSusquehanna-leak7

-IsthedetailedcauseoftheproblemknownandisitrelatedwithpowerupratingofBWR'?-Areother,BWR-owners intheUSconfronted withsimilarproblems'?

Ifso,hasNRCtakenanyactionyettoobligetheownerstoaddresstheproblem7-Havesimilarproblemseventually causedbyincreased materialstressduetopowerupratingoccurredbeforeinBWRintheUS'?Ithankyouinadvanceforyouranswer.Sincerely yoursUlrichMuellerUeliMuellerKoordinator Atomkampagne Icooert5cnaar.-Message.tut Page2-Greenpeace PostfachCH-8031Zuerich++4114474123Phone++4114474199Fax CAWINDOWSiTEMP<GNg00021.

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Mon,Jan17,20008:36AMSusquehanna-2

Shutdown, Dec.99DearSirsinaNucleonics Weekarticle(23/12/99, p.3)wasmentioned ashutdownofSusquehanna-2 NPPduetoastress-caused weldleakinareactorcirculation pump.OntheNRCwebsiteIcouldn'tfindanymentionoftheevent.Soifyoucouldprovidemewithinformation tofollowing points:-whatkindofmaterialwasaffected(INCONELtype)'-hastheNRCreleasedapublication addressing thisspecificevent'-.NRC-spokesman SamHansellisquotedinthearticle,statingthatNRCwillexamineifthereisaBWRgenericissue.Whatfindingsgenerated theexamination oftheSusquehanna-leak'

-lsthedetailedcauseoftheproblemknownandisitrelatedwithpowerupratingofBWR'?-AreotherBWR-owners, intheUSconfronted withsimilarproblems'?

Ifso,hasNRCtakenanyactionyettoobligetheownerstoaddresstheproblem'?

.-Havesimilarproblemseventually causedbyincreased materialstressduetopowerupratingoccurredbeforeinBWRintheUS'?Ithankyouinadvanceforyouranswer.Sincerely yoursUlrichMuellerUeliMuellerKoordinator Atomkampagne Greenpeace PosffachCH-8031Zuerich++4114474123Phone++4114474199Fax 0t18Payg,A~lrJ'

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Date:Mon,17Jan200014:36:27+0100 To:opa@nrc.gov From:UeliMueller<<ueli.mueller@ch.greenpeace.org>

Subject:

Susquehanna-2

Shutdown, Dec.99Content-Type:

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format="flowed" DearSirsinaNucleonics Weekarticle(23/12/99, p.3)wasmentioned ashutdownofSusquehanna-2 NPPduetoastress-caused weldteakinareactorcirculation pump.OntheNRCwebsiteIcouldn'tfindanymentionoftheevent.Soifyoucouldprovidemewithinformation tofollowing points:-whatkindofmaterialwasaffected(INCONELtype)'?-hastheNRCreleasedapublication addressing thisspecificevent'-NRC-spokesman 5amHansellisquotedinthearticle,statingthatNRCwillexamineifthereisaBWRgenericissue.Whatfindingsgenerated theexamination oftheSusquehanna-leak'

-IsthedetailedcauseoftheproblemknownandisitrelatedwithpowerupratingofBWR?-Areother,BWR-owners intheUSconfronted withsimilarproblems'?

Ifso,hasNRCtakenanyactionyettoobligetheownerstoaddresstheproblem7-Havesimilarproblemseventually causedbyincreased materialstressduetopowerupratingoccurredbeforeinBWRintheUS'?Ithankyouinadvanceforyouranswer.Sincerely yoursUlrichMuellerUeliMuellerKoordinator Atomkampagne Rc,be~Schaaf.-Message.ullolPage2'reenpeace PostfachCH-8031Zuerich++4114474123Phone++4114474199Fax

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