ML17320B073

Revised Application for Amend to License DPR-74.Amend Reflects Addl Limitation on Nuclear Enthalpy Rise Hot Channel Factor Due to New Loca/Eccs Analysis in Support of Cycle 5 Reload.Application Part of 840301 Submittal

ML17320B073
Person / Time
Site:	Cook
Issue date:	05/21/1984
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	DENTON H R Office of Nuclear Reactor Regulation
Shared Package
ML17320B074	List: ML17320B073 ML17320B075
References
AEP:NRC:0860K, AEP:NRC:860K, NUDOCS 8405290295
Download: ML17320B073 (10)

Text

REGULATORYIFORMATION DISTRIBUTION SYEIA(RIDE)ACCUSSIIlfNNBR8'5290295 DOC8DATE~84/05/21NOTARIZED~NODOCKETFACIL:50316DonaldO~CookNuclearPowerPlentyUnit2FIndiana805000316AUTH~NAI<EAUTIIORAFFILIATION

)ALEXICHFM.P, Indiana8MichiganElectricCo,RECIP~NAMERECIPIENT AFFILIATION DENTONFHBR

~OfficeofNuclearReactorRegulationi Director

SUBJECT:

Revisedapplication foramendtoLicenseDPR74.Amendreflectsaddilimitation onnuclearenthalpyrisehotchannelfactorduetonewLOCA/ECCS analysisinsupportofCycle5re'load.Application partof8ff0301submittal+

DISTRIBUTION CODE:IE26SCOPIESRECEIVED:LTR ENCLgSIZEGjL4,2~I(,TITLE:Start-UpReport/Refueling Report(50kt)NOTES:RECIPIENT IDCODE/NAME NRRORB1BC04INTERNAI.:

IEFILEOlNRR/DHFSDIR08NRR/DSI/CPB 12COPIESLTTRENCL33111111RECIPIENT IDCODE/NAME NRR/DHFSDEPY07NRR/DHFS/PSRB11 RM/DDAMI/MIB09COPIESLTTRENCLEXTERNAL:

ACRS13NRCPDR02NTIS551111LPDRNSIC0305COri)~~.e.Fi~TOTALNUMBEROF.COPIESREQUIRED:

LTTR18ENCL18 ItiinnnnIiIH)i'ii~

INDIANA8NICHIGANELECTRICCOMPANYP.O,BOX16631COLUMBUS, OHIO43216May21,1984AEP:NRC:0860K DonaldC.CookNuclearPlantUnitNo.2DocketNo.50-316LicenseNo.DPR-74REVISIONTOTHEAPPLICATION FORCHANGESTOTHEUNIT2TECHNICAL SPECIFICATION FORTHECYCLE5RELOADMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555

DearMr.Denton:

Thisletteranditsattachments constitute arevisiontoourapplication (AEP:NRC:0860, datedMarch1,1984)foramendment totheDonaldC.CookNuclearPlantUnitNo.2AppendixATechnical Specifications (T/S).ThisproposedrevisionisinresponsetoconcernsraisedbytheNRCduringthereviewofourproposedUnit2Cycle5reloadlicenseapplication.

Specifically, theproposedchangereflectsanadditional limitation onthenuclearenthalpyrisehotchannelfactor(FI"),duetothenewLOCA/ECCS bHanalysis.

Theanalysiswasperformed insupportoftheCycle5reloadasaresultofyourstaff'sreview.Attachment 1tothisletterprovidestheresultsandbasesofthenewLOCA/ECCS analysisasitrelatestoF><.Theanalysiswasperformed byourfuelsvendor(ExxonNuclear,Co.).Theresultsofthisanalysiswerenotavailable tousuntilMay18,1984.WemetwithyourstaffonMay18,1984inanopenmeetingtodiscusstheresultsofthenewanalysisandoursuggested T/Schanges.WehaverevisedtheproposedT/SbasedontheNRC'scomments.

DuetothefactthatourUnit2startup(i.e.,entryintoMODE4)iscurrently scheduled forJune10,1984andthatwe,wereonlyabletoverifytheneedfortheproposedchangeveryrecently, werequestthatthetimefornoticeandpublication intheFederalRegisterbeshortened onschedulecommensurate withourscheduled reloadstartupdate;Basedonourreview,theproposedchangetothetechnical specification isbasedonanalytical methodswhichweweretoldwerefoundacceptable totheNRC.Inaddition, theresultsoftheanalysisarewithinallacceptance criteriawithrespecttotheECCS.Therefore, webelievetheproposedchangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.Inaddition, sincetheproposedT/Skeepstheplantwithinalldesignbases,thechangewillnotadversely impacttheenvironment.

':.8405290295 840521,'PDRADOCK05000316.sp;PDR CpPgIII Mr.HaroldR.DenAEP:NRC:0860KAttachment 2tothislettercontainstheproposedrevisedT/Spages.Thechangesareindicated byverticalbarsdrawnontherighthandmarginofthepage.TheproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextmeeting.Pursuanttotherequirement of10CFR50.91(b)(1),

acopyofthisletteranditsattachments havebeentransmitted totheStateofMichigan.

Inaddition, commensurate withourrequestforshortening theperiodfornoticeandpublication intheFederalRegister, wenotifiedtheStateofMichiganby,telephone onMay21,1984ofthisrequested amendment toourT/S.Weconsiderthisapplication foralicenseeamendment tobepartoftheapplication submitted inourletterAEP:NRC:0860.

Therefore, weinterpret.

10CFR170.22asnotrequiring anyadditional paymentsforprocessing theaforementioned request.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyand,completeness

'priortosignature bytheundersigned.

VerytrulyyourIM.P.AlehachVicePreidentMPA/dewAttachment cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffE.R.Swanson,NRCResidentInspector

-Bridgman 0J!'1pl,I1IapIllE Mr.HaroldR.DentAEP:NRC:0860K ATTACHMENT 1TheLOCA/ECCS analysisforUnit2,Cycle5operation withuptofivepercent(5%)ofthesteamgenerator tubespluggedwasperformed byExxonNuclearCo.(ENC).Theanalysiswasperformed usingtheEXEM/PWRmodelwithchangesasexplained intheENCletterJCC:076:84 datedMay7,1984.LetterJCC:076:84 wastransmitted toyouinourletterAEP:NRC:0860F, datedMayll,1984.TheresultsofthenewECCS/LOCA analysisarepresented intheattachedTables2.1,3.2,3.4,andFigures3.41,3.42,and3.43.Forbreaksuptoandincluding thedouble-ended severance o'fareactorcoolantpipe,thenewanalysisshowedthattheUnit2Emergency CoreCoolingSystemwillmeettheacceptance criteriaaspresented in10CFR50.46foroperation withENC17x17fueloperating inaccordance withthepeakingfactorlimitsnotedinTable2.1.Thatis:1.Thecalculated'eak fuelelementcladtemperature odoesnotexceedthe2200Flimit.2.Theamountoffuelelementcladdingthatreactschemically withwaterorsteamdoesnotexceed1%ofthetotalamountofzircaloyinthereactor.3.Thecladdingtemperature transient isterminated atatimewhenthecoregeometryisstillamenabletocooling.Thehotfuelandcladdingoxidation limitsof17%arenotexceededduringorafterquenching.

4.Thecoretemperature isreducedanddecayheatisremovedforanextendedperiodoftime,asrequiredbythelong-lived radioactivity remaining inthecore.BasedonthenewLOCA/ECCS analysisperformed, thelimitonFH,is1.415.Whenincludedinthe,T/S,thisvalueisreducedby40toaccountformeasurement uncertainty.

ThustheF<limitforoperation athHAH100%poweris1.36.Xnadditiontotheabovelimitation, itwasalsonecessary tochangetheallowance forincreased F~basedonreducedpowerwhenF~<islimited,AHH.byECCSanalyses, butnotlimitedbyDeparture fromNucleateBoiling(DNB).Thischangeisreflected bythephrase"F<~~1.36/PforExxonNuclearCo.fuel"includedintherevisedTechnical Specifications.

e'I14~(I~gPhCP'IgPdW'g~i,'1)VCf.>JVfII)pIIiU'"~"(1IIItI'I.'lIlQ)'V$fLlf%'J'lLf'lgI'Ilci'I Mr.HaroldR.Denf<JAEP:NRC:0860K bc:J.G.Feinstein J.M.Cleveland/G.

L.John/V.Vanderburg H.N.Scherer,Jr./S.H.Horowitz/R.

C.CarruthR.F.Hering/S.

H.Steinhart/J.

A.KobyraR.W.Jurgensen R.F.KroegerT.P.Beilman-BridgmanJ.F.Stietzel-BridgmanB.H.Bennett/F.

S.VanPelt,Jr.J.B.ShinnockD.Wigginton, NRC-Washington, D.C.,AEP:NRC:0860K DC-N-6015.1 DC-N-6485

'NMFM233

,1f4'r~Jf3l'IwfI'I