ML17334A518

Application to Amend License DPR-74,revising Tech Specs Re Flowrate for Flow Balance Test of Safety Injection Pumps

ML17334A518
Person / Time
Site:	Cook
Issue date:	03/15/1984
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	DENTON H R Office of Nuclear Reactor Regulation
Shared Package
ML17326B107	List: ML17326B106 ML17334A518
References
AEP:NRC:0860A, AEP:NRC:860A, NUDOCS 8403200210
Download: ML17334A518 (8)

Text

REGULATORY INOR@ATIONDISTRIBUTION SYSTEM(RIDS)ACCESSION NBR8403200210DUC~DATE84/03/15NOTARIZEDNOFACIL:50316DonaldC.CookNuclearPowerPlantiUnit2~IndianaAUTHINANEAUTHORAFFILIATION ALEXICH~M.P.

IndianaIlMichiganElectricCo~RECIP,NAME RECIPIENT AFFILIATION DENTONtH~REOfficeofNuclearReactorRegulationr Director

SUBJECT:

Application toamenaLicenseDPH-74<revising TechSpecsreflowratefortlowbalancetestofsafetyinjection pumps'ISTRIBUTIUN CODE:IE2cSCOPIESRECEIVED:LTR ENCLSIZE:TITLE!Start-UpReport/RefuelingReport(50Dkt).NOTES:DOCKET¹05000316RECIPIENT IDCODE/NAME NRRORB1BC04INTERNAL:

IEFILE01'RR/DHFS'DIR 08NRR/OSI/CPBCOPIESLTTRENCL3111'11RECIPIENT IDCODE/NAME

.NRR/DHFSDEPY07NRR/DHFS/PSRB11 Rf/DDAMI/MIB 09COPIESLTTRENCL1]1EXTERNAL; ACRSNRCPDRNTIS.130251111LPDRNSIC0305lgTOTALNUHBEHOFCOPIESREQUIRED:

LTTR~ENCLb INDIANA&MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216March.15,1984AEP:NRC:0860A DonaldC.CookNuclearPlantUnitNo.2DocketNo.50-316LicenseNo.DPR-7'4AMENDMENT TOTHEAPPLICATION FORUNIT2TECHNZCAL SPECIFICATION CHANGESFORCYCLE5RELOADMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.,S.Nuclear.Regulatory Commission Washington, D.C.20555

DearMr.Denton:

Bythisletteranditsattachments, werequestanamendment totheapplication forTechnical Specification (T/S)changes,whichwasaddressed inourletterAEP:NRC:0860 datedMarch1,1984.Thisletterincludesadditional information relatedtotheseventhproposedchangeaddressed inAEP:NRC:0860; andrequestsoneadditional T/Schange.Thewordingoftheseventhchangehasbeenslightlymodifiedinthissubmittal tomakethechangeeasiertounderstand.

Attachment 1tothisletteraddresses theSignificant HazardsConsideration, asrequiredtobesubmitted by10CFR50.91(a)(1),forthemodifiedversionoftheseventhproposedchangeofletterAEP:NRC:0860.

Theseventhproposedchangeconcerned theflowratefortheflowbalancetestfortheSafetyIn'jection (SZ)pumps'heSIpumpflowratewouldbeaffectedbyplannedmodifications toincreasetheminiflowoftheSZpumps.Theincreased miniflowwouldprovideaddedassurance ofadequatepumpcoolingwhilethepumpisoperating butnotinjecting tothecore.Znordertomakethephysicalmodifications forthischangeonareasonable timetable,wearerequesting anearlyindication byMarch23,1984oftheacceptability ofthisT/Schangerequest.Attachment 2tothisletteraddresses theadditional T/Schangethatisbeingrequested aspartoftheUnit2Cycle5reloadapplication andourSignificant HazardsConsideration analysispursuantto10CFR50.92forthischange.Attachment 3tothislettercontainstherevisedpagesfortheadditional T/Schanges(including themodifiedversionoftheseventhchangeproposedinAEP:NRC:0860).

Thechangestotherevisedpagesare84032002l0 8403l5PDR*DOCK0500031hPPDRgrad>~.g~filee/I Mr.HaroldR.Dent~~AEP:NRC:0860A indicated byverticallinesontheright,handmaxginofthepage.TheT/Schangecontained inthisAttachment hasbeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheAEPSCNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextscheduled meeting.Attachment 4tothisletteristhesummaryofthesafetyevaluation performed byWestinghouse tosupportanincreasefrom30gpmto60gpminthesafetyinjection pumpminiflow.Asrequiredby10CFR50.91(b)(1),

acopyof.thisamendedapplication isbeingtransmitted totheappropiiate officialoftheStateofMichigan.

Ourletter'EP:NRC:0860 transmitted theClassIVfeeleviedforthereviewoftheCycle5reloadofUnit2.WeconsidertheTechnical Specification changerequestscontained inthislettertobepartofthatx'eview.Therefox'e, webelievethatnofee,asdefinedin10CFR170.22,.isrequiredfortherequestsaddressed inthisletter.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate a.reasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.

Verytrulyyours,q5~M.P.exich4;~'VicePresident MPA/pbAttachments cc:JohnE.DolanW.G;'Smith, Ji.-BridgmanR.C.CallenG.CharnoffE.R.Swanson,NRCResidentInspector

-Bridgman Mr.HaroldR.DentonAEPNRC0860AATTACHMENT 1TOAEP:NRC:0860ASIGNIFICANT HAZARDSCONSIDERATICN FORCERNGEINFLCNRATEFORTHESAFEZYINJECTICN PUMPSFECNBALAN~TEST

'Mr.HaroldR.DentoAEP:NRC:0860A Theseventhproposedchangeaddressed inletterAEP:NRC:0860 requested thefootnote(**)onpage3/45-6forT/S4.5.2.hbechangedtoread:**TotalSIS(singlepump)flow,including miniflow/shallnotexceed700gpmwithnomorethan640gpmbeingdelivered tothecore.Werequestthatthisproposedchangebemodifiedforclarity,toread:**Combined Loop1,2,3,and4ColdLegFlow(singlepump)(640gpm.TotalSIS(singlepump)flow,including

miniflow, shallnotexceed700gpm.Theabovechangewillallowforincreased (miniflow) coolingoftheSafetyInjection pumpswhichprovidesincreased assurance ofadequate*pumpcoolingwhileusingminiflowcooling.Theincreaseinminiflowmayresultinasmalldecreasei:nflowfrom'thepumpstothecore.Westinghouse hasperformed asafetyevaluation oftheincreased SIpumpminiflowanddecreased injection flowtothecore.Thesummaryoftheirevaluation isenclosedasAttachment 4.Theresultsoftheirevaluation concluded thattheimpact'snegligible forlargebreakLOCAandan0increaseof86.1Finpeakcladtemperature (PCT)forthemostlimitingsmallbreakLOCA,basedonasensitivity analysisperformed onUnit1.TheadditionofthisincreaseinsmallbreakLOCAPCTtothecurrentD.C.CookUnit2smallbreakLOCAPCTof1668Fresultsina0valuewellbelowthe10CFR50.46limitof2200F.Basedondiscussions 0withyourstaff,weunderstand furtherinformation regarding theWestinghouse evaluation isneeded.Therefore, wewillsubmitadditional clarification oftheevaluation inthenearfuture.Wehavealsoperformed areviewoftheproposedflowrateontheintegrity oftheSIpumps.Ourreviewincludedacalculation todetermine theNetPositiveSuctionHead(NPSH)available totheSafetyInjection (SI)pumps.Inthecalculation weassumedthatSIwasintheinjection phaseandalignedwiththeRefueling WaterStorageTank(RWST);theRWSTwasatit'slowlowlevelsthewatertemperature was0100F;allsafetypumpswererunning(i.e.,ResidualHeatRemoval,Containment Spray,Centrifugal

Charging, andSIpumps);andallpumpswereproducing maximumflow.Webelievetheassumedconditions constitute theworstcaseconditions fortheSIpumps.Theresultsofthecalculation indicated thatwiththeaboveconditions, therewouldbeaNPSHmarginofoversixteen(16)feetforbothoftheSIpumps.Therefore, theincreased flowrateiswithinthesafetyboundsofthepumprunoutandhasnosignificant adverseeffectontheintegrity ofthepumps.Basedontheabove,theproposedT/Schangemayresultinsomeincreasetotheconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,butitisourbeliefthattheresultsofthechangeareclearlywi.thinallacceptable criteriawithrespecttothesystemandcomponent's astheymayaffecttheSafetyAnalysisoftheplant.Thustheproposedchangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.

Mr.HaroldR.Dento-5-AEP:NRC:0860A ATTACHMENT 2TOAEP:NRC:0860A ADDITIONAL TECHNICAL SPECIFICATION CHANGEREQUESTFORDONALDC.COOKNUCLEARPLANTUNITNO.2CYCLE5 Mr.HaroldR.Den-6-AEP:NRC:0860A TheeighthproposedchangeconcernsT/S3/4.10.5whichaddresses theRodPositionIndication (RPI)Channelsduringshutdown(MODES3,4,and5).Specifically, wearerequesting thatT/S3/4.10.5bechangedtoaddressthedemandpositionindicators insteadoftheindividual RPXs.Thereasonsandjustification forthischangeareasfollows:T/S4.1.3.4requiresroddroptimemeasurements offulllengthrodsbedemonstrated

...following eachremovalofthereactorvesselhead,etc.T/S4.10.5statesrodpositionindication channelsshallbedetermined tobeOPERABLEbyverifying thedemandpositionindication systemandtherodpositionindication channelagreewithin12stepswithin24hourspriortothestartofroddroptimemeasurement...

Znordertoverifythe12stepagreement betweentheindividual RPZsandthedemandpositionindication system,theindividual RPIshavetobecalibrated.

TheRPZforeachindividual rodiscalibrated atthe~beginning ofafuelcyclewhenthereactorcoolantsystemisatoperating temperature.

Calibration isperformed atoperating temperature becausetheRPIsareextremely temperature sensitive andtherefore becomeincreasingly inaccurate overthelargetemperature changebetweenMODES5through3.Coiloperating temperature isnotestablished untiltheReactorCoolantSystem(RCS)reachesequilibrium afterascending throughMODES5,4,and3..Thecoiltakesapproximately six(6)hourstoreachequilibrium temperature, thusdelayingstartupofthereactor.Utilityexperience indicates thatthe(group)demandpositionindication systemshaveproventobeextremely reliableinWestinghouse reactors.

Demandpositionindication systemsarethemostaccuratemeansofdetermining rodpositionandareinfactusedtocalibrate theRPXs.Furthermore, theT/Ssrequirethatthereactorbemaintained inasubcritical, condition (k(0.99)topreventinadvertent criticality inMODES3,4,and5.Subcriticality canbeadequately maintained withsufficient boronconcentration andallbutoneshutdownorcontrolbankbeingfullyinserted.

Criticality isnormallynotreacheduntiltheshutdownbanksandthreeofthefourcontrolbanksarefullywithdrawn.

T/S3.10.5willcontinuetorequireonlyoneshutdownorcontrolbankbewithdrawn fromthefullyinsertedpositionatatime,duringroddroptimemeasurements.

Therefore, webelievethereisadequatejustification.

fortheproposedchange,whichwouldeliminate thedelayinstartup.Thischangemayresultinsomeincreasetotheprobability orconsequences ofaprev'ously analyzedaccidentormayreduceinsomewayasafetymargin,butitisourbeliefthattheresultsofthechangeareclearlywithinallacceptable criteriawithrespecttothesystemorcomponents astheymayaffecttheSafetyAnalysisoftheplant.Thus,theproposedchangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CPR50.92.

Mr.HaroldR.DentonAEP:NRC:0860AATTACHMENT 3TOAEP:NRC:0860A REVISEDTECHNICAL SPECIFICATION PAGESFORTHESEVENTHANDEIGHTHPROPOSEDCHANGES