ML17292B689

Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl

ML17292B689
Person / Time
Site:	Columbia
Issue date:	06/03/1999
From:	PARRISH J V WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
G02-99-102, G2-99-102, NUDOCS 9906140098
Download: ML17292B689 (124)

Text

CATEGORYREGULAYINFORMATION DISTRIBUTIO

.SYSTEM(RIDS)ACCESSION NBR:9906140098 DOC.DATE:

99/06/03NOTARIZED:

YESSCIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPoweP2JTH.MAMAAUTHORAFFILIATION PARRXSH,J,V.

Washington PublicPowerSupplySystemRECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)DOCKETI05000397

SUBJECT:

Application foramendtolicenseNPF-2l,reflecting changeinnameofWashington PublicPowerSupplySystoEnergyNorthwest.

MarkedupcopyofaffectedpagesofOLforplant,encl.DISTRIBUTION CODE..ROOIDCOPIESRECEIVED..LTR IENCLTITLE:ORSubmittal:

GeneralDistribution NOTES:SIZE:I7ERECIPIENT IDCODE/NAME LPD4-2LACUSHING,J COPIESLTTRENCL1111RECIPIENT IDCODE/NAME LPD4-2PDCOPXESLTTRENCL11INTERNAL:

ACRSNRR/DE/EEIB NRR/DE/EMEB NRR/DSSA/SRXB NiJDOCS-ABSTRACT EXTERNAL:

NOAC1~FILECENTER001' NRR/DE/EMCB 1NRR/DSSA/SPLB 1NRR/SPSBJUNG,I1OGC/RP11NRCPDR111111111011D'ENNOTETOALLNRIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:

LTTR15ENCL14 Att WASHINGTON PUBLICPOWERSUPPLYSYSTEMPO.Box968~Richland, Washington 99352-0968 June3,1999G02-99-102 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Gentlemen:

Subject:

WNP-2OPERATING LICENSENPF-21REQUESTI<ORAMENDMENT LICENSEENAMECHANGEPursuantto10CFR50.90,thislettertransmits anoperating licenseamendment requestfortheWNP-2OperatingLicense (OL).Itisrequested thatanamendment bemadetoupdatetheOLsuchthatthenameofthelicensee"Washington PublicPowerSupplySystem"ischangedto"EnergyNorthwest."

TheneedforthisrequestresultsfromthechangeinthenameoftheWashington PublicPowerSupplySystemtoEnergyNorthwest.

NoimpactonthestatusoftheOLorthecontinued operation ofWNP-2isforeseen, sincethisrequestcontainsaproposedchangethatissolelyadministrative innature.Theattachments tothisletterareasfollows:Attachment 1providesadescription oftheproposedchange.Attachment 2documents, pursuantto10CPR50.92,thedetermination thattheproposedamendment containsNoSignificant HazardsConsiderations.

Attachment 3provides, pursuantto10CPR51.22(c)(9) and(10),thebasisforthecategorical jexclusion fromperforming anEnvironmental Assessment/Impact Statement.

tAttachment 4providesamarkedupcopyoftheaffectedpagesoftheOLforWNP-2.90bie0098

~90mPDRADOCK05000397,',>

PPDR+)It,>raQ REQUESTFORAMX<NTLICENSEENAMECHANGPage2Thisamendment requesthasbeenreviewedbytheCorporate NuclearSafetyReviewBoardandapprovedbytheWNP-2PlantOperations Committee.

Inaccordance with10CFR50.91,theStateofWashington hasbeenprovidedacopyofthisletter.Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecontactMr.PJInserraat(509)377-4147.

Respectfully, ParrishhiefExecutive OQicerMailDrop1023Attachments:

asstatedcc:EWMerschofF-NRCRIVJSCushing-NRRNRCSr.ResidentInspector

-927NDLWilliams-BPA/1399PDRobinsonWinstonEcStrawnDJRoss-EFSEC

STATEOFWASHINGTO

))COUNTYOFBENTON)

Subject:

equestForAmendment NameChangeI,J.V.PARRISH,beingdulysworn,subscribe toandsaythatIamtheChiefExecutive OfficerforENERGYNORTHWEST, theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.DATE,1999J.VarrishChiefExecutive OfficerOnthisdatepersonally appearedbeforemeJ.V.PARRISH,tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledged thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.

GIVENundermyhandandsealthis~rWdayofM~n~1999.=+@AD+ag~.."cd>Q:..+~]:y+pfARYfo:.puB~FW0&~~%xvi~NPublicinandfortheSTAOFWASHINGTON ResidingatkMyCommission Expires'IoSoQ ATTACHMENT 1REQUESTFORAMENDMENT XXCENSEENAMECHANGEDescription ofProposedChange Lail>"~ay~WviQ REQUESTEORAMENDMENT LICENSEENAMECHANG%Attachment 1Page1of,1DESCRIPTION OFPROPOSEDCHANGE~ddhWiththissubmittal, theNRCisbeingrequested toreplacereferences tothenameWashington PublicPowerSupplySystem,withreferences tothenameEnergyNorthwest inallapplicable locations oftheOperating License(OL)forWNP-2.Currently, theOLstatesthatWashington PublicPowerSupplySystemistheNRClicensee.

ThisrequestalsoappliestoAppendixA(Technical Specifications) andAppendixB(Environmental Protection Plan)totheOL.TheOperating LicensenumberforWNP-2isNPF-21.Similarly, inanypendingapplications orlicenseamendments-heretofore submitted byWashington-PublicPowerSupplySystem,butnotyetacteduponbytheNRC,references toWashington PublicPowerSupplySystem,shouldalsobereplacedbyEnergyNorthwest.

Thisadministrative namechangewillalsobereflected infuturecorrespondence withtheNRC.Discussion Theproposedchangeissolelyadministrative innatureandinvolvesonlyanamechange.Thisrequestisbeingsubmitted totheNRCpursuantto10CFR50.90onlyforthepurposeofupdatingtheaffectedOLdocuments.

Theproposedchangedoesnotalteranytechnical contentoftheOLoranytechnical contentoftheWNP-2Technical Specifications requirements, nordotheyhaveanyprogrammatic effectontheWashington PublicPowerSupplySystemOperational QualityAssurance ProgramDescription.

Thechangewillhavenoimpactonthedesign,function, oroperation ofanyplantstructure, system,orcomponent, eithertechnically oradministratively.

ATTACHMENT 2REQUESTI<'ORAMENDMENT LICENSEENAMECHANGENoSignificant HazardsConsideration REQUESTFORAMENNTLICENSEENAMECHANGAttachment 2Page1of,lNOSIGNIFICANT HAZARDSCONSIDERATION EVALUATION Pursuantto10CFR50.92,ithasbeendetermined thatthisrequestinvolvesNoSignificant HazardsConsiderations.

Thedetermination ofnosignificant hazardswasmadebyapplyingtheNRCestablished standards contained in10CFR50.92.Thesestandards assurethatanychangestotheoperation ofWNP-2inaccordance withthisrequest,considerthefollowing:

1)Willthechaneinvolveasinificantincreaseintherobabilit orconseuencesofanaccidentreviouslevaluated?

No.Thisrequestinvolvesanadministrative changeonly.TheOperating License(OL)isbeingchangedtoreference thenewnameofthelicensee.

Noactualplantequipment oraccidentanalyseswillbeaffectedbytheproposedchange.Therefore, thisrequestwillhavenoimpact'on theprobability orconsequence ofanytypeofaccidentpreviously evaluated.

2)Willthechanecreatetheossibilit ofanewordifferent kindofaccidentfromanaccidentreviouslevaluated?

No.Thisrequestinvolvesanadministrative changeonly.TheOLisbeingchangedtoreference thenewnameofthelicensee.

Noactualplantequipment oraccidentanalyseswillbeaffectedbytheproposedchangeandnofailuremodesnotboundedbypreviously evaluated accidents willbecreated.Therefore, thisrequestwillhavenoimpactonthepossibility ofanytypeofaccident:

new,different, orpreviously evaluated.

3)Willthechan einvolveasi nificantreductioninamar inofsafe?No.Marginofsafetyisassociated withconfidence intheabilityofthefissionproductbarriers(i.e.,fuelandfuelcladding, ReactorCoolantSystempressureboundary, andcontainment structure) tolimitthelevelofradiation dosetothepublic.Thisrequestinvolvesanadministrative changeonly.TheOLisbeingchangedtoreference thenewnameofthelicensee.

Noactualplantequipment oraccidentanalyseswillbeaffectedbytheproposedchange.Additionally, theproposedchangewillnotrelaxanycriteriausedtoestablish safetylimits,willnotrelaxanysafetysystemsettings, orwillnotrelaxthebasesforanylimitingconditions ofoperation.

Therefore, thisrequestwillnotimpactmarginofsafety.

1I'\

ATTACHMENT 3REQUESTFORAMENDMENT LICENSEENAMECHANGEEnvironmental Assessment/Impact Statement REQVESTFORAMENTLICENSEENAMECHANGAttachment 3Page1of1ENVIRONMENTAL ASSESSMENT/IMPACT STATEMENT Pursuantto10CFR51.22(b),

anevaluation ofthisrequesthasbeenperformed todetermine whetherornotitmeetsthecriteriaforcategorical exclusion setforthin10CFR51.22(c)(9) and(10)oftheregulations.

Thisrequestinvolvesanadministrative changeonly.TheproposedchangeupdatestheOperating License(OL)suchthatreferences tothelicenseenamewillbeconsistent withthenewname,EnergyNorthwest.

Additionally, thisrequestwillhavenoadverseradiation-impact upontheenvironment, sinceit,onlyappliestothenameofthelicenseedesignated intheOL.Ithasbeendetermined thattheproposedchangeinvolves.

1)Nosignificant hazardsconsideration, 2)Nosignificant changeinthetypes,orsignificant increaseintheamounts,ofanyeffluents thatmaybereleasedoffsite,and3)Nosignificant increaseinindividual orcumulative occupational radiation exposures.

Therefore, thisrequestregarding theOLmeetsthecriteriaof10CFR51.22(c)(9) and(10)forcategorical exclusion fromanenvironmental assessment/impact statement.

f ATTACHMENT 4REQUESTFORAMENDMENT LXCENSEENAMECHANGEMarked-Up Operating LicensePages I~'k'A',~A~l'l'AQIAe:4a,A4' PARR&~/QGRYH4J~W~~u-WHLIC

-PeDOCKETNO.50-397~AIUWPPWMB~~FACILITYOPERATING LICENSELicenseNo.NPF-21I.TheNuclearRegulatory Commiss.ion (the.Commi,ssion ortheNRC)hasfound,that:P~aPG.Hc&&cH.vdss~

A.Theapplication forlicensefiledbyup~System-(%HAS+alsothelicensee)-",

complieswiththestandards andrequirements oftheAtomicEnergyActof1954,asamended(theAct),andtheCommission's regulations setforthin10CFRChapterI,andallrequirednotific~oer'odieshavebeendulymade;B.Construction ofwuppity-salem>

NuclearProjectNo.2(thefacility) hasbeensubstantially completed inconformity withConstruction PermitNo.CPPR-93andtheapplication, asamended,theprovisions oftheAct,andtheregulations oftheCommission; C.Thefacilitywilloperateinconformity withtheapplication, asamended,theprovisions oftheAct,andtheregulations oftheCommission (exceptasexemptedfromcompliance inSection2.D.below);D.Thereisreasonable assurance:

(i)thattheactivities authorized bythisoperating license.canbeconducted withoutendangering thehealthandsafetyofthepublic,and(ii)thatsuchactivities willbe~conducted incompliance withtheCommission's regulations setforthin10CFRChapterI(exceptasexemptedfromcompliance inSection2.D.,below,~~ug~QE.T~ash+nger-pstem-istechnically qualified toengageintheactivities authorized bythislicenseinaccordance withtheCo'i'sul'hin10CFRChapterI;Qs>~uJl~~iF.~%astrrngt-o upp+tern-has satisfied theapplicable provisions of10CFRPart140,"Financial Protection Requirements andIndemnity Agreements",

oftheCommission's regulations; 1

G.Theissuanceofthislicensewillnotbeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic;H.Afterweighingtheenvironmental,

economic, technical, andother.benefits ofthefacilityagainstenvironmental andothercostsandconsidering available alternatives, theissuanceofthisFacilityOperating LicenseNo.HPF-21,subjecttotheconditions forprotection oftheenvironment setforthintheEnvironmental Protection Plan.attachedasAppendixB,isinaccordance with10CFRPart51oftheCommission's regulations andallapplicable requirements havebeensatisfied; andI.Thereceipt,possession, anduseofsource,byproduct andspecialnuclearmaterialasauthorized bythislicensewillbeinaccordance withtheCommission's regulations in10CFRParts30,40and70.2.Basedontheforegoing findingsregarding thisfacility, FacilityOperating 1-1NPP-21I2tyI2tNt~~~(thelicensee) toreadasfollows:Ev6P-9agYA'A6'siN.Ttt11pp11*t~~~2Np-tf,boilingwaternuclearreactorandassociated equipment, ownedby-the-e@-Supg~<~em; ThefacilityislocatedonHanfordReservation inBentonCountynearRichland, Washington, andisdescribed inthelicensee's "FinalSafetyAnalysisReport",assupplemented andamended,andinthelicensee's Environmental Report,assupplemented andamended.B.Subjecttotheconditions andrequirements incorporated herein,theCommission herebylicensesw~um-:E~sp-~0oKYAmE,sg(1)PursuanttoSection103oeanar,topossess,use,andoperatethefacilityatthedesignated locationonHanfordReservation, BentonCounty,'ashington, in.accordance withtheprocedures andlimitations setforthinthislicense;(2)PursuanttotheActandl0CFRPart70,toreceive,possessanduseatanytimespecialnuclearmaterialasreactorfuel,inaccordance withthelimitations forstorageandamountsrequiredforreactoroperation, asdescribed intheFinalSafetyAnalysisReport,assupplemented andamended; IE/,I'P (26)(27)ProressofOffsiteEmerencPrearednessAendixDSERIntheeventthattheNRCfindsthatthelackofprogressincompletion oftheprocedures intheFederalEmergency Management Agency'sfinalrule,44C.F.R.Part350,isanindication thatamajorsubstantive problemexistsinachieving ormaintaining anadequatestateofpreparedness, theprovisions of10C.F.R.Section50.54(s)(2) willapply.EffluentRadiation MonitorsSection11.5SSER¹4PriortoJuly1,1984,thelicenseeshallprovidethefollowing information totheNRCstafffortheirreviewandapproval:

1.Sensitivity oftheeffluentmonitors.

2.Evaluation ofresponsetimesoftheseinstruments.

3.Evaluation oftheinstruments percriteriasetforthinSection5.4.7ofANSI13.10.(28)4.Compliance withSection5.4.9ofANSI13.105.Evaluation ofcapability toprovideacalibrated electrical signaltoverifycircuitalignment and,ifused,acommitment

.thattheybequalified.

Environmental ualifications Section3.11SERSSER¹3SSE~¹4PriortoNovember30,1985,thelicenseeshallenvironmentally qualifyallelectrical equipment according totheprovisions of10CFR50.49.(29)(30)Protection oftheEnvironme tFESBeforeengaginginadditional construction oroperational activities whichmayresultinasignificant adverseenvironmental impactthatwasnotevaluation orthatissignificantly greaterthanthatevaluation intheFinalEnvironmental Statement thelicenseeshallprovideawrittennotification totheDirectoroftheOfficeofNuclearReactorRegulation andreceivewrittenapprovalfromthatofficebeforeproceeding withsuchactivities.

Additional CocernsTheAdditional Concernscontained inAppendixC,asrevisedthroughAmendment No.153,areherebyincorporated intothis1icense.-WasMngton-Pwbl-i~~w~p~ystem-shalloperatethefaciityinaccordance withtheAdditional Concerns.

Amendment No.153 ATTACHMENT 1T~PP~U6hSUMRM~

.Thelicenseeshallcompletethefollowing requirements withintheschedulenotedbelow:I.Preooerational/Acceptance Testsa.Thelicenseeshall,priortoloadingoffuelinthe,core,completetheSystem36preoperational testingtoassurethatthosemonitorsrequiredforfuelloadfullymeettheTechnical Specification requirements withoutrelianceonactionstatements:

b.Thelicenseeshallsuccessfully completethefollowing preoperational/acceptance testsbeforeexceeding 5%power:PT33.0-BChemicalWasteProcessing PT37.0-0Miscellaneous Radiation Monitoring Equipment PT40.0-AOff-GasSystemAT65.0-ASealingSteamSystemAT66.0-ACondenser AirRemovalPT69.0-ACondensate SystemPT70.0-ACondensate StorageTransferPT71.0-ACondensate FilterDemineralizer SystemPT72.0-AReactorFeedwater TurbineandPumpsPT72.0-BReactorFeedwater ControlsAT74.0-AHeaterVentsandDrainsAT82.0-ATurbineBuildingHeatingandVentilating PT92.0-AOff-GasVaultHVACAT110.0-ALoosePartsDetection PT201.0-APrimaryContainment Integrated LeakageRateTes.AT302.0-AIntegrated Condenser In-Leakage Testc.ThelicenseeshallcompletePT22.0-8,NitrogenInterting Systempriortosixmonthsafterinitialcriticality.

2.HanoersSupports, andRestraints AllQI-SIaridQII-SIhangers,supports, andrestraints needinginstallation and/ormodification willbecompleted priortoexceeding 5power.3.Construction Completion (MasterCompletion ListSchedule)

Thel.icensee shallrestrainfuelloading,primarysystemsteampressurization, exceeding 5power,andcommerica1 operation" byprerequisite completion o.theassociated categories ofitemsinaccordance withthescheduleshownontheProjectMasterCompletion ListdatedDecember19,1983.Thelicenseeshallnotextendthecompletion categories forindividual itemsonthelistwithoutpriornotification andindividual concurrence byarepresentative oftheNRCRegionalOffice."Conmerical operation isdefinedasthe100%powerwarrantyrunorJuly1,1984,whichever occursfirst.

APPENDIXBTOFACILITYOPERATING LICENSENO.QPRBWSR%$I+p~~e~WASH&GFQ~BhB:-

PSMER-SU-NUCLEAR-PROJEH-NO~

,P-2DOCKETNO.50-397ENVIRONMENTAL PROTECTION PLAN(NONRAOIO LOGICAL)

~Qp~gQcDWVAVJE<~

AA9NBIHe~WER-MPN+4WFa-NUGLEAlH'RGBEC'M~

(P-2ENVIRONMENTAL PROTECTION PLAN(NON-RAOIOLOGI CAL)TABLE"OFCONTENTSSection1.0Objectives oftheEnvironmental Protection Plan..2.0Environmental Protection Issues...............2.1AquaticResources Issues.......,...........2.2Terrestrial Resources Issues..Page2"12"12"13.0Consistency Requirements

..3.1.PlantOesignandOperation

.3.2Reporting RelatedtotheNPOESPermitandStateCertification.

..3.3Changes.Required forCompl.iance withOtherEnvironmental Regulations.

.4.0Environmental Conditions

.~~3-13-13-23-34-14.1UnusualorImportant Environmental Events.4.2Environmental Monitoring

.5.0Administrative Procedures.

5.1ReviewandAudit..5.2RecordsRetention 4-15"15-15-15.3ChangesinEnvironmental Protection Plan.5.4PlantReporting Requirements 5-15"2 k,~.ima(.'

APPENDIXCADDITIONAL CONDITIONS EPEP~Q~YM.MRSFACILITYOPERATING LICENSENO.NPF-2I'll.~14IIbHontheschedules notedbelow:shallcomplywiththefollowing conditions Amendment NumberdditionalConditionImplementation Date149Thelicenseeshallrelocatecertaintechnical specification requirements tolicensee-controlled documents as-described.

below.Thelocationoftheserequirements shallberetainedby,thelicensee.

Implementation shallbecompleted byJune30,1997.'49a.Thislicense-condition approves.

therelocation ofcertaintechnical specification requirements tolicensee-controlled documents (e.g.,UFSAR,LCS,etc.),asdescribed inAttachment Itothelicensee's letterdatedJanuary14,1997.Theapprovalisdocumented inthestaff'ssafetyevaluation datedMarch4,1997.Regulatory Guide1.160commitments asdescribed inAttachment Itothelicensee's letterdatedJanuary14,1997.Implementation shallbecompleted 90daysfromthedateofissuanceofAmendment 149.151Toensuresufficiently conservative SPC9X9-9OLMCPRs,thecalculation of~CPRwillincludeaconservative adderbasedonthevariability observedintheUS96A7comparison withtheANFBcorrelation.

Thisadderwillbeataminimum,thegreateroftwotimesthestandarddeviation inthemeanerrorofthepredictions relativetothecalcu--latedmatwix'values,orafactor=-of 0.975appliedtothe~CPRcalculation, andwillbeindependent ofthe0.975factorin-cludedintheUS96A7correlation asaconservative biastotheUS96A7predic-tionsofCPRfortheSPCfuel.Implementation shallbecompleted priortoexceeding 25%powerforCycle13.Amendment No.449151 nitlIf Distribution SheetDistri27.txt W977'@ggpoooPriority:

NormalFrom:StefanieFountainActionRecipients:

NRR/DLPM/LPD4-2 JGushingEPeytonCopies:1PaperCopyPaperCopyPaperCopyInternalRecipients:

RidsRgn4MailCenter RidsNrrWpcMail RidsNrrDssaSrxb RidsManager RidsAcrsAcnwMailCenter OGC/RPNRRD84LSBX5~

LECENTERtlghCS"000OKOKOKOK0'KPaperCopyPaperCopyPaperCopyPaperCopyExternalRecipients:

NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003689109:1

Subject:

WNP-2-REQUESTFORAMENDMENT, POST-ACCIDENT NEUTRONFLUXMONITORING

,LICENSECONDITION 2.C.(16),

ATTACHMENT 2,ITEM3(b)-ADDITIONAL INFORMATIO NBody:ADAMSDISTRIBUTION NOTIFICATION.

Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML003689109.,

Page1 Distri27.txt A001-ORSubmittal:

GeneralDistribution Docket:05000397Page2 0

EÃSR@P'ORTH WESTPO.Box968aRichland, Washington 99352-0968 February28,2000G02-00-037 DocketNo.50-397U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen:

Subject:

WNP-2OPERATING LICENSENPF-21REQUESTFORAMENDMENT, POST-ACCIDENT NEUTRONFLUXMONITORING, LICENSECONDITION 2.C.(16),ATTACHMENT 2,ITEM3(b)(ADDITIONAL INFORMATION)

Reference Letter,datedFebruary15,2000,JackCushing(NRC)toJVParrish(EnergyNorthwest),

"RequestforAdditional Information (RAI)fortheEnergyNorthwest NuclearProjectNo.2(TACNo.MA6165)Inthereferenced letter,thestaffrequested thatadditional information beprovidedtosupportreviewofourpendingrequestthatLicenseCondition 2.C.(16),Attachment 2,Item3(b),WideRangeNeutronMonitor,beremovedfromtheWNP-2Operating License.Theadditional information isincludedasanattachment.

Shouldyouhaveanyquestions orrequireadditional information regarding thismatter,pleasecallmeorPJInserraat(509)377-4147.Respectfully, DWColemanManager,Regulatory Affairs'-MailDropPE20'~Attachment CC:EWMerschoff

-NRCRIVJSCushing-NRCNRRNRCResidentInspector

-927NDLWilliams-BPA/1399TCPoindexter

-Winston&,Strawn

\I~II, REQUESTFORAMENDMENT, POST-ACCIDENT NEUTRONFLUXMONITORING LICENSECONDITION 2.C(16),ATTACHMENT 2,ITEM3(b)(ADDITIONAL INFORMATION)

Attachment 1Page1of3Question1InSection2.2,Accuracy:

NEDOSection522pofyourJu1y29,1999,submittal, youstatethatduetoinaccuracies inthetletectors, anrplifiers andrecorders, theAPRMswouldslightlyexceedtheaccuracyrequirement of+/2%ofratedthermalpower.Pleaseprovideadditional clarification oftheAPRMaccuracyandjustification ifthecriterion cannotbemet.R~esonseAreanalysis oftheAveragePowerRangeMonitor(APRM)instrument loopaccuracyhasdetermined thatWNP-2meetsthecriteriawithexistingequipment.

Specifically, acalculation wasperformed thatdetermined theAPRMinstrument loopaccuracyis1%of100%oftheratedpowerrangeunderpre-accidentconditions.

WNP-2calibration procedures forLocalPowerRangeMonitor(LPRM)andAPRMgainadjustment andtripsetpoints providechannelcalibration inaccordance withtheWNP-2Technical Specifications.

Additionally, weeklysurveillances verifytheAPRMsareaccurateto+/-2%ratedthermalpowerbasedonthepowervaluescalculated byaheatbalanceduringMode1(PowerOperation) whileoperating

>25%ratedthermalpower.NEDO-31558, Section5.2.2,specifies anaccuracyrequirement of2%ofratedpower.This.requirement ismorerestrictive thanRegulatory Guide1.97,whichissilentoninstrumentation accuracy.

TheWNP-2APRMsystemmaynotmeettheNEDOaccuracyrequirement underallpost-accidentconditions.

Thisjudgement isbasedontheefFectsofanticipated ofF-normal coreconditions following anAnticipated Transient WithoutScram(ATWS)event(power<25%,asymmetric controlrodpatterns, xenon,etc.).Therefore, thetotalAPRMpowermeasurement uncertainties maybeinexcessof2%duringanATWSeventbuttheexactdegreeofinaccuracy cannotbedetermined.

WNP-2hasevaluated theimpactofnotconforming toNEDO-31558, Section5.2.2post-accident andconcludes thedeviation isacceptable.

Thejustification forthisconclusion isprovidedbelowandisconsistent withtheBWROGpositiononthesubject.WNP-2usestheEmergency Procedure Guidelines (EPGs)toachieveshutdownduringanATWSevent.WhentheATWScondition potentially threatens containment, shutdownisaccomplished byinjecting boronviatheStandbyLiquidControlsystem.Thedecisiontoinjectboronisnotdependent onAPRMindications andispredicated ondegrading containment conditions (suchasrisingsuppression pooltemperature).

Asaresult,anAPRMsystemuncertainty beyondthatspecified inNEDO-31558 isacceptable anddoesnotcompromise plantsafety.ThispositionwasacceptedbytheNRCforLaSalleCountyStation,Units1and2byletterdatedSeptember 17,1999,&omD.M.SkaytoO.D.Kingsley,

'Regulatory Guide1.97-BoilingWaterReactorNeutronFluxMonitoring

-LaSalleCountyStation,Units1and2'TACNO.M77660).TheletterdatedJune21,1999,&omJ.A.Benjamin, toU.S.NRC,concerning

'LaSalleCountyStation,Units1and2Compliance withRegulatory Guide1.97-BoilingWaterReactorNeutronFlux REQUESTFORAMENDMENT, POST-ACCIDENT NEUTRONFLUXMONITORING LICENSECONDITION 2.C(16),ATTACHMENT 2,ITEM3(b)(ADDITIONAL INFORMATION)

,Pcttachment 1Page2of3Monitoring,'rovided theBnalLaSalleresponses forparagraph 5.2.2ofNEDO31558-A.ThispositionwasalsoacceptedbytheNRCforQuadCitiesNuclear.PowerStationUnits1and2byletterdatedDecember31,1998,&omR.M.PulsifertoO.D.Kingsley(TACNOs.M51124andM51125)asnotedinthereferenced LaSalleletterofJune21,1999.Question2Insection2,8,PowerSources:NEDOsection5.2.8,youstatedthatticeAPRMswilllosepmveronalossofoffsitepmveruntilpmverisrestoredbythedivision1and2dieselgenerators andt1cemotorgenerator breakersareinanually reset.T1ceNEDOcriterion isforanuninterruptable andreliablepmversource.Pleaseprovideadditionaljustification fornotmeetingtlciscriteriocc.

R~esonseTheWNP-2NeutronMonitoring System(NMS)isfedfromhighlyreliablepowersources.TheLPRM/APRM subsystem ispoweredfromredundant 480/120VoltACmotor-generator (MG)setsconfigured intwoReactorProtection System(RPS)divisional buses(AandB).TheMGsarefedfromredundant andseparatedivisional (ESFDivisions 1and2)480VoltACbusesinseparatemotorcontrolcenters.EitherRPSDivisionBusAorBcanbeenergized byareservefeedfromanon-divisional sourceviamaincontrolroomoperatoraction,TwoElectrical Protection Assemblies (EPAs)areinstalled inseriesbetweeneachofthetwoRPSMGsetsandRPSbusesandbetweenthereservefeedandtheRPSbuses.TheEPAassemblies arepackagedinenclosures thataremountedonSeismicCategoryIstructures.

EPAsprovideredundant protection totheRPSbusesbyactingtodisconnect theRPSfromthepowercircuits.

EachMGsetisequippedwithahighinertiaflywheelwhichissufficient tomaintainthevoltageandfrequency ofgenerated voltagewithin-5%oftheratedvaluesforatleast1secondfollowing alossofpowertothedrivemotor.TheMGsetpowersourcesarereliableanduninterrupted asrequiredtoproperlyperformallthefunctions discussed intheWNP-2FSAR.NeutronMonitoring Systempowerwillnotbelostduetoloadsheddinglogicorasinglefailurethatwouldcausethelossofredundant RPSbusespoweringtheNMSinstrumentation.

IntheunlikelyeventofthelossofoneRPSDivision, thepowerlevelindication willbeprovidedontheredundant DivisionofNMS.ThepowersourcesfortheNMSmeettheNEDOrequirement foruninterruptibility, becausetheyarereliableandcapableofproviding continuous powersothatNMSsafetyfunctions discussed intheFSARaremet.However,foraLossofOffsitePower(LOOP)event,WNP-2deviatesfromtheNEDOrequirements becausebothRPSpowersourceswillbelosttemporarily.

Forthisevent,restoration ofpowertotheAPRMsubsystem isdependent uponemergency dieselgenerator (DG)startuptime "C*4>III4hHpr'yf<>/J REQUESTFORAMENDMENT, POST-ACCIDENT NEUTRONFLUXMONITORING LICENSECONDITION 2.C(16),ATTACHMENT 2,ITEM3(b)(ADDITIONAL INFORMATION)

-,.Qttachment1 Page3of3plusmanualrestartoftheRPSMGsetsandresetoftheEPAs.Inaccordance withstationprocedures forlossofalloffsiteelectrical power,immediate operatoractionsaretoensurethatallautomatic a'ctionshaveoccurredwhichincludeverifying reactorSCRAM(allrodsinserted) andthedieselgenerators autostartandreenergize theirrespective buses.Thesubsequent operatoractionfollowing verification ofautomatic actionsistorestarttheRPSMGsetsandensureneutronmonitoring systemsreturntoservice.Inaccordance withdesign,theDGsarerunningandsupplying powertosafetybusesinapproximately 15seconds.ResetoftheEPAsandmanualrestartoftheRPSMGsetareinthesamelocation(RadWasteBldg467'),however,thislocationisremotefromthemaincontrolroom(RadWasteBldg501')andoperatordispatchisrequired.

Duringthisperiodoftime,thecontrolroomoperatorcandetermine ifcontrolrodsinsertedproperlyusingtheControlRodPositionIndication System(RPIS)whichremainsavailable toprovidebackuptotheNMS.SourceRangeMonitor(SRM)andIntermediate RangeMonitor(IRM)systems,utilizedetectors thatarewithdrawn

&omthecoreduringnormalpoweroperation.

ThedrivemotorsfortheSRM/IRMdetectors arepoweredfromEngineered SafetyFeature(ESF)divisional sourceswhichwillbeenergized uponDGstartup.TheSRMandIRMsystemshaveredundant channelcapability.

Thesystemsensorsandassociated equipment arepoweredbya24VoltDCbattery/charger system.Thebatterychargersforthissystemreceivetheirpowersource&omESFdivisional sources.Insummary,thepresentdesignoftheWNP-2NMSmeetstheintentofSection5.2.8ofNEDO31558-Ainthatthesystemisreliableanduninterruptible forNMSrequiredsafetyfunctions.

Itshouldbenotedthatwithaconcurrent LOOPtheRPSMGsetwouldbeinterrupted, butcanbemanuallyrestoredasdescribed above.Theoperatorstillhasinformation available asdescribed abovetodetermine reactorstatusduringRPSMGsetrestoration.

Thisnon-conformance withtheNEDOisconsistent withtheBWROGRegGuide1.97NeutronMonitoring Systemsubcommittee fortheRG1.97NMS-PowerSuppliespositionthattheexistingMGsetpowersuppliesmeettheintentoftheBWROGpost-accident monitoring functional criteriaasdescribed inparagraph 5.2.8ofNEDO31558-Aanddoesnotcompromise plantsafety.ThispositionwasacceptedbytheNRCforLaSalleCountyStation,Units1and2byletterdatedSeptember 17,1999,&omD.M.SkaytoO.D.Kingsley,

'Regulatory Guide1.97-BoilingWaterReactor¹utronFluxMonitoring

-LaSalleCountyStation,Units1and2'TACNO.M77660).TheletterdatedJune21,1999,RomJ.A.Benjamin, toU.S.NRC,concerning

'LaSalleCountyStation,Units1and2Compliance withRegulatory Guide1.97-BoilingWaterReactorNeutronFluxMonitoring,'rovided thefinalLaSalleresponses forparagraph 5.2.2ofNEDO31558-A.ThispositionwasalsoacceptedbytheNRCforQuadCitiesNuclearPowerStationUnits1and2byletterdatedDecember31,1998&omR.M.PulsifertoO.D.Kingsley(TACNOs.M51124andM51125)asnotedinthereferenced LaSalleletterofJune21,1999.

~~6 Distribution SheetDistri45.txt Priority:

NormalFrom:StefanieFountainActionRecipients:

JGushingCopies:1NotFoundInternalRecipients:

~OGC/RPCENTERNotFound",ggERBKSL1NotFoundNotFoundExternalRecipients:

TotalCopies:Item:ADAMSPackageLibrary:MLADAMS"HQNTAD01ID:003685100

Subject:

Proprietary ReviewDistribution

-PreOperating License8Operating ReactorBody:Docket:05000397, Notes:N/APage1

'%s4~

i'1EWER@FNORTHUlfESTFebruary7,2000G02-00-022 PO.Box968aRichland, Washington 99352-0968 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Gentlemen:

Subject:

WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Reference:

Letter,datedJanuary3,2000,JackCushing(NRC)toJVParrish(EnergyNorthwest)

"RequestforAdditional Information (RAI)forWNP-2,(TACNO.MA7228)"Inthereference, thestaffrequested thatadditional information beprovidedtosupportreviewofourpendingrequestforanamendment toreviseSubsection 4.3.1.2.b ofTechnical Specification 4.3.1.Theadditional information isincludedasattachments, whichconsistsofaresponsetotheRAIquestions andareportfromAseaBrown-Boveri (ABB)Combustion Engineering, Inc.SomeofthematerialinAttachment Bhasbeenidentified asproprietary andismarkedaccordingly (i.e.,bracketed).

Therefore, pursuanttotherequirements of10CFR2.790,anaffidavit isenclosedtosupportthewithholding ofthisinformation frompublicdisclosure.

Shouldyouhaveanyquestions ordesireadditional information regarding thematter,pleasecallmeorPJInserraat(509)377-4147.

Respectfully, DWColeman(MailDropPE20)Manager,Regulatory AffairsAttachments cc:EWMerschoff-NRCRIVJSCushing-NRCNRR.NRCSr.ResidentInspector-927N DLWilliams-BPA/1399TCPoindexter

-WinstonAStrawn AFFIDAVIT

~eSTATEOFWASHINGTON

)))COUNTYOFBENTON)

Subject:

ReportCENSPSD-787-P, WNP-2SVEA-96FuelAssemblies DryFuelStorageCriticality SafetyEvaluation, DatedFebruary, 1995I,D.W.Coleman,beingdulysworn,subscribe toandsaythatIamtheManager,Regulatory Affairs,forENERGYNORTHWEST, theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.Theattachment tothislettercontainsinformation

[markedinbrackets]

thatisconsidered byABBCombustion Engineering, tobeproprietary.

Attachedisanaffidavit executedbyI.C.Rickard,Director, NuclearLicensing, ofABBCombustion Engineering NuclearPower,Inc.,datedJanuary25,2000,whichprovidesthebasisonwhichitisclaimedthatthesubjectdocumentshouldbewithheldfrompublicdisclosure undertheprovisions of10CFR2.790.EnergyNorthwest treatsthesubjectdocumentasproprietary information onthebasisofstatements bytheowner.Insubmitting thisinformation totheNRC,EnergyNorthwest requeststhatthesubjectdocumentbewithheldfrompublicdisclosure inaccordance with10CFR2.790.DATED.W.ColemanManager,Regulatory AffairsOnthisdatepersonally appearedbeforemeD.W.Coleman,tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledged thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.

GIVENundermyhandandsealthisdayof2000.',',ResidingatMy,',Cbirimission'Expires aS,JsIL"tta!s"u~tNotaryPublicinandfortheSTATEOFWASHINGTON (dAuM

&~gyp'Llllll I)g~;pyOgg4UIWygrrrlg(ILOttl)BL'L46 f

REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment A.Page1of6RequestforAdditional Information Question¹1Discussbrieflythetypesofanalyses(including anyseismicdynamicanalysis) performed todetermine thestructural integrity ofthevariouselementsaffectedbythenewgeometrical limitations forstorageofnewfuelassemblies inthenewfuelracks.Thisdiscussion shouldincludetheanalysesrelatedtotheaccidental dropofthefuelassemblies beingsupported bythepedestal.

ResponsetoRequestforAdditional Information Question¹1Astructural analysishasbeenperformed toverifythestructural integrity ofthenewfuelracksresulting fromthenewgeometrical limitations ofthenewfuelracksupportsystem.Seeattacheddiagramsofnewfuelstoragerackarrangement.

Theconfiguration controlcomponents usedinthenewfuelvaultconsistofaseriesoftemplates andworkingplatformgratingsectionsandafuelsupportassembly(pedestal)

~Thetemplates andworkingplatformgratingsectionsallowonlyi/4ofthetotaldesigncapacityoffuelassemblies tobeinstalled (60vs.240assemblies).

Thetemplates permiteveryotherlocationintwofuelrackrowstobeavailable forfuelassemblystorageinacheckerboard patternandthenskipstworowsinbetweenwheretheworkingplatformgratingresides.Theworkingplatformgratingpreventsanyfuelfrombeinginserted.

Thispatternisrepeated, asnecessary, forthevolumeoffuelassemblies tobestoreduptothelimitof60fuelassemblies.

Eachtemplateisfabricated fromi/4inchaluminumplateandisanon-structural elementthataddsnoweighttothefuelrackbeamsortheirsupports.

Thetemplateissecurelymountedonandfastenedtotheworkingplatformgrating.Theworkingplatformissupported fromthenewfuelvaultcoverlip,independent fromthefuelrackbeamsortheirvaultwallsupportboxbeams.Thus,neitherthetemplates northeworkingplatforms provideanyloadingtothefuelrackoritssupportsystem.Theothercomponent isa"fuelsupportassembly" or"pedestal" whichisplacedonthelowerfuelrackandactsasaspacertoraisethefuelassemblies approximately 42inchesforeaseofinspection, exchangeoftheshippinghandlewiththein-vessel balehandle,etc.Thepedestalisconstructed of3'hinchstainless steelschedule40pipe.Thestrengthcharacteristics ofthepedestalaresufficient tosupportthefuelassemblyinthereceptorcellinthelowerfuelrackbeam.Thispedestalsecurelyfitsintothelowerfuelrackbeaminastructurally similarmannerasafuelassemblyandacceptsthenewfuelassemblyintoitstubesectioninastructurally similarmannerasdidthelowerfuelrack.Thepedestalemploysa3inchstainless steelschedule40pipesectiontoachieveaslipfitdesignandasquareplatetoassurepropercentering andfitintothefuelrackreceptorcell.Thepedestalislessthan5%oftheweightofafuelassembly.

Thenewfuelvaultfuelracksupportsystemiscomposedofthreelevelsoffuelrackbeamssupported byboxbeamsattachedtothewallsofthevault.Theuppertwofuelrackbeamsholdthefuellaterally andthelowerfuelrackbeamholdsthefuelvertically andlaterally when Ij~L~t(

REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment A.Page2of6ResponsetoRequestforAdditional Information Question¹1(continued) anassemblyisfullyinserted.

Toaddressthepotential forupliftofafuelassemblymountedinthepedestal, areviewofthefloorresponsespectraandacalculation ofthelowerfuelrackbeamwasperformed.

Theverticalloadonanylowerfuelrackbeamisreducedtolessthan55%oftheoriginalload(i.e.,onehalfoftheweightoftheoriginalnumberoffuelassemblies, plustheweightofthepedestals).

Basedonaconservative naturalfrequency andresponsespectrumanalysis, theforcesfromasafeshutdownearthquake forthenewfuelassemblysupportsystemarebelow1.0gintheverticaldirection.

Thus,noverticalupliftofthefuelassemblywilloccurandtheimplementation ofthistool(pedestal) willnothaveanadversestructural impact(vertically).

Toaddressthepotential forlateralloadincreases duetotheelevatedfuelassemblies (throughtheuseofpedestals),

ananalysiswasperformed comparing theoriginalandelevatedfuelassemblyconfigurations.

Theproposedfuelstoragelimitations andthetemplateassureonlyhalf(everyotherone)ofthedesignednumberofnewfuelassemblies areplacedinarow.Theoriginaldesignusedthreelevelsoffuelrackbeamstocarrythelateralloadoffuelassemblies resulting in'/iofthefuelassemblylateralloadbeingcarriedbythecenterfuelrackbeamand/4ofthelateralloadbeingcarriedbytheothertwofuelrackbeams.Whenthe42inchpedestalisused,onlythecenterandupperfuelrackbeamsareassumedtocarrythelateralload.However,sinceonlyhalfofthefuelassemblies areallowed(fromthatoriginally designed),

theresulting lateralloadsoneachofthebeamswillbeequalto(ontheupperfuelrack)orlessthan(onthecenterfuelrack)theoriginalload.Thismaintains adequatedesignmarginsforfuelrackloads.

REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment A~Page3of6RequestforAdditional Information Question¹2Provideasummaryoftheresultsoftheaboveanalysesandcotifirmthatthe(strengtli)

"capacities" ofthevariousstructural elements(e.g.,thepedestal, vaultfloor,rackwalls,coverplates,etc.)areadequatetosatisfythedemandimposedonthembythenewco>figuration ofthefuelassemblies aspertheapplicable industrycodes.ResponsetoRequestforAdditional Information Question¹2Theproposedlimitations resultinanewconfiguration offuelassemblies thatconsistsofonly'fithenumberoforiginaldesignfuelassemblies inansinglefuelrackrowandi/4ofthetotalnumberoforiginaldesignfuelassemblies inthenewfuelvault.Thisisasignificant loadreduction andakeytoassuringthatthestrengthcapacities ofvariousstructural components areadequate.

Thetemplates andworkingplatformgratingsaresupported independently fromthefuelassemblyracksanddonotaffectthestrengthofthenewfuelrackstructural elements.

Therefore, theuseoftemplates forloadingconfiguration controlandtheuseofpedestals donotresultinloadincreases tothevaultfloor,rackwalls,orotherrackcomponents.

Furthermore, thestrengthcapacities ofFSARTable3.9-2saremaintained.

Calculations demonstrate thatthereisnomechanism resulting fromtheconfiguration controlcomponents thatwouldadversely affecttheconfiguration orintegrity ofthenewfuelassemblyandthattheywouldnotcauseanaccidental fueldrop.Inaddition, theseconfiguration controlcomponents donotaffecttheprevioustestingresultsofaccidental fueldropsonthefuelracksorvaultfioordescribed inFSARSection9.1.1.3.2.

RequestforAdditional Information Question¹3ProvidereportCENPSD-787-P, "WNP-2SVEA-96,FuelAssemblies DryFuelStorageCriticalSafetyEvaluation.

"ResponsetoRequestforAdditional Information Question¹3Seeattachedproprietary reportCENPSD-787-P, "WNP-2SVEA-96,FuelAssemblies DryFuelStorageCriticalSafetyEvaluation."

0'I'a~

REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment AJ'age4of6SEEENLARGEDDEFA1LBELOWIFUELASSEMBLY(TYP)(SSOLB.NOM1NAL)NEWFUI3.STORAGEVAULTPEDESTALOYP)FUELRACKOYP)TEMPLATE(1/4THKALPLATEANOL3x3x1/4)OYP)GRATING(TYP)TEMPIATES NOTSHOWNTOEXPOSEGRATINGdcSTORAGECELLSr~rDNOTE:ALLDIMENSIONS ANDWEIGHTSARENOMINALEWER&VNORTHWESTWNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

NEWFUELVAULT-DIAGRAM1 REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment A3'age5of6GRATINGWITHTEMPlATEGRATING(TYP)FUELASSEMBLY(TYP)FUELRACK(IYP)BOXBEAMOYP)PEDESTAL(TYP)27'-6SIDEVTIONVIEWFUEL6UNOLE-'INSERTED GYP)FUELRACK(IYP)GRATINGOYP)TEMPLATES NOTSHOWNTOEXPOSEGRATING8cSTORAGECELlSQr,QrTEMPLATES (SECUREOTOGRATING)EVACANl'TORAGE CELLOYP)GPPTLPLANVIEWNOTE:ALLDIMENSIONS ANDWEIGHTSARENOMINALElNER&YNORTHVYESTWNP-2,OPERATING I.ICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

NEW'UELVAULT-DIAGRAM2 plb REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment A3'age6of6GRATINGIFUELASSEMBLYOYP)(14'-8'G.

NOMINAL)TEMPIATESEEDETAILIIINEWFUELISTORAGEVAULTRIELRACK(TVP)BOXBEAM63/4,SOOYP)PEDESTALOYP)SEEDETAILf2IIBOXBEAM63/4"x8'IGHOYP)ND7'1/2"FUELASSEMBLYTEMPIATESECUREDTOGRATINGCRATING(33/4HIGHx7'-5"LG)SUPPORTED ONCONCRETELIPPIPE31/2IISCH40SFUELRACK~SIDEOFNEWFUELSTORACEVAULTPIATE1/2x41/2SO-SSIBOXBEAMIDETAIL1PIPE3'0SCH4OS~DETAILPEDESTALNOTE:ALLDIMENSIONS ANDWEIGHTSARENOMINALEIWER4$YNORTHWESTWNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

NEWFUELVAULT-DIAGRAM3 REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b (ADDITIONAL INFORMATION)

Attachment BIProprietary ReportCENPSD-787-P, "WNP-2SVEA-96,FuelAssemblies DryFuelStorageCriticalSafetyEvaluation" Proprietary Affidavit Pursuan0CFR2.790Page1of1.I,IanRickard,deposeandsaythatIamtheDirector, NuclearLicensing, ofABBC-ENuclearPower,Inc.(ABB),dulyauthorized tomakethisaffidavit, andhavereviewedorcausedtohavereviewedtheinformation whichisidentified asproprietary anddescribed below.Iamsubmitting thisaffidavit inconformance withtheprovisions of10CFR2.790oftheCommission's regulations forwithholding thisinformation.

Ihavepersonalknowledge ofthecriteriaandprocedures utilizedbyABBindesignating information asatradesecret,privileged orasconfidential commercial orfinancial information.

Theinformation forwhichproprietary treatment issought,andwhichdocumenthasbeenappropriately designated asproprietary, iscontained inthefollowing:

~CENPSD-787-P, "WNP-2SVEA-96FuelAssemblies DryFuelStorageCriticality SafetyEvaluation,"

datedFebruary, 1995.Pursuanttotheprovisions ofparagraph (b)(4)ofSection2.790oftheCommission's regulations, thefollowing isfurnished forconsideration bytheCommission indetermining whethertheinformation soughttobewithheldfrompublicdisclosure, includedintheabovereferenced

document, shouldbewithheld.

1.Theinformation soughttobewithheldfrompublicdisclosure isownedandhasbeenheldinconfidence byABB.Itconsistsofmethodology andcalculational resultsfornuclearcriticality ofSVEA-96fuelcontained indrystoragevaults.2.Theinformation consistsofanalytical dataorothersimilardataconcerning aprocess,methodorcomponent, theapplication ofwhichresultsinsubstantial competitive advantage toABB.3.Theinformation isofatypecustomarily heldinconfidence byABBandnotcustomarily disclosed tothepublic.4.Theinformation isbeingtransmitted totheCommission inconfidence undertheprovisions of10CFR2.790withtheunderstanding thatitistobereceivedinconfidence bytheCommission.

5.Theinformation, tothebestofmyknowledge andbelief,isnotavailable inpublicsources,andanydisclosure tothirdpartieshasbeenmadepursuanttoregulatory provisions orproprietary agreements thatprovideformaintenance oftheinformation inconfidence.

6.Publicdisclosure oftheinformation islikelytocausesubstantial harmtothecompetitive positionofABBbecause:a.Asimilarproductismanufactured andsoldbymajorcompetitors ofABB.b.Development ofthisinformation byABBrequiredthousands ofdollarsandhundredsofmanhoursofeffort.Acompetitor wouldhaveioundergosimilarexpenseingenerating equivalent information.

c.Theinformation consistsoftechnical dataandqualification information forABB-supplied

products, thepossession ofwhichprovidesacompetitive economicadvantage.

Theavailability ofsuchinformation tocompetitors wouldenablethemtodesigntheirproducttobcttcrcompetewithABB,takemarketing orotheractionstoimprovetheirproduct's positionorimpairthepositionofABB'sproduct,andavoiddeveloping similartechnical analysisinsupportoftheirprocesses, methodsorapparatus.

d.InpricingABB'sproductsandservices, significant

research, development, engineering, analytical, manufacturing, licensing, qualityassurance andothercostsandexpensesmustbeincluded.

TheabilityofABB'scompetitors toutilizesuchinformation withoutsimilarexpenditure ofresources mayenablethemtosellatpricesreflecting significantly lowercosts.Sworntobeforemethis25thdayofJanuary,2000I~n",-NotaryPublicti",$Mycommissionexpires:/

3/6"~r~rrii;uncle Ian.RickaDire,uclearLicensing i/~i/~~><

Distri55.txt Distribution SheetPriority:

NormalFrom:Esperanza LomosbogActionRecipients:

NRR/DLPM/LPD4-2 JCushingEPeytonInternalRecipients:

RidsNrrDssaSrxb RidsNrrDssaSplb RidsManager RidsAcrsAcnwMailCenter OGC/RPNRR/DSSA/SRXB NRR-/DSSFgSPGBC~zxx,zcgvzzao>ACRSCopies:111NotFoundAotFoundNotFoundOKOKOKOKNotFoundNotFoundNotFoundNotFoundNotFoundExternalRecipients:

NOACNotFoundTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01 ID:003681093

Subject:

WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TOTECHNICAL SPECIFICATION LCO349gRESIDUALHEATREMOVALSHUTDOWNCOOLINGSYSTEMHOTSHUTDOWN(ADDITIONAL INFORMATION)

Body:Docket:05000397, Notes:N/APage1 IIk" ENFIQI'ORTH WESTPO.Box968aRichland, Washington 99352-0968 January31,2000G02-00-019 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Gentlemen:

Subject:

WNP-2,OPERATING LICENSENPF-21REQUE<STFORAMENDMENT TOTECHNICAL SPECIFICATION LCO3.4.9,RESIDUALHE<ATREMOVALSHUTDOWNCOOLINGSYSTEM-HOTSHUTDOWN(ADDITIONAL INFORMATION)

Reference:

Letter,datedJanuary3,2000,JackCushing(NRC)toJVParrish(EnergyNorthwest),

"RequestforAdditional Information (RAI)forWNP-2,(TACNO.MA6166)"Inthereference, thestaffrequested thatadditional information beprovidedtosupportreviewofourpendingrequestforanamendment torevisetheApplicability ofLCO3.4.9intheTechnical Specifications.

Theadditional information isincludedasanattachment.

Shouldyouhaveanyquestions ordesireadditional information regarding thematter,pleasecallmeorPJInserraat(509)377-4147.

Respectfully, DWColemanManager,Regulatory AffairsMailDropPE20Attachment cc:EWMerschoff

-NRCRIVJSCushing-NRCNRRNRCSr.ResidentInspector

-927NDLWilliams-BPA/1399TCPoindexter

-Winston2Strawn Pjik "kEQUESTFORAMENDMENT TOTECHNICAL SPECIFICATION LCO3.4.9,RESIDUALHEATREMOVALSHUTDOWNCOOLINGSYSTEM-HOTSHUTDOWN(ADDITIONAL INFORMATION)

Attachment Page1of3QuestionInitsJuly29,1999submittal, thelicenseestatedthatthebasisfortherequested technical spectJication (TS)changeisthattheoriginalplantdesignoperating temperature fortheresidualheatremovul(RHR)shutdowncooling(SDC)pipingandsupportsislessthantheoperational limitcuirently requiredbyTSLimitingCondition forOperation (LCO)3.4.9.Duringaconference callwiththestaffonNovember17,1999,thelicenseestatedthatin1988,anevaluation wasp<<stormed toassessthecondition oftheRHRSDCpipingsystembecauseofthepotential ofexposingthepipingsystemtobeyondoriginaldesignoperating temperature.

Thelicenseeisrequested toprovidedetailsofthe1988assessment (withrespecttothermalstresslimitandthermalfatiguecyclelimit)anditsendings.Background The1988systemoperating temperature discrepancy andresolution wasdocumented inNon-Conformance Report(NCR)288-028(February of1988).TheNCRnotedthattheRHRpipingdownstream oftheheatexchanger wasdesignedforanormaloperating temperature of295'F,whilebyprocedure itwaspossibletoexposeaportionofthepipingtoamaximumtemperature of320'F(saturation temperature for75psig)duringshutdown.

Thiswasbecausetheflowpathforinitiating RHRwasthroughtheheatexchanger bypassvalve.AreviewofthepastRHRshutdowncoolingoperation wascompleted tosupplement theresolution ofthe1988NCR.Additionally, ourcurrentreviewnotedthatfromFebruaryof1984throughMarchof1986,thesysteminitiation wasallowedattemperatures upto355'F(saturation temperature for125psig).Thus,forourevaluation ofthecondition oftheaffectedpipingsystemamaximumtemperature of355'Fat125psigwasassumedfortheinitiation temperature fortheRHRShutdownCooling(SDC).ThermalLoadsonPipingASuppoitsTheRHRSDCsupplyandreturnpipingconsistsofacombination ofASMECodeClass1andCodeClass2piping.ASMEClass1pipingprimary(e.g.earthquake) plussecondary (e.g.thermalexpansion) stressintensity range(Equation 10)hasanallowable stressof3Sm,whichisbasedonthestressintensity definedastwicethemaximumshearstress.IftheEquation10allowable isexceededthenthealternative Equation12and13mustbesatisfied.

OnlyEquation12includesstressesduetothermalexpansion andthermalanchormovements.

Additionally, ASMEClass1pipingandcomponents areevaluated forcumulative damagecausedbyvariousstresscyclesappliedtosystems.Thecuni'ulative usagefactorshallnotexceed1.0.

<<IIIfI REQUESTFORAMENDMENT TOTECHNICAL SPECIFICATION LCO3.4.9,RESIDUALHEATREMOVALSHUTDOWNCOOLINGSYSTEM-HOTSHUTDOWN(ADDITIONAL INFORMATION)

Attachment Page2of3ThermalLoadsonPiping&Supports(continued)

Theeffectsofthermalexpansion ontheASMEClass2pipingsystemmustmeettherequirements ofeitherEquation10(Sa)orEquation11(Sh+Sa).ForASMEClass2piping,theallowable stressrangeforexpansion stresses(Sa)isbasedon7000fullrangethermalcycles.Basedontheplantoperating cyclehistory,theplanthadbeenstartedup34timesbytheendof1988.Duringthefirstyearofoperation, 1984,theplantexperienced 13startups.

Althougheveryshutdowndidnotincludegoingintotheshutdowncoolingmode,forthisevaluation itisassumedthat34temperature cycleswereexperienced.

Thepreferred loop,RHR-B,wasnormallyusedtoinitiateshutdowncooling,butitispossiblethateachloopwouldhavehadaportionofthemaximumprojected cycles.However,forthisevaluation itwasassumedthatbothloopshadexperienced 34cyclesofhighertemperature.

ThecurrentASMEClass1and2stressanalysesfortheRHRreturnandsupplypipingmeettheASMECodeallowable stresslimitsfortheapplicable operating conditions.

Thesepipinganalyseswereevaluated fortheeffectofthepotential higheroperating temperature.

Thenewevaluation showedthattheadjustedstressesremainwithintheASMECodeClass1and2allowable limits.Duringthe1988assessment, itwasconcluded thatthelimitingfactorforthermalexpansion beyondtheanalyzedsystemtemperature wasthepipesupportsystem(e.g.hangers,anchors,etc.)ofthereturnlines.Giventhepossibility ofinitiating theRHRSDCathigherthananalyzedtemperature, NCR288-028identified tencriticalpipesupportsthatmayhavebeenloadedinexcessoforiginalthermaldesignload.Thosecriticalsupportswereinspected andnodamagewasfound.Thehighestloadingwouldhaveoccurredduring1984to1986,whentemperatures possiblyreached355'F.From1986to1988theprocedures limitedsystemtemperatures toamaximumof320'F.Thus,the1988inspection wassufficient todemonstrate thatnodamagehadoccurredinthesupportsystem.ThermalF<atigueCycleTheASMEClass1pipingfatiguelimitisacumulative usagefactorlessthanorequalto1.0.Anevaluation wascompleted thataccounted fortheincreased temperature forinitiation ofRHRSDC.Theresultsdemonstrated thatthepipingfatigueusagewasstilllessthan1.0forbothRHRpipingloopsassumingthateachloophadbeenusedforallshutdowns.

Theoccurrence ofhighertemperature RHRSDCinjections wasnotedintheapplicable systemdesigncalculations andwillbeaccounted forinanyfutureupdatesoftheASMEClass1fatigueanalysesorevaluations forplantlifeextension.

rm~ty I'I,~"MQUESTFORAMENDMENT TOTECHNICAL SPECIFICATION LCO3.4.9,RESIDUALHEAT?MMOVAL SHUTDOWNCOOLINGSYSTEM-HOTSHUTDOWN(ADDITIONAL INFORMATION)

Attachment Page3of3ThermalFatigueCycle(continued)

TheASMEClass2pipingthermalfatiguecyclelimitof7000fullrangecyclesissatisfied becausethepipingthermalexpansion

stresses, duetotheincreased temperature, meetstherequirement ofeitherEquation10orEquationllofASMECodeSub-Section NC-3600.Conclusion Priorto1988,plantprocedures allowedforinitiation ofRHRSDC'attemperatures inexcessofthespecified operating temperature intheRHR=system designspecification.-

Anevaluation:

ofthethermalfatiguecyclesimposedonaffectedpipingdetermined thatASMElimitswerenotexceeded.

SincethetimeofNCR288-028,plantprocedures werechangedtolimitRHRSDCoperation toareactorsteamdomepressureoflessthan48psig(295'),Thislimitation agreeswithallcurrentpipingsystemanalyses.

l1 Distri77.txt Distribution Sheet+917~~PE/uPriority:

NormalFrom:Esperanza LomosbogActionRecipients:

NRR/DLPM/LPD4-2" JCushingEPeytonInternalRecipients:

RidsManager OGC/RPNRR/DSSA/SRXB NA=ileCACRCopies:111111111NotFoundNotFoundNotFoundOKNotFoundNotFoundNotFoundNotFoundNotFoundExternalRecipients:

NRCPDRNOACNotFoundNotFoundTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01 ID:993310150

Subject:

WNP2~OPERATING LICENSENPF21REQUESTFORAMENDMENT TECHNICALSPECIFICATION5.5.7.cVENTILATION FILTERTESTINGPROGRAMBody:PDRADOCK05000397PDocket:05000397, Notes:N/APage1 I

Nl8&ER@F'ORTHWESTPO.Box968aRichland, Washington 99352-0968 November18,1999G02-99-203 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Gentlemen:

Subject:

WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAM

Reference:

NRCGenericLetter99-02,datedJune3,1999,"Laboratory TestingofNuclear-Grade Activated Charcoal" Inaccordance withtheCodeofFederalRegulations, Title10,Parts2.101,50.59and50.90,,andasrequested bythereferenced genericletter,EnergyNorthwest herebysubmitsarequestforamendment totheWNP-2Operating License.Specifically, wearerequesting arevisiontoTechnical Specification (TS)5.5.7.c.Thechangeswouldrevisetherequirements that:1)asampleofthecharcoaladsorberfortheStandbyGasTreatment (SGT)SystemandtheControlRoomEmergency Filtration (CREF)Systembetestedinaccordance withAmericanSocietyforTestingandMaterials (ASTM)D3803-1986, "Standard TestMethodforNuclear-Grade Activated Carbon";2)methyliodidepenetration belessthanavalueof.175%fortheSGTSystemand1.0%fortheCREFSystem;and3)charcoaladsorbertestingbeconducted atarelativehumidityofgreaterthanorequalto70%.Asrequested byGenericLetter(GL)99-02,EnergyNorthwest proposesthatTS5.5.7.cberevisedsothat:1)testingofcharcoaladsorbersamplesbeinaccordance withASTMD3803-1989 ataspecified temperature of30'entigrade (C)(86'-Fahrenheit (F));2)methyliodidepenetration tobelessthanavalueof0.5%fortheSGTSystemand2.5%fortheCREFSystem;and3)testingbeperformed at70%relativehumidity.

geel7't)>(0I~0GenericLetter99-02alsorequiresthatTS5.5.7.cspecifythefacevelocityofanysystemthathasafacevelocitygreaterthan44feetperminute(fpm),sothatcharcoaltestingwillbeconducted atthatvelocity.

ForthisTSchange,afacevelocityof75fpmwillbespecified fortheSGTSystem.The'acevelocityfortheCREFSystemisbelow44fpmandneednotbespecified.

Inaddition, therevisiontoTS5.5.7.cwillnotethatvariations intestingparameters arepermitted pertheguidanceinTable1andSectionA5.2ofASTMD3803-1989.

4~~

,REQUESTFORTTECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAMPage2of3Theengineered safetyfeature(ESF)filterventilation systemsaredescribed inFSARSection6.5.1.TheSGTSystemisdesignedtolimitthereleaseofairborneradioactive contaminants fromsecondary containment totheatmosphere pertheguidelines of10CFR100intheeventofadesignbasisaccident(DBA).Thesafety-related SGTSystemisastandbysystemwhichconsistsoftwofullyredundant subsystems, eachwithitsownsetofductwork, dampers,highefficiency particulate air(HEPA)/charcoal filters,andcontrols.

Eachcharcoalfiltertrainconsistsofamoistureseparator, twoelectricheaterbanks,aprefilter, aHEPAfilterbank,twofourinchcharcoaladsorberbanks,asecondHEPAfilterbank,andtwocentrifugal fans.TheCREFSystemprovidesaradiologically controlled environment fromwhichtheplantcanbesafelyoperatedfollowing aDBA.Thesafety-related CREFSystemisastandbysystemwhichisoperatedtomaintainthecontrolroomenvironment duringnormaloperation.

Uponreceiptofinitiation signal(s)

(indicative ofconditions thatcouldresultinradiation exposuretocontrolroompersonnel),

theCREFSystemautomatically switchestothepressurization modeofoperation topreventinfiltration ofcontaminated airintothecontrolroom.Asystemofdampersisolatesthecontrolroom(fromthenormalintakeandexhaust),

andcontrolroomoutsideairflowisredirected andprocessed througheitheroftwofiltersubsystems.

Eachsubsystem consistsofanelectricheater,aprefilter, aHEPAfilter,anactivated charcoaladsorbersection,afilterunitfan,acontrolroomrecirculation fan,andtheassociated ductworkanddampers.InGL99-02theNRCnotedthattestingnuclear-grade activated charcoaltostandards otherthanASTMD3803-1989, suchasASTMD3803-1986, doesnotprovideassurance forcomplying withourcurrentlicensing basisasitrelatestolimitingdosetothepublicandcontrolroomstaffduringaDBA.Thestaffconsiders ASTMD3803-1989 tobethemostaccurateandrealistic protocolfortestingcharcoalinESFventilation systemsbecauseitoffersthegreatestassurance ofaccurately andconsistently determining thecapability ofthecharcoal.

GenericLetter99-02alsonotedthattestingcharcoalatanelevatedtemperature greaterthan30'resultsinanoverestimation oftheactualiodine-removal capability ofthecharcoal, whilea30'testtemperature ismorerepresentative oflimitingaccidentconditions.

TheproposedchangestoTS5.5.7.careconsistent withthesampletechnical specification providedinGL99-02.EnergyNorthwest willreplacethereference toASTMD3803-1986, including associated testingmethodsAandB,witharequirement totestinaccordance withASTMD3803-1989.

Testingwilloccuratatemperature of30'(86').Testingwillalsocontinueataspecified relativehumidityof70%becausetheSGTandCREFsystemshavehumiditycontrol.Inaddition, andaspermitted bythegenericletter,thelimitsformethyliodidepenetration willbechangedtolessthan0.5%fortheSGTSystemandlessthan2.5%fortheCREFSystem.BecauseASTMD3803-1989 isamoreaccurateanddemanding testmethodthanoldertestmethods,EnergyNorthwest canuseasafetyfactorof2ratherthan5fordetermining theacceptance criteriaforcharcoalfilterefficiency.

Also,becausetheSGTSystemhasafacevelocitygreaterthan44fpm,itsfacevelocityof75fpmwillbeincludedintherevisiontoTS5.5.7.c.

1'is,I+'IV4'

,REQUESTFORTECHNICAL SPECIFICATION 5.5.7.cVF<WTILATION FILTERTESTINGPROGRAMPage3of3Asrequested byGL99-02,arecentlaboratory charcoaltestoftheCREFSystemperformed onAugust5,1999usedtheguidanceprovidedbyASTMD3803-1989.

Theresultsmettheacceptance criterion derivedfromapplyingasafetyfactorof2tothecharcoalfilterefficiency assumedinourdesignbasisanalysis.

Thenextlaboratory charcoaltestwillbeperformed ontheSGTSystem,andshouldbecompleted byDecember1999.EnergyNorthwest willcontinuetotestourESFventilation systemsusingthe1989standard.

Aspreviously discussed withthestaff,thisrequestforamendment totheWNP-2Operating Licensesufficesforthewrittenresponseoriginally requiredbyGL99-02within180daysofthedateofthegenericletter.Additional information hasbeenattachedtothislettertocompletetheamendment request.Attachment 1describes anevaluation oftheproposedchangesinaccordance with10CFR50.92 andconcludes theydonotresultinasignificant hazardsconsideration.

Attachment 2providestheEnvironmental Assessment Applicability Reviewandnotesthattheproposedchangemeetstheeligibility criteriaforacategorical exclusion assetforthin10CFR51.22(c)(9).

Therefore, inaccordance with10CFR51.22(b),

anenvironmental assessment ofthechangeisnotrequired.

Attachment 3providesmarkeduppagesoftheTechnical Specifications.

Attachment 4consistsofthetypedTechnical Specification pagesasproposedbythisamendment.

Thisrequestforamendment hasbeenapprovedbytheWNP-2PlantOperations Committee andreviewedbytheEnergyNorthwest Coiporate NuclearSafetyReviewBoard.Inaccordance with10CFR50.91, theStateofWashington hasbeenprovidedacopyofthisletter.Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecontactmeorPJInserraat(509)377-4147.

Respectfully, RLWebring,MailDropPE08VicePresident, Operations Support/PIO Attachments EWMerschoff

-NRCRIVJSCushing-NRCNRRNRCSeniorResidentInspector

-927NDJRoss-EFSECTCPoindexter

-Winston&StrawnDLWilliams-BPA/1399

~f1hh)l1t STATEOFWASHINGTON)

)COU1%I'YOFBENTON)

Subject:

RequestforAmendment Technical Specification 5.5.7.cVentilation FilterTestingProgramI,DKAtkinson, beingdulysworn,subscribe toandsaythatIamtheActingVicePresident, Operations Support/PIO, forENERGYNORTHWEST, theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthatthestatements madeinitaretrue.DATE4~&l81999LP/cDKAtkinsonActing,VicePresident, Operations Support/PIO Onthisdatepersonally appearedbeforemeDKAtkinson, tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledged thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.

GIVENundermyhandandsealthis~(dayof+II~1999~,aINotaryblicinandfortheSTATEOFWASHINGTON

,.;...,zEZia/~~X sMyCommission expires~~l~/aa'rsrlip

~gglllllllltg pj].rrieeeaceeo Illlflllnlllo

"'f REQUESTFORTECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAMAttachment 1Page1of3Evaluation ofSignificant HazardsConsiderations SummaryofProposedChangeAsrequested byGenericLetter(GL)99-02,EnergyNorthwest isrequesting arevisiontoTechnical Specification (TS)5.5.7.c.ThisTSpresently requiresthatasampleofthecharcoaladsorberfortheStandbyGasTreatment (SGT)SystemandtheControlRoomEmergency Filtration (CREF)Systembetestedinaccordance withAmericanSocietyforTestingandMaterials (ASTM)D3803-1986, "Standard TestMethodforNuclear-Grade Activated Carbon."Technical Specification 5.5.7.calsospecifies thatmethyliodidepenetration belessthanavalueof0.175%fortheSGTSystemand1.0%fortheCREFSystem,andthatcharcoaladsorbertestingbeconducted atarelativehumidityofgreaterthanorequalto70%.ThestaffhasnotedinGL99-02thattestingnuclear-grade activated charcoaltostandards otherthanASTMD3803-1989, suchasASTMD3803-1986, doesnotprovideassurance forcomplying withourcurrentlicensing basisasitrelatestolimitingdosetothepublicandthecontrolroomduringadesignbasisaccident(DBA).Thestaffconsiders ASTMD3803-1989 tobethemostaccurateandrealistic protocolfortestingcharcoalinengineered safetyfeature(ESF)ventilation systemsbecauseitoffersthegreatestassurance ofaccurately andconsistently determining thecapability ofthecharcoal.

EnergyNorthwest proposesarevisiontoTS5.5.7.cthatisconsistent withthesampletechnical specification providedinGL99-02.Thechangewillreplacethereference toASTMD3803-1986, including associated testingmethodsAandB,witharequirement totestinaccordance withASTMD3803-1989.

Thechangewillalsospecifythat:1)testingwilloccuratatemperature of30'entigrade (86'ahrenheit);

2)testingwilloccuratarelativehumidityof70%duetotheSGTandCREFsystemshavinghumiditycontrol;3)thelimitsformethyliodidepenetration willbechangedtolessthan0.5%fortheSGTSystemandlessthan2.5%fortheCREFSystem;4)testingfortheSGTSystemoccursatitsdesignfacevelocityof75feetperminute;and5)variations inthetestingparameters (notedabove)arepermitted pertheguidanceinTable1andSectionA5.2ofASTMD3803-1989.

NoSignificant HazardsConsideration Determination EnergyNorthwest hasevaluated theproposedchangetotheTechnical Specifications usingthecriteriaestablished in10CFR50.92(c) andhasdetermined thatitdoesnotrepresent asignificant hazardsconsideration asdescribed below:~Theoperation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

TheSGTSystemisdesignedtolimitthereleaseofairborneradioactive contaminants fromsecondary containment totheatmosphere withintheguidelines of10CFR100intheeventofaDBA.TheCREFSystemprovidesaradiologically controlled environment from kffit"l4v

~REQUESTFORTTECHNICAL SPECIFICATION 5.5.7.cV1PlTILATION FILTERTESTINGPROGRAMAttachment 1Page2of3whichtheplantcanbesafelyoperatedfollowing aDBA.Theproposedamendment willrequirethatcharcoalfromthesetwoESFsystemsbetestedtothemoreconservative standards ofASTMD3803-1989.

Usingthemoreconservative ASTMD3803-1989 testingstandardwillprovidenoincreaseintheprobability ofanaccidentpreviously evaluated.

Thestaffconsiders ASTMD3803-1989 tobethemostaccurateandmostrealistic protocolfortestingcharcoalinESFventilation systemsbecauseitoffersthegreatestassurance ofaccurately andconsistently determining thecapability ofthecharcoal.

Usingthemoreconservative ASTMD3803-1989 testingstandardwillprovidegreaterassurance thattheESFventilation systemswillproperlyperformtheirsafetyfunction, thusassuringnoincreaseintheradiological consequences ofaDBA.Therefore, operation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

~Theoperation ofWNP-2inaccordance withtheproposedamendment willnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangewillnotcreateanewordifferent kindofaccidentsinceitonlyrequiresthatcharcoalfromtheSGTandCREFsafety-related filtration systemsbetestedtothemoreconservative standards ofASTMD3803-1989.

Usingthemoreconservative ASTMD3803-1989 testingstandardwillprovideevengreaterassurance thattheESFventilation systemswillproperlyperformtheirsafetyfunction, thushelpingtominimizetheradiological consequences ofaDBA.Theincreased marginprovidedbythemoreconservative testingstandardwillassurenonewordifferent kindsofaccidents resultfromtheproposedchange.Therefore, theoperation ofWNP-2inaccordance withtheproposedamendment willnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

~Theoperation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant reduction inthemarginofsafety.Theproposedamendment requiresthatmoreconservative ESFcharcoalfiltertestingcriteriabeusedtoverifyESFventilation systemsareoperable.

Moreconservative testingcriteriawillprovidegreaterassurance thattheESFventilation systemswillproperlyperformtheirsafetyfunction, thushelpingtominimizetheradiological consequences ofaDBA.Usingmoreconservative testingcriteriawillresultinmaintaining thecurrentmarginofsafety.

.REQUESTFORTECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAMAttachment 1Page3of3Inaddition, theproposedmethyliodidepenetration acceptance criteriaincludeasafetyfactoroftwoaspermitted byGL99-02.Thissafetyfactorprovidesadegreeofassurance that,attheendoftheoperating cycle,thecharcoalwillbecapableofperforming atalevelatleastasgoodasthatassumedinthedesignbasisaccidentdoseanalysis.

TheNRCfoundthisfactorofsafetyacceptable, basedontheaccuracyoftestresultsobtainedusingtheASTMD3803-1989

standard, asnotedintheNRCsafetyevaluation reportenclosedintheletterdatedMay13,1998,NRCtoODKingsley, "Issuance ofAmendments (TACNOS.M99726ANDM99727)."

Therefore, operation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant reduction inthemarginofsafety.

l)%Ql

.REQUESTFORTECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAMAttachment 2Page1of1Environmental Assessment Applicability ReviewEnergyNorthwest hasevaluated theproposedamendment againstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.

Theproposedchangemeetsthecriteriaforcategorical exclusion asprovidedforin10CFR51.22(c)(9).

Thechangerequestdoesnotposeasignificant hazndsconsideration nordoesitinvolveanincreaseintheamounts,orachangeinthetypes,ofanyeffluentthatmaybereleasedoff-site.

Furthermore, thisproposedrequestdoesnotinvolveanincreaseinindividual orcumulative occupational exposure.

REQUESTFORTECHNICAL SPECIFICATION 5.5.7.cVENTILATION FILTERTESTINGPROGRAMAttachment 3Marked-Up VersionofTechnical Specification 5.5.7.c ProgramsandManuals5.55.5ProgramsandManuals5.'5.7Ventilation FilterTestinProramVFTP(continued) c.Demonstrate foreachoftheESFsystemsthatalaboratory testofasampleofthecharcoaladsorber, whenobtainedasdescribed inRegulatory Guide1.52,Revision2,showsthemethyl.iodidepenetration lessthanthevaluespecified belowwhentestedinaccordance withASTHD3803-PB6-pfet4ed-lfFf m-and-He&e gatafc~pe~o~we eeeyj-ttttety~~~specified 4&ew.below.Teg+a~Qof+he5'6>syne~>llmls~heI<<ted<<t<<Aceyyeyetlty egee:teetyy<<<<tl:.ESFVentilation SystemPenetration

(%)RH(%)SGTSystem.~95-o,s70CREFSystem70d.Demonstrate foreachoftheESFsystemsthatthepressuredropacrossthecombinedHEPAfiltersandthecharcoaladsorbers islessthanth'evaluespecified belowwhentestedatthesystemflowratespecified below:ESFVentilation SystemDeltaP(incheswg)--Flowrate(cfm)e.4012to4902900to1100SGTSystem<8CREFSystem<6Demonstrate that.theheatersforeachoftheESFsystemsdissipate thenominalvaluespecified below,whentestedinaccordance withASHEN510-1989:

ESFVentilation SystemSGTSystemCREFSystemWattage(kW)18.6,to22.84.5to5.55.5.8t<<<<ExlosiveGasandStoraeTankRadioactivit Honitorin ProramThisprogramprovidescontrolsforpotentially explosive gasmixturescontained intheHain.Condenser OffgasTreatment Systemandthequantityofradioactivity contained inunprotected outdoorliquidstoragetanks.Theprogramshallinclude:OV+41'~8'>0%5l>i+.heIL,

>4i~~pa~~m~4v5'~hFdccv~~~cl~gcsv'p~vvn[4wJpH~continued

<++e~p~v~~~K,re4~ivw hvLnnidi4yp Tdg~$d~Jgec+~o~852,a+ASIH03'F03-Ifr WNP-25.0-13Amendment No.149

/~~~'~~~~4'ILhll~1 REQUESTFORAIBAiNTTECHNICAL SPECIFICATION 5.5.7.cVF<22TILATION FILTERTESTINGPROGRAMAttachment 4Replacement PagesforTechnical Specification 5.5.7.c JIg~>h ProgramsandHanuals5.55.5ProgramsandHanuals5.5.7Ventilation FilterTestinProramVFTP(continued) c~Demonstrate foreachoftheESFsystemsthatalaboratory testofasampleofthecharcoaladsorber, whenobtainedasdescribed inRegulatory Guide1.52,Revision2,showsthemethyliodidepenetration lessthanthevaluespecified belowwhentestedinaccordance withASTHD3803-1989 atatemperature of30'C(86'F)andtherelativehumidityspecified below.TestingoftheSGTSystemwillalsobeconducted atafacevelocityof75feetperminute.ESFVentilation SystemPenetration

(%)RH(%)SGTSystemCREFSystem0.52.57070Variations intheabovetestingparameters oftemperature, relativehumidity, andfacevelocityarepermitted perTable1andSectionA5.2ofASTH03803-1989.

d.Demonstrate foreachoftheESFsystemsthatthepressuredropacrossthecombinedHEPAfiltersandthecharcoaladsorbers islessthanthevaluespecified belowwhentestedatthesystemflowratespecified below:ESFVentilation SystemDeltaPFlowrate(incheswg)(cfm)SGTSystemCREFSystem<84012to4902<6900to1100e.Demonstrate thattheheatersforeachoftheESFsystemsdissipate thenominalvaluespecified belowwhentestedinaccordance withASHEN510-1989:

ESFVentilation SystemSGTSystemCREFSystemWattage(kW)18.6to22.84.5to5.5continued WNP-25.0-13Amendment No.449

'%',g.<<pi ProgramsandManuals5.55.5ProgramsandManuals(continued) 5.5.8ExlosiveGasandStoraeTankRadioactivit Monitorin ProramThisprogramprovidescontrolsforpotentially explosive gasmixturescontained intheMainCondenser OffgasTreatment Systemandthequantityofradioactivity contained inunprotected outdoorliquidstoragetanks.Theprogramshallinclude:'aThelimitsforconcentrations ofhydrogenintheHainCondenser OffgasTreatment Systemandasurveillance programto'nsurethe'limits aremaintained.

Suchlimitsshallbeappropriate tothesystem'sdesigncriteria(i.e.,whetherornotthesystemisdesignedtowithstand ahydrogenexplosion);

andb.Asurveillance programtoensurethatthequantityof'adioactivity contained inalloutsidetemporary liquidradwastetanksthatarenotsurrounded byliners,dikes,orwalls,capableofholdingthetanks'ontents andthatdonothavetankoverflows andsurrounding areadrainsconnected totheLiquidRadwasteTreatment Systemislessthantheamountthatwouldresultinconcentrations greaterthanthelimitsofAppendixB,Table2,Column2to10CFR20.1001-20.2402,atthenearestpotablewatersupplyandthenearestsurfacewatersupplyinanunrestricted area,intheeventofanuncontrolled releaseofthetanks'ontents.

Theprovisions ofSR3.0.2andSR3.0.3areapplicable totheExplosive GasandStorageTankRadioactivity Monitoring ProgramSurveillance Frequencies.

5.5.9DieselFuelOilTestinProramAdieselfueloiltestingprogramshallestablish therequiredtestingofbothnewfueloilandstoredfueloil.Theprogramshallincludesamplingandtestingrequirements, andacceptance

criteria, allinaccordance withapplicable ASTHStandards.

Thepurposeoftheprogramistoestablish thefollowing:

a~Acceptability ofnewfueloilforusepriortoadditiontostoragetanksbydetermining thatthefueloilhas:I.AnAPIgravity,aspecificgravity,oranabsolutespecificgravitywithinlimits,continued WNP-25.0-14Amendment No.449(

.,>~<<gv'r>t"IiaAh'l'I' y~yeProgramsandHanuals5.55.5ProgramsandHanuals5.5.9DieselFuelOilTestinProram(continued) 2.Akinematic viscosity, ifgravitywasnotdetermined bycomparison withthesupplier's certificate, andaflashpointwithinlimitsforASTH2-Dfueloil,3.Awaterandsedimentcontentwithinlimitsoraclearandbrightappearance withpropercolor;b.Otherproperties forASTH2-Dfueloilarewithinlimitswithin31daysfollowing samplingandadditiontostoragetanks;andc.Totalparticulate concentration ofthefueloilinthestoragetanksis~10mg/1whentestedevery31daysinaccordance withASTHD-2276,HethodA-2orA-3.Theprovisions ofSR3.0.2andSR3.0.3areapplicable totheDieselFuelOilTestingProgramtestFrequencies.

5.5.10Technical Secifications TSBasesControlProramThisprogramprovidesameansforprocessing changestotheBasestotheseTechnical Specifications.

a.ChangestotheBasesoftheTSshallbemadeunderappropriate administrative controlsandreviews.b.Licensees maymakechangestoBaseswithoutpriorNRCapprovalprovidedthechangesdonotinvolveeitherofthefollowing:

l.AchangeintheTSincorporated inthelicense;or2.AchangetotheFSARorBasesthatinvolvesanunreviewed safetyquestionasdefinedin10CFR50.59.c.TheBasesControlProgramshallcontainprovisions toensurethattheBasesaremaintained consistent withtheFSAR.d.Proposedchangesthatmeetthecriteriaof5.5.10.baboveshallbereviewedandapprovedbytheNRCpriortoimplementation.

ChangestotheBasesimplemented withoutpriorNRCapprovalshallbeprovidedtotheNRConafrequency consistent with10CFR50.71(e).

(continued)

WNP-25.0-15Amendment No.449~

i~"~sm Distri80.txt Distribution Sheet/j/zi/8'riority:

Normal,From:Esperanza LomosbogActionRecipients:

NRR/DLPM/LPD4-2 JCushingEPeytonInternalRecipients:

RidsManager OGC/RP'RR/DSSA/SRXB NRR/DSQeCente01~SCopies:111NotFoundNotFoundNotFoundOKNotFoundNotFoundNotFoundNotFoundNotFoundExternalRecipients:

NRCPDRNOACNotFoundNotFoundTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01 ID993310160

Subject:

WNP2~OPERATINGLICENSENPF21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION4.3.1.2.bFUELSTORAGE(Body:pdradock05000397pDocket:05000397, Notes:N/APage1 ENERGYNORTHWESTPO.Box968oRichland, Washington 99352-0968-.

November18,1999G02-99-202 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:

Subject:

WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGE

Reference:

NRCAdministrative Letter98-10,December29,1998,"Dispositioning ofTechnical Specifications thatareInsufficient toAssurePlantSafety"Inaccordance withtheCodeofFederalRegulations, Title10,Parts2,101,50.59,and50.90,EnergyNorthwest herebysubmitsarequestforamendment totheWNP-2Operating License.Specifically, EnergyNorthwest isrequesting arevisiontosub-section 4.3.1.2.b ofTechnical Specification 4.3.1"Criticality,"

torevisethewordingthatdefinesthelimitations forplacement offuelintheNewFuelStorageFacility.

ThecurrentwordingofTechnical Specification 4.3.1.2.b, adoptedaspartoftheImprovedTechnical Specifications anddocumented byNUREG-1434, correctly describes thenewfuelvaultrackspacingassociated withtheoriginalrackdesign.However,itdoesnotaccurately reflectthecurrentdesignfeaturesandcontrolsreliedupontoadequately limitthespacingofnewfuelassemblies inthenewfuelvaultasrequiredtoensurecompliance withTechnical Specification 4.3.1.2.a underallpostulated conditions; and,therefore constitutes adegradedornon-conforming condition pursuanttotheguidanceoftheReference.

Thiscorrection shouldhavebeenmadeaspartofthereviewactivities inpreparation forsubmittal oftheImprovedTechnical Specifications, but.wasnot.Weareproposing anamendment tosubsection 4.3.1.2.b ofTechnical Specification 4.3.1toaddressthisnon-conforming.

condition.

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'REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEPage2of2Additional information hasbeenattachedtothislettertocompleteEnergyNorthwest's amendment request.Attachment 1providesadetaileddescription andbasisforacceptability oftheproposedchanges.Attachment 2describes anevaluation oftheproposedchangesinaccordance with10CFR50.92(c),

andconcludes thechangesdonotresultinasignificant hazardsconsideration.

Attachment 3providestheEnvironmental Assessment Applicability Reviewandnotesthattheproposedchangemeetstheeligibility criteriaforacategorical exclusion assetforthin10CFR51.22(c)(9).

Therefore, inaccordance with10CFR51.22(b),

anenvironmental assessment ofthechangeisnotrequired.

Attachment 4summarizes theproposedchang'eanoprovidesamarkeduppageoftheTechnical Specification.

Attachment 5submitsthetypedTechnical Specification pageasproposedbythisrequest.Thisrequestforanamendment hasbeenapprovedbytheWNP-2PlantOperations Committee andreviewedbyEne;gyNorthwest's Corporate NuclearSafetyReviewBoard.Inaccordance with10CFR50.91, theStateofWashington hasbeenprovidedacopyofthisletter.Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecontactmeorPJInserraat(509)377-4147.

Respectfully, RLWebringVicePresident, Ope>",itions Support/PIO MailDropPE08Attachments CC:EWMerschoff

-NRCRIVJSCushing-NRCNRRNRCResidentInspector

-927NDJRoss-EFSECTCPoindexter

-Winston&StrawnDLWilliams-BPA/1399 f

STATEOFWASHINGTON

))COUNTYOFBENTON)

Subject:

RequestforAmendment Technical Specification 4.3.1.2.b FuelStorageI,DKATKINSON, beingdulysworn,subscribe toandsaythatIamtheActingVicePresident, Operations Support/PIO forENERGYNORTHWEST, theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.DATE,1999DKAtkinsonActingVicePresident, Operations Support/PIO Onthisdatepersonally appearedbeforemeDKAtkinson, tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledged thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.

GIVENundermyhandandsealthis/Rdayof8ItJ3k1999.NoPublicinandfortheSTATEOFWASHINGTON ResidingatWMyCommission Expires OgtltIIIIIIIIIICOCCCCCCC COIIItttttlltll

,RI<.QUEST I<'ORAhlENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 2Page1of2,Evaluation ofSignificant HazardsConsideration SummaryofProposedChangeEnergyNorthwest isproposing anamendment tosub-section 4.3.1.2.b ofTechnical Specification 4.3.1,"Criticality."

Weproposetochangethecurrentwording,whichdescribes thenewfuelracks,withwordingthatwouldlimitthenumberoffuelassemblies thatmaybestoredinthefacility, andestablish geometrical limitations forstorageofnewfuelassemblies intheracks.Theproposedwordingisasfollows(changesare~underlined:

4.3.1.2Thenewfuelstorageracksaredesignedand,withfuelassemblies

inserted, shallbemaintained with:a.(nochange)b.Amaximumf60newfuelasembliesstoredinhenewfuelstoraeracksarranedin6satia11earedzne.Wihinsoraezonethenominalcener-o-centerdiancebetweencellsforstorinfuelassemblies is14inches.Thenominalcenter-to-center distancebetweencellsforstorinfuelassembliinad'acentzonesis37inches.Desinfeaturesrelieduontosatialllimit~the]acementoffuelbundleswithinhenewfuelvultareruiredtobe~intliedrirlacemenofnewfuelbundleinthevault.

NoSigniTicant HazardsConsideration Determination EnergyNorthwest hasevaluated theproposedchangetoTechnical Specifications usingthecriteriaestablished in10CFR50.92(c),

andhasdetermined thatitdoesnotrepresent asignificant hazardsconsideration asdescribed below:~Theoperation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Theproposedchangedoesnotincreasetheconsequences ofanypreviously analyzedaccidentortransient, sincethearrangement ofnewnuclearfuelinstorageracksmaintains theeffective neutronmultiplication factormuchlessthan0.95.Thechangeinconfiguration requirements willnotincreasetheprobability ofanypreviously analyzedaccident, becausephysicalconstraints areinstalled inthestoragerackswhennewfuelassemblies areinserted, assuringthatonlycertaincellscanbeusedforstorageofnewfuel.Therefore, operation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

~MI*4(i

,REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 2Page2of2~Theoperation ofWNP-2inaccordance withtheproposedamendment willnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangeisconsistent withanewfuelcriticality analysisperformed insupportofapreviously implemented changetoSection9.1oftheFSAR.Avarietyofaccidents wereconsidered inthatanalysis, anditwasdetermined thattheeffective neutronmultiplication factorwaswellbelowspecified limitsforanynormaloraccidentcase.Therefore, operation ofWNP-2inaccordance withtheproposedamendment willnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated.

~Theoperation oiWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant rediiction inthemarginofsafety.ThecurrentwordingofTechnical Specification 4.3.1.2.b wasdetermined tonotprovidesufficient marginofsafetytoassurethattherequirements ofTechnical Specification 4.3.1.2.a wouldbemaintained.

Theproposedamendment modifiestherequirements fornewfuelstorageconfiguration forTechnical Specification 4.3.1.2.b, toassurethemarginofsafetyismaintained foroptimummoderation conditions.

Therefore, operation ofWNP-2inaccordance withtheproposedamendment willnotinvolveasignificant reduction inthemarginofsafety.

• I+

.REQUESTFORAIiIENDMENTTECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 1Page1of3Description ofProposedChangesSummaryOfProposedTechnical Specification ChangeEnergyNorthwest isproposing anamendment tosub-section 4.3.1.2.b ofTechnical Specification 4.3.1,",Criticality."

Weproposetochangethecurrentwording,whichdescribes thenewfuelracks,withwordingthatwouldlimitthenumberoffuelassemblies thatmaybestoredinthefacility, andestablish geometrical limitations forstorageofnewfuelassemblies intheracks.Theproposedwordingisasfollows(changesareu~nderlined:

4.3.1.2Thenewfuelstorageracksaredesignedand,withfuelassemblies

inserted, shallbemaintained with:a.(nochange)b.maximumf6newfuelasembliesstoredinthenewfuelstoraerackarranedin6satiallsegratedzones.Withinastoraezonethenominalcenter-to-center distancebetweencellsforstorinfuelasembliesis14inchesThenominalcenter-to-center distancebetweencellsforstorinfuelassemblies inad'acentzonesis37inches.Desinfeaturesrelieduontosatialllimithelacementoffuelbundleswithinthenewfuelvaultareruiredtobeinstalled riortolacementofnewfuelbundleinthevault.BasisfortheProposedTechnical Specification ChangeTheNewFuelStorageFacilityisadrystoragefacilitywithairasthemediumsurrounding storedfuel.Thefaci!ityisaconcretevault;boththeverticalandhorizontal cross-sections arerectangular.

Thefloorofthevaultincludesadraintoremovewaterthatmayaccidentally orunknowingly beintroduced intothevault.Thecellutilization patternforthefuelconsistsof2contiguous rowsinwhichfuelassemblies maybestoxed,alternating with2contiguous rowsinwhichfuelstorageisprohibited.

Withina2-xowsetinwhichfuelisstored,alternate cellsarephysically blocked,inacheckerboard pattern,topreventinadvertent cellusage..Thisresultsinanominalcenter-to-center distancebetweencellsforstoringfuelassemblies of14inches.Thenominalcenter-to-center distancebetweencellsusedtostorefuel,acrossthe2-rowsetinwhichfuelstorageisprohibited, is37inches.Asketchofthisutilization patternisincludedonPage3ofthisattachment.

Theaboveconfiguration wasanalyzedtodetermine theeffective neutronmultiplication factor,k,,for(1)geometrical variations resulting fromtolerances fortheinstallation, (2)airasthevaultatmosphexe, and(3)watexasthevaultatmosphere inarangeofdensities varyingfrom1to0.02gm./cc.

l~lt-

,'REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 1Page2of3Additionally, postulated accidents wereincludedintheanalysis:

assemblies droppedonthevaultfloor,andinsertion patternsthatvariedfromthebaselineconfiguration described above.Nocreditwastakenfortheneutronabsorptive effectofmetalscomprising thestoragerack,thegadolinium andthezirconium claddinginthefuelassemblies, andanymetalintheconcretestructure ofthevault.Theanalysiswasperformed usingthecomputercodeKENO,withneutroncross-sections calculated usingthePHOENIXcode.TheNRChasapprovedbothcodes.Theconclusion oftheanalysisofthisconfiguration isthatk,~ranges between0.64and0.86fornormalgeometryandis0.898foraworst-case accidentinvolving aninsertion patternthatvariedfromthespecified baselineconfiguration.

Thedroppedfuelbundleaccidentresultedinarangeofk,~of0.87to0.88.Technical Specification 4.3.1.2.a specifies alimitingvalueof0.95fork,~whenfullyfloodedwithunborated water.Inshort,theKENOanalysisshowsaconsiderable marginofsafetyfortheconfiguration described above,graphically presentsonPage3ofthisattachment, andforconfigurations resulting fromaccidents involving droppedfuelassemblies andinsertion errors.

~~a~$a~~0~~~~~I%.'-"'::::-""'E.""-:-"-'E.'="'4E:"E:."-:::i

'4E":-';-.-"-'E'-"'.":-'-'"'E'::.4E;:

:E-..-=:;E'--"-::r

-:.=-::E:=-"E;=::=--E

~~I~~~~~~~~~[%g<p~4'i<'j4>

.REQUESTFORA5IENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 3Page1of1Environmental Assessment Applicability ReviewEnergyNorthwest hasevaluated theproposedamendment againstthecriteriaforidentification oflicensing andregulatory actionsrequiring environmental assessment inaccordance with10CFR51.21.

Theproposedchangemeetsthecriteriaforcategorical exclusion asprovidedunder10CFR51.22(c)(9) becausethechangedoesnotposeasignificant hazardsconsideration nordoesitinvolveanincreaseintheamounts,orachangeinthetypes,ofanyeffluentthatmaybereleasedoffsite.Furthermore, thisrequestdoesnotinvolveanincreaseinindividual orcumulative occupational exposure.

'REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 4Marked-Up VersionofTechnical Specification 4.3.1.2.b DesignFeatures4.04.0DESIGNFEATURES(continued) 4.3FuelStorage.'I3.3.1C~ii1114.3.1.1Thespentfuelstorageracksare.designedandshallbemaintained with:a.k,<<~0.95iffullyfloodedwithunbor'ated water,whichincludesanallowance foruncertainties asdescribed inSection9.1.2oftheFSAR;andb.4.3.1.2Anominal6.5inch.center.tocenterdistancebetweenfuelassemblies placedinthestorageracks.thfuIassemblies inset+Thenew-fuelstorageracksaredesigned.andshallbemaintained

.with:a~k,~0.95iffullyfloodedwithunborated water,whichincludesanallowance foruncertainties asdescribed inSection9.1.1oftheFSARVand4.3.2~DcaiaaeThespentfuelstoragepoolisdesignedandshallbemaintained topreventinadvertent drainingofthepoolbelowelevation 583ft1.25inches.4.3.3~CaacitThespentfuelstoragepoolisdesignedandshallbemaintained withastoragecapacitylimitedtonomorethan2658fuelassemblies.

b.Amaximumof60newfuelassemblies storedinthenewfuelstorageracks,arrangedin6spatially separated zones.Withinastoragezone,thenominalcenter-to-center distancebetweencellsforstoringfuelassemblies is14inches.Thenominalcenter-to-center distancebetweencellsforstoringfuelassemblies inadjacentzonesis37inches.Designfeaturesreliedupontospatially limittheplacement offuelbundleswithinthenewfuelvaultarerequiredtobeinstalled priortoplacement ofnewfuelbundlesinthevault.IMNP-24.0-2Amendment No.149

.'REQUESTFORAMENDMENT TECHNICAL SPECIFICATION 4.3.1.2.b FUELSTORAGEAttachment 5Replacement PageforTechnical SpeciTication 4.3.1.2.b N*

17>DesignFeatures4.04.0DESIGNFEATURES(continued) 4.3FuelStorage4.4.3.1.1Thespentfuelstorageracksaredesignedandshallbemaintained with:'a~k,<<~0.95iffullyfloodedwithunborated water,whichincludesanallowance foruncertainties asdescribed inSection9.1.2oftheFSAR;andb.Anominal6.5inchcentertocenterdistancebetweenfuelassemblies placedinthestorageracks.4.3.1.2Thenewfuelstorageracksaredesignedand,withfuelassemblies

inserted, shallbemaintained with:.a~b.k,<<~0.95iffullyfloodedwithunborated water,whichincludesanallowance foruncertainties asdescribed inSection9.1.1oftheFSAR;andAmaximumof60newfuelassemblies storedinthenewfuelstorageracks,arrangedin6spatially separated zones.Withinastoragezone,thenominalcenter-to-centerdistancebetweencellsforstoringfuelassemblies is14inches.Thenominalcenter-to-center distancebetweencellsforstoringfuelassemblies inadjacentzonesis37inches.Designfeaturesreliedupontospatially limittheplacement offuelbundleswithinthenewfuelvaultarerequiredtobeinstalled priortoplacement ofnewfuelbundlesinthevault.4.3.2~DrainaeThespentfuelstoragepoolisdesignedandshallbemaintained topreventinadvertent drainingofthepoolbelowelevation 583ft1.25inches.4.3.3~CaacitThespentfuelstoragepoolisdesignedandshallbemaintained withastoragecapacitylimitedtonomorethan2658fuelassemblies.

WNP-24.0-2Amendment No.449 ysstses Distri46.txt Distribution SheetPriority:

NormalFrom:AndyHoyActionRecipients:

LPD4-2EPeytonCUSHING,J Copies:111NotFoun'dNotFoundNotFoundInternalRecipients:

RidsManager OGC/RPNRR/DSSA/SRXB NRR/DSSA/SPLB LeeBerterAndrewKuglerACRS,OKNotFoundNotFoundNotFoundOKNotFoundOKNotFoundExternalRecipients:

NRCPDRNOACNotFoundNotFoundTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01 ID:993060091 13

Subject:

REQUESTFORAMENDMENT TOTECHNICAL SPECIFICATIONS SR3.8.4.6andSR3.8.5.1(REPLACEMENT PAGES)Body:Docket:05000397, Notes:N/APage1 October20,1999G02-99-184 EP@ERSF>NORTHNfESTPO.Box968uRichland, Washington 99352-0968 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555Gentlemen:

Subject:

WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TECHNICAL SPECIFlCATIONS SR3.8.4.6andSR3.8.5.1(REPLACEMENT PAGES)

Reference:

LetterGO2-99-146, datedJuly29,1999,RLWebring(EnergyNorthwest) toNRC,"RequestforAmendment, Technical Specifications SR3.8.4.6and3.8.5.1"ThepurposeofthisletteristoresubmitthetypedTechnical Specification pagesastheywouldberevisedbythereferenced amendment request.Theoriginalpages,whichwereincludedasAttachment 5inthereference, contained anincorrect pagenumbering sequence.

Thereplacement pagesassociated withtheproposedchangesareincludedasanattachment andreflectthecorrected pagenumbering.

Nootherchangesweremade.Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecallmeorPJInserraat(509)377-4147.

Respectfully, FoCDWColemanManager,Regulatory AffairsMailDropPE20I)Attachment cc:EWMerschoff

-NRCRIVJSCushing-NRCNRR~,NRCSr.ResidentInspector

-927NHBAA40ff3dkoQ9'/DLWilliams-BPA/1399TCPoindexter

-Winstonk,Strawn REQUESTFORAMENDMENT TECHNICAL SPECIFICATIONS SR3.8.4.6andSR3.8.5.1(REPLACEMENT PAGES)'~qj7Attachment Replacement PagesTechnical Specifications SR3.8.4.6andSR3.8,5.1Amendment Request DCSources-Operating 3.8.4SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR3.8.4.5Verifybatteryconnection resistance is<24.4E-6ohmsforinter-cell connectors oftheDivision1and2batteries,

<169E-6ohmsforinter-cell connectors oftheDivision3battery,and<20%abovetheresistance asmeasuredduringinstallation forinter-tier andinter-rack connectors.

12monthsSR3.8.4.6NOTE-ThisSurveillance shallnotbeperformed inMODE1,2,or3.However,creditmaybetakenforunplanned eventsthatsatisfythisSR.Verifyeachrequiredbatterychargersuppliestherequiredloadfor~1.5hoursat:24monthsa.~126Vforthe125Vbatterychargers; andb.~252Vforthe250Vbatterycharger.(continued)

WNP-23.8-27Amendment No.449

~~&IVYAly~V~g~gP'>'f~,~h'~>f1 DCSources-Operating 3.8.4SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR3.8.4.7-NOTES1.Themodifiedperformance discharge testinSR3.8.4.8maybeperformed inlieuoftheservicetestinSR3.8.4.7onceper60months.2.ThisSurveillance shallnotbeperformed inMODE1,2,or3.However,creditmaybetakenforunplanned eventsthatsatisfythisSR.Verifybatterycapacityisadequatetosupply,andmaintaininOPERABLEstatus,therequiredemergency loadsforthedesigndutycyclewhensubjected toabatteryservicetest.24monthsWNP-23.8-28Amendment No.449 r4'",,~ti*

DCSources-Operating 3.8.4SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR3.8.4.8-NOTE--------------------

ThisSurveillance shallnotbeperformed inNODE1,2,or3.However,creditmaybetakenforunplanned eventsthatsatisfythisSR.Verifybatterycapacityisa80%ofthemanufacturer's ratingforthe125Vbatteries andz83.4%ofthemanufacturer's ratingforthe250,Vbattery,whensubjected toaperformance discharge testoramodifiedperformance discharge test.60monthsAND'2monthswhenbatteryshowsdegradation orhasreached85%ofexpectedlifewithcapacity<100%ofmanufacturer's ratingAND24monthswhenbatteryhasreached85%oftheexpectedlifewithcapacityz100%ofmanufacturer's ratingWNP-23.8-28aAmendment No.449 DCSources-Shutdown3.8.5ACTIONSCONDITION REQUIREDACTIONCOMPLETION TIMEA.(continued)

A.2.3ANDA.2.4Initiateactiontosuspendoperations withapotential fordrainingthereactorvessel.InitiateactiontorestorerequiredDCelectrical powersubsystems toOPERABLEstatus.Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR3.8.5.1NOTEThefollowing SRsarenotrequiredtobeperformed:

SR3.8.4.6,SR3.8.4.7,andSR3.8.4.8.ForDCelectrical powersubsystems requiredtobeOPERABLEthefollowing SRsareapplicable:

SR384I)SR3842>>SR3843)SR3.8.4'.4, SR3.8.4.5,SR3.8.4.6,SR3.8.4.7,andSR3.8.4.8.Inaccordance withapplicable SRsWNP-23.8-30Amendment No.449