ML17292B534

Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error

ML17292B534
Person / Time
Site:	Columbia
Issue date:	01/15/1999
From:	RICHARD I C, RICKARD I C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ASEA BROWN BOVERI, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-99 LD-99-002, LD-99-2, NUDOCS 9901220123
Download: ML17292B534 (89)

Text

January15,1SS9LD-99-002 U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555

Subject:

ReportofaOefectPursuantto1QCFR21Concerning Incorrect ModelingofaBWRLowerPlenumVolumeinBISONThepurposeofthisletteris'tonotifytheNuclearRegulatory Commission ofadefectunder10CFR21,"Reporting ofDefectsandNoncompliance."

ThedefectconcernstheOperating LimitfortheMinimumCriticalPowerRatio(MCPR)inBoilingWaterReactors(BWRs)analyzedusingtheBISONfasttransient analysiscode.Specifically, thedefectinvolvesincorrect modelingofthereactorvessellowerplenumvolumeintheBISONcode,whichcouldleadtotheestablishment ofnon-conservative MCPROperating Limitsinplanttechnical specifications.

TheEnclosure summarizes theevaluation performed byABBCombustion Engineering (ABB-CE).

Ifyouhaveanyquestions, pleasefeelfreetocontactmeorVirgilPaggenofmystaffat(860)2854700,Verytrulyyours,COMBUSTION ENGINEERING, INC.lan.ickard,DirectoruclearLicensing

Enclosure:

Asstatedcc:M.A.Barnoski(ABB-CE)~(,.t~ABBCombustion Engineering NuclearPowerComhusion Engineer(ng, Inc.P.O.Box5002000DayHihRd.Windsor,CT0609&0500 Te(ephone (880)888-1911Fax(880)285-5203

Enclosure toLD-99-002 Page2of2(vi)Inthecaseofabasiccomponent whichcontainsadefectorfailstocomply,thenumberandlocationofallsuchcomponents inuseat,suppliedfor,orbeingsuppliedforoneormorefacilities oractivities subjecttotheregulations inthispart:TheBISONcomputercodeisaproprietary ABBAtomABprogramusedbyABB-CEforperforming BWRsafetyanalysesforU.S.customers.

Thedefectappliesonlytoreloadfuelassemblies currently inoperation atWNP-2.(vii)Thecorrective actionwhichhasbeen,isbeing,orwillbetaken;thenameoftheindividual ororganization responsible fortheaction;andthelengthoftimethathasbeenorwillbetakentocompletetheactiontAnevaluation ofthedefecthasbeenperformed byABB-CE.Theresultsofthatevaluation showthatthereisnosafetyproblematWNP-2foroperation ofthepreviousCycles12and13anditscurrentCycle14operating state(NormalScramSpeed,Recirculation PumpTripoperable, andTurbineBypassoperable) priorto5,000MWd/MTU.Thatis,theestablished MCPROperating Limitscurrently intheplanttechnical specifications forthisoperating stateprovideadequateprotection.

However,certainMCPROperating Limitsforotheroperating statespriorto5,000MWd/MTUandalloperating statesafter5,000MWd/MTUforWNP-2Cycle14mustbeincreased toaccommodate thedefect.Theutilitycurrently projectsthatWNP-2willreach5.000MWd/MTUinearly1999.ABB-CEhasnotifiedtheWashington PublicPowerSupplySystemofthenecessary changestotheWNP-2MCPROperating Limits.TheBISONcodemodelforWNP-2hasbeenrevisedtocorrecttheerror.AllABB-CEBWRfuelusershavebeennotifiedofthiscondition.

(viii)Anyadvicerelatedtothedefectorfailuretocomplyaboutthefacility,

activity, orbasiccomponent thathasbeen,isbeing,orwillbegiventopurchasers orlicensees:

TheWashington PublicPowerSupplySystemhasbeennotifiedofthedefectandhasbeenprovidedwithrevisedMCPROperating LimitsforWNP-2.TOTALP.84 Enclosure toLD-99<02Pageosof2ABBCombustion Engineering NuclearPower10CFR21ReortofaDefectorFailuretoComIThefollowing information isprovidedpursuanttotherequirements setforthin10CFR21.21(c)(4):

(l)liameandaddressoftheindividuals informing theCommiss1on:

lanC.Rickard,DirectorNuclearLicensing Combustion Engineering, Inc.2000DayHillRoad.Windsor,CT06095-0500 (ii)Identification ofthefacility, theactivity, orthebasiccomponent suppliedforsuchfacilityorsuchactivitywithintheUnitedStateswhichfailstocomplyorcontainsadefect:Theactivityforwhichthisreportisbeingfiledistheestablishment ofnon-conservative MCPROperating LimitsfortheWashington PublicPowerSupplySystemNuclearProjectUnit2(WNP-2)nuclearpowerplantduringCycles12,13,and14operation..

(iii)Identification ofthefirconstructing thefacilityorsupplying thebasiccomponent whichfailstocomplyorcontainsadefect:Combustion Engineering, Inc.2000DayHillRoadWindsor,CT06095-0500 (iv)iVatureofthedefectorfailuretocomplyandthesafetyhazardwhichiscreatedorcouldbecreatedbysuchdefectorfailuretocomply:Thedefectidentified involvestheincorrect modelingofthereactorvessellowerplenumvolumeintheBISONcode.ThedefectcausedtheBISONcodemodeltohavealowerplenumvolumeapproximately twiceitspropersize.Thisincorrect modelinghasthepotential toleadtocalculation ofnon-conservative MCPROperating Limitsinsomesituations.

(v)Thedateonwhichtheinformation ofsuchdefectorfailuretocomplywasobtained:

ABB-CEdetermined thatadefectintheBISONcodeexistedonJanuary14.1999.

02/16/1999 X/U,S.Nuc/egu/atory Commission Operations CenterReportGeneralInformation orOther(PAR)P~aeIEvent¹35271RepOrg:ABBCOMBUSTION ENGINEERING Supplier:

ABBCOMBUSTION ENGINEERING Region:1City:WINDSORCounty:State:CTNotification Date/Time:01/15/1999 14:15(EST)EventDate/Time:01/15/1999 14:15(EST)Lastllodiflcation:

01/15/1999 Docket¹:Agreement State:NoLicense¹:UNSPECIFIED PARAGRAPH NRCNotifiedby:IANRICKARDMQOpsOfficer:DOUGWEAVEREmergency Class:NONEMERGENCY 10CFRSection:21.21Notifications:

BLAIRSPITZBERG VERNHODGER4NRRPART21NOTIFICATION RELATEDTOMINIMUMCRITICALPOWERRATIO(MCPR)"ThepurposeofthisletteristonotifytheNuclearRegulatory Commission ofadefectunder10CFR21,'Reporting ofDefectsandNoncompliance.'he defectconcernstheOperating LimitfortheMinimumCriticalPowerRatio(MCPR)inBoilingWaterReactors(BWRs)analyzedusingtheBISONfasttransient analysiscode.Specifically, thedefectinvolvesincorrect modelingofthereactorvesseltowerplenumvolumeintheBISONcode,whichcouldleadtotheestablishment ofnon-conservative MCPROperating Limitsinplanttechnical specifications.

"TheEnclosure summarizes theevaluation performed byABBCombustion Engineering (ABB-CE).

Ifyouhaveanyquestions, pleasefeelfreetocontactme[IanC.RickardJorVirgilPaggenofmystaff."'IThiseventeffectsWNP-2currentoperating cycle(Cycle14).Ii**iIiii*Iii*i*IiiIiiiiIIiii*IiIIII****i**ii*i*I**i*IIiiIiiIiiiI11IiI*iilIIiiIi**iiiiIIIIIIi*IIiiII*Il1IIIIiIIiII*IiiIIiIii******iIIi~ii*

CATEGORYj.REGULAYINFORMATION DISTRIBUTIO SYSTEM(RIDS)ACCESSION NBRP9901220123 DOC.DATE:

99/01/15NOTARIZED:

NODOCKET¹FACIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUTH.NAMEAUTHORAFFILIATION RICKARD,I.C.

ABBCombustion Engineering Nuclear'uel (formerly Combustio RICHARD,I.C.

ABBAtom,Inc.(formerly ASEAAtom,Inc.)RECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)

SUBJECT:

Part21reptreincorrect modelingofBWRlowerplenumvolinBISON.Decfect appliesonlytoreloadfuelassemblies currently inoperation atWNP-2.BISON codemodelforWNP-2hasbeenrevisedtocorrecterror.DISTRIBUTION CODE:IE19TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:Part21Rept(50DKT)NOTES:INTERNARECIPIENT IDCODE/NAME PD4-2PDRES/DET/EIB RGN2RGN4COPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME POSLUSNY,C NRR/DRPM/PECB PDRWARD,M.RGNlRGN3COPIESLTTRENCL1111111111EXTERNAL:

INPORECORDCTRNRCPDR1111NOACSILVER,ENUDOCSFULLTXT1.111,VHSGCu~emrHASSKOSH~0NOTETOALLnRIDSnRECIPIENTS PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:

LTTR15ENCL15 r>"5,~fit+~~>

~'~".~l llew,OLFQOJanuary15,1999LD-99-002 U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555

Subject:

ReportofaDefectPursuantto10CFR21Concerning Incorrect ModelingofaBWRLowerPlenumVolumeinBISONThepurposeofthisletteristonotifytheNuclearRegulatory Commission ofadefectunder10CFR21,"Reporting ofDefectsandNoncompliance."

ThedefectconcernstheOperating LimitfortheMinimumCriticalPowerRatio(MCPR)inBoilingWaterReactors(BWRs)analyzedusingtheBISONfasttransient analysiscode.Specifically, thedefectinvolvesincorrect modelingofthereactorvessellowerplenumvolumeintheBISONcode,whichcouldleadtotheestablishment ofnon-conservative MCPROperating Limitsinplanttechnical specifications.

TheEnclosure summarizes theevaluation performed byABBCombustion Engineering (ABB-CE).

Ifyouhaveanyquestions, pleasefeelfreetocontactmeorVirgilPaggenofmystaffat(860)285<700.Verytrulyyours,COMBUSTION ENGINEERING, INC.lan.ickard,DirectoruclearLicensing

Enclosure:

Asstatedcc:M.A.Barnoski(ABB-CE)'VABBCombustion Engineering NuclearPowerCornbusdon Engineering, Inc.P.O.Box5002000DayHillRd.Mrindsor, CT060954500 Telephone (860)688-1911Fax(860)285-5203'7901220123 990115PDRADQCK05000397S,PDR Enclosure toLD-99-002 Page1of2ABBCombustion Engineering NuclearPower10CFR21ReortofaDefectorFailuretoComIThefollowing information isprovidedpursuanttotherequirements setforthin10CFR21.21(c)(4):

(i)Nameandaddressoftheindividuals informing theCommission:

lanC.Rickard,DirectorNuclearLicensing Combustion Engineering, Inc.2000DayHillRoadWindsor,CT06095-0500 (ii)Identification ofthefacility, theactivity, orthebasiccomponent suppliedforsucltfacilityorsucltactivitywithintheUnitedStateswhichfailstocomplyorcontainsadefect:Theactivityforwhichthisreportisbeingfiledistheestablishment ofnon-conservative MCPROperating LimitsfortheWashington PublicPowerSupplySystemNuclearProjectUnit2(WNP-2)nuclearpowerplantduringCycles12,13,and14operation.

(iii)Identification oftltefirmconstructing thefacilityorsupplying thebasiccomponent whichfailstocomplyorcontainsadefect:Combustion Engineering, Inc.2000DayHillRoadWindsor,CT06095-0500 (iv)Natureofthedefectorfailuretocomplyandtltesafetyhazardwhicltiscreatedorcouldbecreatedbysuchdefectorfailuretocomply:Thedefectidentified involvestheincorrect modelingofthereactorvessellowerplenumvolumeintheBISONcode.ThedefectcausedtheBISONcodemodeltohavealowerplenumvolumeapproximately twiceitspropersize.Thisincorrect modelinghasthepotential toleadtocalculation ofnon-conservative MCPROperating Limitsinsomesituations.

(v)Thedateonwhichtlteinformation ofsuchdefectorfailuretocomplywasobtained:

ABB-CEdetermined thatadefectintheBISONcodeexistedonJanuary14,1999.

Enclosure toLD-99-002 Page2of2(vi),Inthecaseofabasiccomponent wltichcontainsadefectorfailstocomply,thenumberandlocationofallsuchcomponents inuseat,suppliedfor,orbeingsuppliedforoneormorefacilities oractivities subjecttotheregulations inthispart:TheBISONcomputercodeisaproprietary ABBAtomABprogramusedbyABB-CEforperforming BWRsafetyanalysesforU.S.customers.

Thedefectappliesonlytoreloadfuelassemblies currently inoperation atWNP-2.(vii)Thecorrective actionwlticlthasbeen,isbeing,orwillbetaken;thenameoftheindividual ororganization responsible fortheaction;andthelengthoftimetltathasbeenorwillbetakentocompletetheaction:Anevaluation ofthedefecthasbeenperformed byABB-CE.Theresultsofthatevaluation showthatthereisnosafetyproblematWNP-2foroperation ofthepreviousCycles12and13anditscurrentCycle14operating state(NormalScramSpeed,Recirculation PumpTripoperable, andTurbineBypassoperable) priorto5,000MWd/MTU.Thatis,theestablished MCPROperating Limitscurrently intheplanttechnical specifications forthisoperating stateprovideadequateprotection.

However,certainMCPROperating Limitsforotheroperating statespriorto5,000MWd/MTUandalloperating statesafter5,000MWd/MTUforWNP-2Cycle14mustbeincreased toaccommodate thedefect.Theutilitycurrently projectsthatWNP-2willreach5,000MWd/MTUinearly1999.ABB-CEhasnotifiedtheWashington PublicPowerSupplySystemofthenecessary changestotheWNP-2MCPROperating Limits.TheBISONcodemodelforWNP-2hasbeenrevisedtocorrecttheerror.AllABB-CEBWRfuelusershavebeennotifiedofthiscondition.

(viii)Anyadvicerelatedtothedefectorfailuretocomplyaboutthefacility,

activity, orbasiccomponent thathasbeen,isbeing,orwillbegiventopurchasers orlicensees:

TheWashington PublicPowerSupplySystemhasbeennotifiedofthedefectandhasbeenprovidedwithrevisedMCPROperating LimitsforWNP-2.

Distribution SheetDistri84.txt Priority:

NormalFrom:PatriciaExumActionRecipients:

InerneRemii.ents.

FILECENTER01Copies:PaperCopyExternalRecipients:

NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003686666'1

Subject:

SUMMARYOFJANUARY27,2000MEETINGWITHENERGYNORTHWEST REGARDING THEPROPOSEDSECONDARY CONTAINMENT/STANDBY GASTREATMENT SUBMITTAL.Body:ADAMSDISTRIBUTION NOTIFICATION.

Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML003686666.

DF01-DirectFlowDistribution:

50Docket(PDRAvail)Docket:05000397Page1 ti+g0'Nr*y+~4$'y14******lt't><<fi/Jll]litgOgenre'ICENSEE:

EnergyNorthwest UNITEDSTATESNUCLEARREGULATORY COMMISSION WASHiNGTON,O.C.20555-0001 February15,2000/~~gPg-iIIkcurn+n~gebe<conn~(in4P,dc(enRle.~~FACILITY:

WNP-2

SUBJECT:

SUMMARYOFMEETINGWITHENERGYNORTHWEST REGARDING THEPROPOSEDSECONDARY CONTAINMENT/STANDBY GASTREATMENT SUBMITTAL OnJanuary27,2000,theNuclearRegulatory Commission (NRC)staffmetwithrepresentatives ofEnergyNorthwest todiscusstheupcomingsecondary containment/standby gastreatment licenseamendment submittal.

Theproposedchangeswouldrevisethefollowing:

SR3.6.1.3.10 increases thesecondary containment bypassleakagefrom.74standardcubicfeetperhour(scfh)to.028percent/day approximately 9.4scfh.SR3.6.4.1.1 changetherequirement toverifysecondary containment pressureislessthan.25inchvacuumwatergagetolessthan0inchvacuumwatergage.SR3.6.4.1.4 increasethesecondary containment drawdowntimefrom2minutesto20minutes.TS5.5.7increasethestandbygastreatment systemflowrateto5000cubicfeetperminute(cfm).EnergyNorthwest withdrewasimilaramendment requestinJuly1999,whenthestaffidentified acalculation errorindetermining containment releaseconcentration.

Duetotheextensive reviewrequiredoftheprevioussubmittal, boththestaffandthelicenseefeltthatameetingtodiscusstheupcomingsubmittal wouldbebeneficial inshortening thereviewandavoidingunnecessary requestsforadditional information.

Inordertoimproveefficiency thesameNRCstaffmemberswhowereinvolvedinthefinalreviewforthefirstsubmittal wereatthemeetingandwillreviewthesecondsubmittal.

Enclosure 1isalistofthemeetingparticipants.

Enclosure 2isacopyoftheslidespresented byEnergyNorthwest.

Attheoutsetofthemeeting,Mr.JohnArbuckleofEnergyNorthwest presented anoverviewofthesubmittal.

Theemphasiswasonhowthissubmittal haschangedfromtheprevioussubmittal.

Thissubmittal includesmeteorological dataandatmospheric dispersion calculations (X/Qcalculations).

LetaBrown,oftheNRCstaff,suggested thatitwouldbeusefuliftheX/Qcalculations andanelectronic versionofthemeteorological datawereprovidedforstaffreview.Mr.DavidStudleyofScientech discussed theX/Qcalculations including thefourreleasepointsandthecontrolroomintakes.Thediscussion alsocoveredtheapplication ofARGON96Codeandtheassumptions thatweremade.Thedescription ofthesiteconfiguration andoftheOo@~~It"~48KFiXgfjP"~88C8<ggg

/' ~.~controlroomintakeswereusefultothestaffinunderstanding theassumptions thatweremade.Thestaffexpressed aconcernwiththeventoptionusedintheARCON96Codethatwasusedtocalculate someofthecontrolroomatmospheric dispersion factors.Itwassuggested thatanacceptable solutionwouldbetorecalculate theventruncasesasagroundreleaseoptionusingARGON96.'r.BruceBoyumofEnergyNorthwest discussed theaccidents thatwereanalyzedspecifically, mainsteamlinebreakaccident, fuelhandlingaccident, controlroddropaccidentandloss-of-coolant accident(LOCA).Mr.BoyumstatedthattheLOCAwastheboundingaccident.

Mr.MarkBlumberg,'of theNRCstaff,statedthatitwouldbeusefultoincludethecalculations fortheLOCAanalysisandincludesufficient informatiori onotheraccidents sothatitcanbedetermined thattheLOCAistheboundingaccident.

Mr.Studleydescribed theAxidentCode,whichisthedoseanalysiscodeusedinthesubmittal.

TheAxidentCodemodelsthetransport ofradioactivity totheenvironment andtothecontrolroom.Themajorassumptions andthereasonsforthemwerediscussed.

Mr.Boyumalsodiscussed thereleasepathwaysincluding theuseoftheGothicCodetojustifythe40percentmixingassumedinsecondary containment.

Mr.RichardLobel,oftheNRCstaff,saidtheproposedsubmittal shouldincludeadescription ofthederivation anduseoftheflowequationwhichisthebasisforFigure4ofAttachment 2tothelicensee's October15,1996,submittal.

Inaddition, thestaffmayrequestinputusedinreactorbuildingpressuredrawdowncalculations sothatthestaffmayperformindependent calculations.

Afinaldecisionhasnotbeenmade.Mr.Boyumthendiscussed controlroomairflowsandunfiltered controlroomin-leakage.

Mr.Blumbergstatedthatlicensees havehadtoverifytheirunfiltered in-leakage assumptions.

TheASTME741,"Standard TestMethodsforDetermining AirChangeinaSingleZonebyMeansofaTracerGasDilution,"

testmethodisacceptable tothestaffasaverification testforunfiltered in-leakage.

Thelicenseecoulddescribetheirdesignandproposeanalternative testmethodthatwouldhavetobereviewedandapprovedbythestaff.TheNRCstafffeltthatEnergyNorthwest didagoodjobexplaining theirsubmittal andthattheywerereceptive tosuggestions fromthestaff.DocketNo.50-397

Enclosures:

1~ListofMeetingParticipants 2.EnergyNothwestSlidesccw/encls:SeenextpageE-MailJZwolinski/SBlack SRichardsDLange,EDOEPeytonRLobelMBlumberg LBrownLSmith,RIVJackGushing,ProjectManager,Section2ProjectDirectorate IV8Decomissioning DivisionofLicensing ProjectManagement OfficeofNuclearReactorRegulation DISTRIBUTION:

'HardCoCentralFilePUBLICPDIV-2R/FJCushingOGCACRSOFFICEPDIV-2/PM CPDIV-2/LA NAMEDATEJcushing:Icc EPeytoncBII"ffOoFFICIALRECORDCOPYDOCUMENTNAME:GAPDIV-2EWNP2iMTS12700.

rcewecIU(e,IIuxPDIV-2/SC SDembe"f~=/t//r.'/'=~

'/~6hzQg~

0 controlroomintakeswereusefultothestaffinunderstanding theassumptions thatweremade.Thestaffexpressed aconcernwiththeventoptionusedintheARCON96Codethatwasusedtocalculate someofthecontrolroomatmospheric dispersion factors.Itwassuggested thatanacceptable solutionwouldbetorecalculate theventruncasesasagroundreleaseoptionusingARGON96.Mr.BruceBoyumofEnergyNorthwest discussed theaccidents thatwereanalyzedspecifically, mainsteamlinebreakaccident, fuelhandlingaccident, controlroddropaccidentandloss-of-coolant accident(LOCA).Mr.BoyumstatedthattheLOCAwastheboundingaccident.

Mr.MarkBlumberg, oftheNRCstaff,statedthatit,wouldbeusefultoincludethecalculations fortheLOCAanalysisandincludesufficient information onotheraccidents sothatitcanbedetermined thattheLOCAistheboundingaccident.

Mr.Studleydescribed theAxidentCode,whichisthedoseanalysiscodeusedinthesubmittal.

TheAxidentCodemodelsthetransport ofradioactivity totheenvironment andtothecontrolroom.Themajorassumptions andthereasonsforthemwerediscussed.

Mr.Boyumalsodiscussed thereleasepathwaysincluding theuseoftheGothicCodetojustifythe40percentmixingassumedinsecondary containment.

Mr.RichardLobel,oftheNRCstaff,saidtheproposedsubmittal shouldincludeadescription ofthederivation anduseoftheflowequationwhichisthebasisforFigure4ofAttachment 2tothelicensee's October15,1996,submittal.

Inaddition, thestaffmayrequestinputusedinreactorbuildingpressuredrawdowncalculations sothatthestaffmayperformindependent calculations.

Afinaldecisionhasnotbeenmade.Mr.Boyumthendiscussed controlroomairflowsandunfiltered controlroomin-leakage.

Mr.Blumbergstatedthatlicensees havehadtoverifytheirunfiltered in-leakage assumptions.

TheASTME741,"Standard TestMethodsforDetermining AirChangeinaSingleZonebyMeansofaTracerGasDilution,"

testmethodisacceptable tothestaffasaverification testforunfiltered in-leakage.

Thelicenseecoulddescribetheirdesignandproposeanalternative testmethodthatwouldhavetobereviewedandapprovedbythestaff.TheNRCstafffeltthatEnergyNorthwest didagoodjobexplaining theirsubmittal andthattheywerereceptive tosuggestions fromthestaff.JackGushing,ProjectManager,Section2ProjectDirectorate IV8Decomissioning DivisionofLicensing ProjectManagement OfficeofNuclearReactorRegulation DocketNo.50-397

Enclosures:

1.ListofMeetingParticipants 2.Licensee's Slidesccw/encls:Seenextpage ylC WNP-2CC:Mr.GregO.Smith(MailDrop927M)VicePresident, Generation EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 Mr.AlbertE.Mouncer(MailDrop1396)ChiefCounselEnergyNorthwest P.O.Box968Richland, Washington 99352-0968 Ms.DeborahJ.Ross,ChairmanEnergyFacilitySiteEvaluation CouncilP.'.Box43172Olympia,Washington 98504-3172 Mr.D.W.Coleman(MailDropPE20)Manager,Regulatory AffairsEnergyNorthwest P.O.Box968Richland, Washington 99352-0968 Mr.PaulInserra(MailDropPE20)Manager,Licensing EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 RegionalAdministrator, RegionIVU.S.NuclearRegulatory Commission

,HarrisTower8Pavilion611RyanPlazaDrive,Suite400Arlington, Texas76011-8064 ChairmanBentonCountyBoardofCommissioners P.O.Box69Prosser,Washington 99350-0190 SeniorResidentInspector U.S.NuclearRegulatory Commission P.O.Box69Richland, Washington 99352-0069 Mr.RodneyL.Webring(MailDropPE08)VicePresident, Operations Support/PIO EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 ThomasC.Poindexter, Esq.Winston&Strawn1400LStreet,N.W.Washington, DC20005-3502 Mr.BobNicholsExecutive PolicyDivisionOfficeoftheGovernorP.O.Box43113Olympia,Washington 98504-3113 Mr.J.V.ParrishChiefExecutive OfficerEnergyNorthwest P.O.Box968(MailDrop1023)Richland, WA99352-0968 ENERGYNORTHWEST MEETINGPARTICIPANTS JANUARY272000ENERGYNORTHWEST DouglasColemanBruceBoyumJohnBekahaziLindaWoolsleyJohnArbuckleSCIENTECH-NUS DavidStudleyNRCJackGushingSteveDembekMarkBlumbergRichardLobelLetaBrownEnclosure 1

ENERGYNORTHWEST Secondary Containment/SGT Submittal Presentation AIntroduction (JohnArbuckle)

Meteorological DataAndX/QCalculations (JohnArbuckleandDaveStudley)DoseAnalysisAndResults(BruceBoyumandDaveStudley)Summary(BruceBoyum)Enclosure 2

INTRODUCTION InitialProblemSubmittal HistoryAnalysisProblem/TS Retraction/JCO-FAO ImpactComparison ofKeySGTParameters Technical Specification ChangesSubmittal Content INITIALPROBLEMUnderCertainPost-Accident Meteorological Conditions, WNP-2couldnotDevelop0.25-inch NegativeDifferential PressureWithin120SecondsTherefore, aRevisedDesignBasisandDoseAnalysiswasProvided.

JCO(FAO)PreparedandSubmitted toStaff.

SUBMITTALHISTORY~October1996Technical Specification.

Amendment RequestDecember1997-June1999FormallyResponded toThreeRAls

ANALYSISPROBLEMAnalysisProblem/TS Retraction/JCO-FAO ImpactJul1999WithdrewTechnical Amendment Request-Discovery ofaNonconservative ErrorinDetermining Containment ReleaseConcentration DuringResolution ofProposedRAI4NoImpactonJCO-FAO,CurrentDesignBasis,Technical Specifications orRecentAnalyses COMPARISON OFKEYSGTPARAMETERS 2minutes2240cfm4457cfmOriginalKeParameter DesinDrawdownTimeSCLeakageSGTFlowCurrentDesinJCO-FAO10minutes1475cfm5385-5850cfmProposedDesin20minutes2240cfm5000cfm l,1 TECHNICAL SPECIFICATIONSProposedTechnical Specification ChangesSR3.6.1.3.10 SR3.6.4.1.1 SR3.6.4.14IncreaseSecondary Containment BypassLeakagefrom0.74scfhto(0.028%/day)

<~<9.4scfh)ChangetheSurveillance Requirement toVerifyEvery24HoursthatthePressureWithinSecondary Containment is(0inch(vs0.25inch)c~-'-',,ofVacuumWaterGaugeIncreaseSecondary Containment DrawdownTimefrom120secondsto20minutes5.5.7.2.A IncreaseStandbyGasTreatment SystemFlowRatefrom4457cfmto5000cfm SUBMITTALCONTENTDetailedHistory-Supersedes PreviousSubmiitals Responses toRAlsIncorporated DesignBasisMeteorology andX/QValuey>,,rii."'itAccidents Analyzed-LOCAinDetail,FHA,MSLBandCRDAGOTHICModelandBenchmarking EffortsDiscussion ofStandbyGasTreatment SystemEvaluation ofSignificant HazardsEnvironmental Considerations Evaluation

~-Marked-Up andTypedTechnical Specifications Marked-Up Technical Specification Bases-ForInfoOnly I

METEOROLOGICAL DATAANDXlQCALCULATIONS Description ofMetTower,Terrain,andInstrumentation DataUsed(6yrs)ARCON961.Description ofReleasePointsandControlRoomlntakes2.Application ofARCON96atWNP-23.Comparison WithJCO-FAOandPowerUprate DESCRIPTION OFMETTOWER,TERRAIN,ANDINSTRUMENTATION Meteorological TowerConsistsofa240-ftStructure witha5-ftExtension MastTheTowerisTriangular inShapeandofOpenLatticeConstruction toMinimizeTowerInterference withMeteorological Measurements WindSpeedandDirection isMonitored bySeparateChannelsatthe33-ftand245-ftElevations ASingleChannelProvidesAirTemperature Difference Between33-ftand245-ftElevations

DESCRIPTION OFMETTOWER,TERRAIN,ANDINSTRUMENTATION SitingofInstrumentation withRespecttoMeteorological TowerandSurrounding Vegetation isVeryGoodTheBaseoftheTowerMaintained asNaturalVegetation AreaAroundtheTowerisOpenTerrainwithnoNaturalorMan-MadeObstructions toImpactDataBeingCollected

DATAUSED(6YRS)Site-specific Meteorological (Temperature 8WindSpeed)DatawereusedforaSix-yearSpanfromJanuary1,1984,toJanuary1,1990ACorresponding Calculation WasPerformed andaCurvewasGenerated whichEncompasses aMinimumof96.1PercentofallWNP-2WeatherConditions DataCheckedforReasonableness TheCurveExcludesApproximately FourPercentasaConservative Approximation of95'/0/5'/o llF DATAUSED(6YRS)WinterCasesYieldedLongerDrawdownTimesthanSummerCasesLimitingCaseVeryConservative

-Atmospheric Temperature of0'F,noWind,StandbyServiceWaterSystemSprayPondTemperature 77'F,Division2Electrical Power(i.e.,Division1NotinOperation),

OneTrainofStandbyGasTreatment SysteminOperation, and50%RoomCoolerEfficiency CaseResultedinaDrawdownTimeof711Seconds(11.85Minutes)

JC, DATAUSED(6YRS)ZeroWindSpeedandZeroDegreesTemperature.

usedBecauseTemperature ImpactonDifferential PressureisProminent Factor,duetotheHigherDifferential Temperature BetweenInsideandOutsideTemperatures (9

X/QCALCULATIONS

.rVy4waaARCON961.Description ofReleasePointsandControlRoomintakes2.Application ofARCON96atWNP-23.Comparison withJCO-FAOandPowerUprate X/QCALCULATIONS ARCON96ARCQN96usedtoDetermine X/QvaluesforThreeControlRoomlntakesandFourReleasePointsUtilizedtheSameTimePeriod/plant SpecificDataasUsedintheDrawdownAnalysisCRIntakes-LocalandTwoRemoteIntakes

'~I'~l::.-~NQCALCULATIONS eReleasePointsConsidered

.TurbineBuildingWalls-ReleasefromTurbineBuildingWallstobeUsedwithEventssuchasCRDAsReactorBuildingWalls-ReleasefromReactorBuildingWallstobeUsedDuringDrawdownPeriodandSecondary BypassLeakageReactorBuildingRoofline(Stack)Release-VentReleasefromReactorBuildingRoofUsedforSGTSReleasesReactorBuilding(KingKong)Doors-ReleasefromReactorBuildingGradeArea X/QCALCULATIONS

-ARCON96-SITECONFIGURATION SEENEXTSLIDE X/QCalculations

-ARCON96-SiteConfiguration Intake¹11589W,1229442flMSLReactorBldgRoofline1243.5W,11918N671ftMSLKKDoors1176W,11778N441ftMSLTtttoNorthSitoNorth12300ftN12200TurbineBldgWallSourcesCRIntake1467W,11883N528ftMSLRoofElevation 457MSL57SMSL,TurbineBldg,545tSL66ShtSLReactorBldg.506542MSLhtL12100120001190011800ReactorBldgWallSourcesIntake¹21025W,11565442ftMSL160015001400474MSLPtaatGrado.441MSL130020011001170011600115001000ftW X/QCALCULATIONS Application ofARGON96AnalyzedeachofthefourReleasePathsforeachoftheThreeIntakes(i.e.,12Scenarios)

Analyzedall12Scenarios forall6YearsTheMaximumValueofthe6YearswasChosenforeachTimePeriod(i.e.,notjusttheMaximumYearbuttheMaximumValueeachTimeStep)LocalIntakenotUsedforLOCAduetothePresenceofanAutomatic Isolation Signal X/QCALCULATIONS A.Application ofARCON96Between0to3Hours,noCreditforOperatorAction-psedAverageofthetwoRemotelntakes~>--"~"From3Hourstothe30Days,CreditforOperatorAction-Usedthe.LowerofthetwoX/QsCalculated fortheRemoteIntakes~@',z

-q",VeryConservative Treatment

-WiththePresenceoftwoRemote'"""c"Intakes,thePlantwillbeabletoSwitchtotheUpwindIntakeandinEffectPrecludetheIntroduction ofActivityDuringtheAccident X/QCALCULATIONS SEENEXTSLIDE I1 NQCalculations ARCON96ResultsandComparison withOriginalCRNQsforUFSARTimePeriodGroundReleaseNQCalculated withARGON96s/m'QUsedforUFSARAnalysisRatioofARGON96Values/m'oUFSARValue0-2hr2-3hr3-8hr8-24hr1-4das4-30dasSGTSRelease0-2hr2-3hr3-8hr8-24hr1-4das4-30das9.94E-59.91E-57.16E-54.37E-52.35E-5~1.56E-52.54E-4'j.70E-48.15E-53.20E-52.26E-51.90E-52.17E-45.43E-54.49E-53.55E-51.67E-51.67E-53.77E-49.43E-57.80E-56.17E-52.90E-52.90E-545.81%182.50%159.47%123.10%140.72%934167.37%180.28%104.49%51.86%7793%65.52%

DOSEANALYSISANDRESULTSAccidents AnalyzedforRadiological Consequences AXIDENTCode1.HowApplied2.WhereusedBeforeSummaryofLOCAMajorAssumptions ChangesfromOriginalDesignandPreviousSubmittal LOCAResults ACCIDENTS ANALYZEDMainSteamLineBreak(MSLB)FuelHandlingAccident(FHA)ControlRodDropAccident(CRDA)LossOfCoolantAccident(LOCA) 11 AXIDENTCODE~fDoseAnalysisCode-Radiological Consequences oftheSpectrumofDesignBasisAccidents wereAnalyzedusingtheSCIENTECH-NUS AXIDENTCodeCodeDescription

-AXIDENTModelstheTransport ofRadioactivity totheEnvironment andtotheControlRoom.This.CodeIncludesthetimeDependent EffectsofContainment Sprays,Recirculation, PurgeandIntakeFilters,Atmospheric Dispersion, NaturalDecay,etc.TheCodeisBasedontheExplicitSolutionoftheIntegrated ActivityinaReceptorVolume.

AXIDENTCODEIndustryExperience/Usage oftheAXIDENTCode-Developed intheearly70'stoSupporttheLicensing andLicensing ReviewsofbothU.S.andinternational Commercial NuclearPowerPlants.Developed tofilltheVoidinCodesAvailable toAssesstheEmergingIssueatthetime-ControlRoomHabitability.

GenerallndustUsae~UsedtoSupportLicensing Submittals inthe70'sUsedforaNumberofPlantsinSupportofthePost-TMIActionItem~UsedThroughout the80'sand90'stoResolveControlRoomHabitability andAccidentAnalysesIssues

AXIDENTCODESCIENTECH Experience Successfully Benchmarked thePreviousResultsGenerated byotherCodeswhichComputetheIntegrated/exact Solution(i.e.,Bechtel's LOCADOSEandS&L'sPostDBA)OvertheYears,Thousands ofCaseshavebeenrunontheAXIDENTCode.InallCases,theResultshaveTrendedasExpected.

TheResultshavealsoConsistently beeninCloseAgreement withtheSteadyStateMurphy/Campe Equations.

SI AXIDENTCODERecentCalculations Submitted totheNRCInclude:ControlRoomandOffsiteDoseCalculations toSupporttheFPCCrystalRiverRestartCRDAandMSLBAnalysesfortheCPLLBrunswick Station's PowerUprateEffortReanalysis EffortfortheCooperStation-PendingReview III<<e~I~i~'~~~II'Y/////III~~~~Ir~Ie C

CONTROLROOMAIRFLOWSAirintake1100cfmFilterUnit:95%effElemental andOrganic99%eff.Particulate ControlRoom(CR)CRTotalVolume,2.0E5ft'xitFlow.~1110.55cfmUnfiltered Infiltration 8cin~ass/egress 10.55c6n MAJORASSUMPTIONS

)~AXIDENTCodeusedforDoseAnalysisSourceTermReleasePerTID-14844 (102%PowerLevel)100/0NobleGases-25%Halogens(50%ESFLeakage)91%Elemental 5%Particulate 4%OrganicDoseConversion FactorsinAccordance withICRP30 MAJORASSUMPTIONS Instantaneous MixinginPrimaryContainment ReleasefromContainment of.5'/oiday Total.32/o/day Containment Leakage-.18'/o/day MSIVLeakageNoSuppression PoolScrubbing Credited MAJORASSUMPTIONS SGTFilterEfficiency

--99%Efficient forHalogens0%Efficient forNobleGases.SGT.Flow:5000cfmSingleTrain50cfmBypassLeakageControlRoomFilterEfficiency 95%Efficient forElemental andOrganiciodine99%Efficient forParticulate iodine 7I MAJORASSUMPTIONS Secondary Containment DrawdownTimeof20MinutesDuringDrawdownTime:-NoSGTFiltration Credited-Secondary Containment LeakageataRateof1Volume/day 40%MixinginSecondary Containment forEntireScenario MAJORASSUMPTIONS gl~PESFLeakageIntoSecondary Containment:

--1gpm-10%FlashingFraction-50%CoreIodineSourceTermControlRoomUnfiltered Inleakage:

10scfmIngress/egress

.55scfmInfiltration Secondary Containment BypassLeakageof.028%/day (9.4scfh)NewX/QValues DOSEANALYSISMETHODOLOGY MAJORCHANGES'~ITEMDrawdownTimeSec.CtmtMixingESFLeakageSGTFilterBypassBypassLeakage(%Day)CURRENTDESIGN5MinNone14cfm.00209PREVIOUSSUBMITTAL 20Min40%Vol.None14cfm054*'cj~PROPOSEDDESIGN20Min40%Vol.1GPM.50cfm.028r4, LOCAANALYSISRESULTSCRWholeBodyGRThyroidGRBetaCALC.~REM0.428.16.8.LlMIT~REM53030EABWholeBodyEABThyroid3.756.625300LPZWholeBodyLPZThyroid3.413125300 4

ELOCADOSEBYPATHERELEASEPATHCONTROLROOMLPZTHYROIDW.BODYTHYROIDW.BODYSec.CtmtBypassSec.CtmtLeakage21.02.028E-51Q10.20.54E-3Sec.CtmtSGTRel.4.2ESF.Leakage Sec.Ctmt0.3.161E-51.21.22E-3MSIVLeakageTOTAL3.028.1.1804131311.734 CONTAINMENT RELEASEIMPACT(.04%1day SecCtmtBypassLeakage)RELEASEPATHCRTHYROIDDOSE(REM).32'/o/DAY

.5'/o/DAY SecCtmtBypassSecCtmtLeakageSecCtmtSGTRel.ESFLeak(SecCtmt)MSIVLeakageTOTAL.024.20.33.036.9.030.33.039.2 t~4I,00~I EFFECTOFRELEASEELEVATION DESCRIPTION GroundRelease=100%RooflineRelease=0/0GroundRelease=60'/0RooflineRelease=40'/0GroundRelease=50'/0RooflineRelease=50'/0DOSEREM39.239.639.7GroundRelease=0'/0RooflineRelease=100%39.2BasedonThyroidDoseinControlRoomAssuming.5'/0/day Containment Leakageand.04%/daySecondary Containment Bypass EFFECTOFSGTFLOWRATEDESCRIPTION 4Kcfmfor30DaysDOSE(REM)THYROIDW.BODY37.3.3575Kcfmfor30Days10Kcfmfor30Days(20MinDrawdn)10Kcfmfor30Days(10MinDrawdn)10Kcfmfor1HrThen4K36.937.3.369A09.409.362cfm30DaysBasedOn.32%/dayCtmtLeakageand.04%/daySecCtmtBypassLeakage SUMMARYDoseAnalysisMeets10CFR50and10CFR100LimitsNoHardwareChangesNecessary BeyondThoseCompleted in-SupportoftheJCO-FAOTechSpecSubmittal tobeMade.inFebruaryFSARChangeswillbeImplemented Following ApprovalofTechSpecSubmittal FSARChangesInclude:-.AccidentAnalysisandDosesControlRoomHabitability Analysis~Secondary Containment Description

-Description ofSGTSandREAJCO-FAOwillbeClosedFollowing ApprovalofTechSpecSubmittal le'g.

qRC~OC~+4Cy4V00Cy+n~OUNITEDSTATESNUCLEARREGULATORY COMMISSION REGIONIV611RYANPLAZADRIVE,SUITE400ARLINGTON, TEXAS76011-8064 NOVl5I999Mr.J.V.Parrish(MailDrop1023)ChiefExecutive OfficerEnergyNorthwest P.O.Box968Richland, Washington 99352-0968

SUBJECT:

INVITATION TODISCUSSION OFPILOTPROGRAMRESULTS

DearMr.Parrtsh:

OnMay30,1999,weinitiated apilotoftherisk-informed baselineinspection programatCooperNuclearStationandFortCalhounStation.Thepilotprogramisscheduled toendNovember27.OnDecember1,1999,theNRCwillmeetwithOmahaPublicPowerDistrictandNebraskaPublicPowerDistricttodiscusstheirperceptions andlessonslearnedgatheredduringthepilotprogram.Youwillfindthedetailsofthemeetingdocumented intheenclosedmeetingnotice.AlthoughthemeetingisbetweentheNRCandmembersofthepilotplantstaffs,wewillbediscussing topicsthatmaybeofinteresttoyourorganization.

Thismeetingwillbeopentopublicobservation.

Following themeeting,thediscussion willbeopenedforcommentsandquestions fromobservers.

Wewouldentertain andwelcomeyourparticipation atthattime.Shouldyouhaveanyquestions onthisinspection plan,pleasecontactCharlesMarschall at~(817)860-8185orDavidLovelessat(817)860-8161.Sincerely, gals'@zPdK CharlesS.Marschall, ChiefProject'Branch CDivisionofReactorProjectsDocketNo.:50-397LicenseNo.:NPF-21

Enclosure:

AsStated

EnergyNorthwest ccw/enclosure:

ChairmanEnergyFacilitySiteEvaluation CouncilP.O.Box43172Olympia,Washington 98504-3172 RodneyL.Webring(MailDropPE08)VicePresident, Operations Support/PIO EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 GregO.Smith(MailDrop927M)VicePresident, Generation EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 D.W.Coleman(MailDropPE20)Manager,Regulatory AffairsEnergyNorthwest P.O.Box968Richland, Washington 99352-0968 AlbertE.Mouncer(MailDrop1396)GeneralCounselEnergyNorthwest P.O.Box968Richland, Washington 99352-0968 PaulInserra(MailDropPE20)Manager,Licensing

.EnergyNorthwest P.O.Box968Richland, Washington 99352-0968 PerryD.Robinson, Esq.Winston8Strawn1400LStreet,N.W.Washington, D.C.20005-3502 BobNicholsStateLiaisonOfficerExecutive PolicyDivisionOfficeoftheGovernorP.O.Box43113Olympia,Washington 98504-3113 EnergyNorthwest bcctoDCD(IE45)-3-bccdistrib.byRIVwenclosure:

BranchChief(DRP/E)ProjectEngineer(DRP/E)bccdistrib.w/oenclosure:

RegionalAdministrator DRPDirectorDRSDirector-BranchChief(DRP/TSS)

ResidentInspector RIVFileRITSCoordinator DOCUMENTNAME:R:QWN2>mn12-1.wpd Torecelvecopyofdocurnent, Indicateinbox:"C"

=Copwithoutenclosures "E"=Copwithenclosures "N"~NocopyRIV'C:DRP/C CSMarschall;vlh 11/15/99OFFICIALRECORDCOPY

%+8RecuC~+~~oCyAA0cOlCy+gO~>>*++UNITEDSTATESNUCLEARREGULATORY COMMISSION REGIONIV611RYANPLAZADRIVE,SUITE400ARLINGTON, TEXAS76011-8064 November15,1999NOTICEOFLICENSEEMEETINGNameofLicensee:

NameofFacility:

Docket:DateandTimeofMeeting:LocationofMeeting:PurposeofMeeting:NRCAttendees:

LicenseeAttendees:

NebraskaPublicPowerDistrictOmahaPublicPowerDistrictCooperNuclearStationFortCalhounStation50-28550-298December1,19991-3p.m.(CDT)FortCalhounStationAuditorium Hwy.75-NorthofFortCalhounFortCalhoun,NebraskaDiscussion ofthelicensee's perceptions andlessonslearnedfromthepilotinspection programK.Brockman,

Director, DivisionofReactorProjectsC.Marschall, Chief,BranchC,DivisionofReactorProjectsA.Madison,Transition TaskForceLeader,OfficeofNuclearReactor'Regulation W.Jones',SeniorReactorAnalyst,DivisionofReactorSafetyL.Wharton,FCSProjectManager,OfficeofNuclearReactorRegulation L.Burkhart, CNSProjectManager,OfficeofNuclearReactorRegulation D.Loveless, SeniorProjectEngineer, BranchC,DivisionofReactorProjectsW.GaryGates,VicePresident, FortCalhounStationS.Gambhir,DivisionManager,NuclearOperations J.Chase,.Division Manager,NuclearAssessments M.Tesar,Division, Manager,NuclearSupportServicesR.Phelps,DivisionManager,NuclearEngineering J.Solymossy, Manager,FortCalhounStationM.Frans,Manager,NuclearLicensing R.Jaworski, Manager,RevisedReactorOversight ProjectB.Hansher,Supervisor, Station,Licensing NebraskaPublicPowerDistrictOmahaPublicPowerDistrict-2-H.Hackerott, Supervisor, SystemsAnalysisJ.McDonatd, PlantManager,CooperNuclearStationP.Caudill,GeneralManager,Technical ServicesG.Smith,NuclearProjectsManagerJ.Sumpter,Licensing Supervisor D.Robinson, QAAssessment ManagerR.Wachowiak, RiskManagement Supervisor NOTE:(1)Thismeetingisopentoattendance bymembersofthegeneralpublic.(2)NRCpersonnel, notlistedabove,thatdesiretoattendthismeetingshouldnotifyC.S.Marschall at817/860-8185 byCOBonNovember19,1999.(3)Acommentsessionwillbeconducted attheendofthemeetingforparticipation ofallRegionIVoperating reactorlicensees.

~nApprovedBy:CharlesS~Marschall, ChiefProjectBranchCDivisionofReactorProjectsCC:G.R.Horn,SeniorVicePresident ofEnergySupplyNebraskaPublicPowerDistrict141415thStreetColumbus, Nebraska68601JohnR.McPhail,GeneralCounselNebraskaPublicPowerDistrictP.O.Box499Columbus, Nebraska68602-0499 B.L.Houston,NuclearLicensing andSafetyManagerNebraskaPublicPowerDistrictP.O.Box98Brownville, Nebraska68321 NebraskaPublicPowerDistrictOmahaPublicPowerDistrict-3-Dr.WilliamD.LeechManager-NuclearMidAmerican Energy-907WalnutStreetP.O.Box657DesMoines,Iowa50303-0657 RonStoddardLincolnElectricSystem10400StreetP.O.Box80869Lincoln,Nebraska68501-0869 MichaelJ.Linder,DirectorNebraskaDepartment ofEnvironmental QualityP.O.Box98922Lincoln,Nebraska68509-8922 ChairmanNemahaCountyBoardofCommissioners NemahaCountyCourthouse 1824NStreetAuburn,Nebraska68305CherylK.Rogers,ProgramManagerNebraskaHealthandHumanServicesSystemDivisionofPublicHealthAssurance ConsumerServicesSection301,Centennial Mall,SouthP.O.Box95007Lincoln,Nebraska68509-5007 RonaldA.Kucera,DirectorofIntergovernmental Cooperation Department ofNaturalResources P.O.Box176Jefferson City,Missouri65102JerryUhlmann,DirectorStateEmergency Management AgencyP:O.Box116Jefferson City,Missouri65101 NebraskaPublicPowerDistrict.OmahaPublicPowerDistrict-4-VickL.Cooper,ChiefRadiation ControlProgram,RCPKansasDepartment ofHealthandEnvironment BureauofAirandRadiation ForbesFieldBuilding283Topeka,Kansas66620MarkT.Frans,ManagerNuclearLicensing OmahaPublicPowerDistrictFortCalhounStationFC-2-4Adm.~P.O.Box399Hwy.75-NorthofFortCalhounFortCalhoun,Nebraska68023-0399 JamesW.Chase,DivisionManagerNuclearAssessments FortCalhounStationP.O.Box399FortCalhoun,Nebraska68023J.M.Solymossy, Manager-FortCalhounStationOmahaPublicPowerDistrictFortCalhounStationFC-1-1PlantP.O.Box399Hwy.75-NorthofFortCalhounFortCalhoun,Nebraska68023PerryD.Robinson, Esq.Winston8Strawn1400L.Street,N.W.Washington, D.C.20005-3502 ChairmanWashington CountyBoardofSupervisors Washington CountyCourthouse P.O.Box466Blair,Nebraska68008CherylK.Rogers,ProgramManagerNebraskaHealthand-Human ServicesSystemDivisionofPublicHealthAssurance ConsumerServicesSection301Centennial Mall,SouthP.O.Box95007Lincoln,Nebraska68509-5007 0C NebraskaPublicPowerDistrictOmahaPublicPowerDistrict-5-bcc:DMB(IE45)OEDORIVCoordinator (16E15)ORAFileRIVFileE-MailTo:()PMNSPABFJMBWSBAB2LJBLRWOEMAILWCWJACCAHGFSBWH'AC1,CJGLAT,DLF,LJB1CLG,LMB,NLHCMS,JAK,NSLPDPLPLNRCAttendees MtgAnnouncement Coordinator DEDRA/D/NRRActing,ADT/NRRActingADP/NRRL.Burkhart, ProjectManager,NRRR.Wharton,ProjectManager,NRRD/OEW.Walker,SeniorResidentInspector J.Clark,SeniorResidentInspector C.Hackney,RSLOG.Sanborn,EOB.Henderson, PAORASecretaries DRPDivisionDRSDivisionDNMSDivisionDeanPapaP.LongdoDOCUMENTNAME:R:QCNS<CN12-1'MN.DRP andR:QFCS>FC12-1 MN.DRPToreceivecoofdocument, IndicateInbox:"C"=Cowithoutenclosures "E"=Cowithenclosures N"=NocoRIV:DRP/CCCSMarschall:vlh11/15/99RSLOPAOCCAHackne11/15/99BWHenderson 11/15/99OFFICIALRECORDCOPY Distri89.txt Distribution SheetPriority:

NormalFrom:Esperanza LomosbogActionRecipients:

NRR/DLPM/LPD4-2 NRR/DLPM/LPD4-1 LRWhartonLBurkhartJCushingInternalRecipients:

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Subject:

SummaryofSignificant MeetingwithLicensee(Part50)Body:PDRADOCK05000397PDocket:05000285, Notes:N/ADocket:05000298, Notes:N/ADocket:05000397, Notes:N/APage1