ML17332A556

Proposed Tech Specs to Incorporate 2.0 Volt Interim Steam Generator Tube Support Plate Plugging Criterion for Fuel Cycle 15

ML17332A556
Person / Time
Site:	Cook
Issue date:	02/03/1995
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
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ML17332A555	List: ML17332A553 ML17332A556
References
NUDOCS 9502130202
Download: ML17332A556 (19)

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ATTAQiMENT 2TOAEP'NRC:1166/

EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES9502130202 950203PDRADQCK050003i5PPDR CI

~iEACTORCOOLANTSYSTEMSURVEILLANCE REQUIRE."KNTS 2.Tubesinthoseareaswhereexperience hasindicated potential problems'.

Atubeinspection (pursuant toSpecification 4.4.5.4.a.8) shallbeperformed oneachselectedtube.Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatubeinspection, thisshallberecordedandanadjacenttubeshallbeselectedandsubjected toatubeinspection.

c~Inadditiontothesamplerequiredin4.4.5.2.b.l through3,alltubeswhichhavehadtheWcriteriaappliedwillbeinspected intherollexpandedregion.Therollexpandedregionofthesetubesmaybeexcludedfromtherequirements of4.4.5.2.b.l.

d."Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4-2)duringeachinse'rvice inspection maybesubjected toapartialtubeinspection provided:

Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found..2.Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found./5e.Implementation ofthesteamgenerator tube/tube spportplateinterimpluggingcriteriaforonefuelcycle(Cycle4requiresa100Xbobbincoilinspection forhotlegtubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithknownouterdiameterstresscorrosion cracking(ODSCC)indications.

Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

InsectionResultsC-1Lessthan5Xofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

C-2Oneormoretubes,butnotmorethan1Xofthetotaltubesinspected aredefective, orbetween5XandlOXofthetotaltubesinspected aredegradedtubes.C-3Morethan10Xofthetotaltubesinspected aredegradedtubesormorethan1Xoftheinspected tubesaredefective.

COOKNUCLEARPLANT-UNIT13/44-8AMENDMENT NO.~,~,~,178 REACTORCOOPTSYSE'HSSURVE'ZLLANC REUTR:-.M:-NTS Cont'uedbThesteamgenerator shallbedetermined OPERABLEaftercompleting thecorresponding actions(plugging orsleevingalltubesexceeding therepairlimitandalltubescontaining through-wall cracks)requiredbyTable4.4-2.CeSteamgeneatortuberepairsmaybemadeinaccordance withthemethodsdescribed ineitherWCAP-12623 orCEN-313-P.

4.4.5.5eortsacb.Following eachinservice inspection ofsteamgenerator tubes,ifthereareanytubesrequiring pluggingorsleeving, thenumberoftubespluggedorsleevedineachsteamgenerator shallbereportedtotheCommission within15days.Thecompleteresultsofthesteamgeneatortubeinservice inspection shallbeincludedintheAnnualOperating Reportfortheperiodinwhichthisinspection wascompleted.

Thisreportshallinclude:1.Numberandextentoftubesinspected.

2~Locationandpercentofwall-thickness penetration foreach.indication ofanimperfection.

C~de3.Identification oftubespluggedorsleeved.Resultsofsteamgenerator tubeinspections whichfallintoCategoryC-3andequirepromptnotification oftheCommission shallbereportedpursuanttoSpecification 6.9.1priortoresumption ofplantopeation.Thewrittenfollowupofthisreportshallprovideadescript'on ofinvestigations conducted todetermine causeofthetubedegradation andcorrective measurestakentopreventrecurrence.

Theresultsofinspections performed under4.4.5.2foralltubesinwhichthetubesupportplateinterimpluggingcriteriahasbeenappliedorthathavedefectsbelowtheF+distanceandwerenotpluggedshallbereportedtotheCommission within15daysfollowing theinspection.

Thereportshallinclude:Listingofapplicable tubes.2~Location(applicable intersections pertube)andextentofdegradation (voltage).

e.Theresultsofsteamlinebreakleakageanalysisperformed underT/S4.4.5.4.a.lO willbereportedtotheCommission priortorestartforCycle~.l~COOKNUCLEARPLANT-UNIT13/44-12KKNDHENTNO.+S&g466p+iip178

~~~~~REACTORCOOLANTSYSTEMO>ERATIONAL LEAKAGEIMITINGCONDITION FOROPERATION 3.46.2ReactorCoolantSystemleakageshallbelimitedto:a.'oPRESSUREBOUNDARYLEAKAGEtb.1GPMUNZDENTZFZED LEAKAGEtCoe.600gallonsperdaytotalprimary-to-secondary..leakage,.through allsteamgenerators and150allonsperdaythroughanyonesteamgenerator forFuelCycle4I10GPMIDENTIFIED LEAKAGEfromtheReactorCoolantSystem,Seallineresistance greaterthanorequalto2.27E-1ft/gpm~and,1GPMleakagefromanyreactorcoolantsystempressureisolation valvespecified inTable3.4-0.APPLICABILITY MODESlg2,3and4.<<<<~CTION:a.b.CoWithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandin'COLDSHUTDOWNwithinthefollowing 30hours.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excluding PRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.Withanyreactorcoolantsystempressureisolation valve(s)leakagegreaterthantheabovelimit,exceptwhen:Theleakageislessthanorequalto5.0gpm,and2~Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage<<byanamountthatreducestheTosatisfyALARArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations showingthatthemethodiscapableofdemonstrating valvecompliance withtheleakagecriteria.

Specification 3.4.6.2.e isapplicable withaveragepressurewithin20psiofthenominalfullpressurevalue.COOKNUCLEARPLANTUNIT13/44-16AMENDYZNT NO.46&,+66,].78OrderdatedApril20,1981

~~~JVREACTORCOO~TSYSBASES34.4.5SEAMGENERATORS TUBEINTEGRITY TheSurveillance Requirements forinspection ofthesteamgenerator tubesensurethatthestructural integrity ofthisportionoftheRCSwill'bemaintained.

Theprogramforinservice inspection afsteamgenerator tubesi.sbasedonamodification ofRegulatory Guide1-83,Revision1.Znservice inspection ofsteamgenerator tubingisessential inordertomaintainsurveillance oftheconditions cifthetubesintheeventthatthereisevidenceofmechanical damageorprogressive degradation duetodesign,manufacturing errors,orinservice conditions thatleadtocorrosion.

Znservice inspection ofsteamgenerator tubingalsoprovidesameansofcharacterizing thenatureandcauseofanytubedegradation sothatcorrective measurescanbetaken.Theplantisexpectedtobeoperatedi.namannersuchthatthesecond-arycoolantwillbemaintained withinthosechemistry limitsfoundtornegligible corrosion ofthesteamgenezator tubes.Zfthesrycoolantchemistry i.snotmaintained withintheseparameter limitcalizedcorrosion maylikelyresultinstresscorrosion cracking.

Theentofcrackingduri.ngplantoperation wouldbelimitedbythelimi.onofsteamgenerator tubeleakagebetweentheprimarycoolantsystemesecondary coolantsystem.Theallowabeprimary-to-secondary leakts150gallonsperdaypersteamgenerator foronefuelcycle(Cycle.Axialorcircumferent'ally orientedcackshavingaprimary-.to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetyto.'withstand theloadsimposedduringnormaloperation andbypostulated accidents.

Leakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

Asteamgeneatorwhileundergoing creviceflushinginMade4isavailable fordecayheatremovalandisoperable/operating uponreinstatement ofauxiliary ormainfeedflowcontrolandsearncontrol.Wastage-type defectsareunlikelywiththeallvolatiletreatment (AVT)ofsecondaycoolant.However,evenifadefectofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled inservice steamgenerator tubeexaminations.

Pluggingorsleevingwillberequiredforalltubeswithimperfecionsexceeding

.therepairlimitwhichisdefinedinSpecification 4.4.5.4.a.

Steamgenerator tubeinspections ofoperating plantshavedemonstrated thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthi.ckness.

Tubesexperiencing outerdiameterstresscorrosion crackingwithi.nthethickness ofthetubesupportplatesarepluggedorrepairedbythecriteriaof4.4.5.4.a.10.COOKNUCLEARPLANT-UNIT1B3/44-2aAYENDMENT NO.403,@Seesk66s178

~~~~~,~Ie REACTORCOOLANTSYSTEMBASESMaintaining anoperatileakagelimit,of150gpdpersteamgenerator (600gpdtotal)forFuelcycle4willminimizethepotential foralargeleakageevent,duringsteamlinezeakunderLocAconditions.

BasedontheNDEuncertainties, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousi.nspection, theexpectedleakratefollowing asteamlineruptureislimitedtobelow12.6gpmwhichwi.lllimitthecalculated offsitedosestowithin10percentof10CFR100guidelines.

Leakageintheintactloopsislimitedto150gpd.Zftheprojected endofcycledistribution ofcrackindications esultsinprimary-to-secondary leakagegreaterthan12.6gpminthefaultedloopduringapostulated steamlinebreakevent,additional tubesmustberemovedfromserviceinordertoreducethepostulated primary-to-secondazy steamlinebreakleakagetobelow12.6gpm.PRESSUREBOUNDARYLEAKAGEofanymagnitude i.sunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLEAKAGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperation maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsinceisolation removesthesourceofpotential failure.TheSurveillance Requirements forRCSpzessureIsolation Valvesprovideaddedassurance ofvalveintegrity therebyreducingtheprobability ofgrossvalvefailureandconsequent intersystem LOCA.LeakagefromtheRCSPressureIsolation ValvesisIDENTIFZED LEAKAGEandwillbeconsidered asaportionoftheallowedlim'it.34.4.7CH=MZSTRY Thelimitations onReactorCoolantSystemchemi.stry ensurethatcorzosion oftheReactorCoolantSystemisminimized andreducesthepotent'al forReactorCoolantSystemleakageorfailureduetostresscorrosion.

Maintaining thechemistry withintheSteadyStateLimitsprovidesadequatecorrosion protection toensurethestructural integrity oftheReactorcoolantSystemovertheli.feoftheplant.Theassociated effectsofexceedi.ng theoxygen,chlor:de, andfluoridelimitsaretimeandtemperature dependent.

Corrosion studiesshowthatoperation maybecontinued withcontaminant concentration levelsinexcessoftheSteadyStateLimits,uptotheTransient Limits,forthespecified limitedtimein"ervals withouthavingasi.gnificant, effect.onthestzuctural integrity oftheReactorCoolantSystem.Thetimeintervalpermitting continued operation withintherestrictions oftheTransient Limitsprovidestimefortakingcorrective actionstorestorethecontaminant concentrations towithintheSteadyStateLimits.COOKNUCLEARPLANTUNIT1B3/44-4AHENDHENT NO88g%44q178

~i'~~J~ATTACHMENT 3TOAEP:NRC:1166$

PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES r~~r EACTORCOOLANTSYSTSURVEILLANCE REUIREMENTS Contnued2.3.Tubesinthoseareaswhereexperience hasindicated poCential problems.

Atubeinspection (pursuant CoSpecification4.4.5.4.a.

8)shallbeperformed oneachselectedtube.Ifanyselectedtubedoesnotpermitthepassageoftheeddycurrentprobeforatubeinspection, thisshallberecordedandanadjacenttubeshallbeselectedandsubjected toatubeinspection.

c~Inadditiontothesamplerequiredin4.4.5.2.b.l through3,alltubeswhichhavehadtheWcriteriaappliedwillbeinspected intherollexpandedregion.Therollexpandedregionofthesetubesmaybeexcludedfromtherequirements of4.4.5.2.b.l.

d.Thetubesselectedasthesecondandthirdsamples(ifrequiredbyTable4.4-2)duringeachinservice inspection maybesubjected toapartialtubeinspection provided:

Thetubesselectedforthesamplesincludethetubesfromthoseareasofthetubesheetarraywheretubeswithimperfections werepreviously found.2.Theinspections includethoseportionsofthetubeswhereimperfections werepreviously found.e.Implementation ofthesteamgenerator tube/tube supportplateinterimpluggingcriteriaforonefue1cycle(Cycle15)requiresa100%bobbincoilinspection forhotlegCubesupportplateintersections andcoldlegintersections downtothelowestcoldlegtubesupportplatewithknownouterdiameterstresscorrosion cracking(ODSCC)indications.

~Theresultsofeachsampleinspection shallbeclassified intooneofthefollowing threecategories:

Cate~ox~C-lC-2C-3InsectonResultsLessthan5%ofthetotaltubesinspected aredegradedtubesandnoneoftheinspected tubesaredefective.

Oneormoretubes,butnotmorethan1%ofthetotaltubesinspected aredefective, orbetween5Sand10$ofthetotaltubesinspected aredegradedtubes.Morethan10%ofthetotaltubesinspected aredegradedtubesormorethan1$oftheinspected tubesaredefective.

COOKNUCLEARPLANT-UNIT13/44-8AMENDMENT NO.'OS,454,446,477-,

EACTORCOOLANTSYSTEMSSURVEILLANCE REUIREMENTS Continued b.c~Thesteamgenerator shallbedetermined OPERABLEaftercompleting thecorresponding actions(plugging orsleevingalltubesexceeding therepairlimitandalltubescontaining through-wall cracks)requiredbyTable4.4-2.Steamgenerator tuberepairsmaybemadeinaccordance withthemethodsdescribed ineitherWCAP-12623 orCEN-313-P.

4.4.5.5R~eortsa.b.Following eachinservice inspection ofsteamgenerator tubes,ifthereareanytubesrequiring pluggingorsleeving, thenumberoftubespluggedorsleevedineachsteamgenerator shallbereportedtotheCommission within15days.Thecompleteresultsofthesteamgenerator tubeinservice inspection shallbeincludedintheAnnualOperating Reportfortheperiodinwhichthisinspection wascompleted.

Thisreportshallinclude:l.Numberandextentoftubesinspected.

2.Locationandpercentofwall-thickness penetration foreachindication ofanimperfection.

C.d.e.3.Identification oftubespluggedorsleeved.Resultsofsteamgenerator tubeinspections whichfallintoCategoryC-3andrequirepromptnotification oftheCommission shallbereportedpursuanttoSpecification 6.9.1priortoresumption ofplantoperation.

Thewrittenfollowupofthisreportshallprovideadescription ofinvestigations conducted todetermine causeofthetubedegradation andcorrective measurestakentopreventrecurrence.

Theresultsofinspections performed under4.4.5.2foralltubesinwhichthetubesupportplateinterimpluggingcriteriahasbeenappliedshallbereportedtotheCommission within15daysfollowing theinspection.

Thereportshallinclude'.

1.Listingofapplicable tubes.2.Location(applicable intersections pertube)andextentofdegradation (voltage).

Theresultsofsteamlinebreakleakageanalysisperformed underT/S4.4.5.4.a.l0 willbereportedtotheCommission priortorestartforCycle15.COOKNUCLEARPLANT-UNIT13/44-12AMENDMENT NO.403,446,477, r~p04~&4.

CTORC0SYSOPERATIONAL LEAKAGEIMTINGCONDITION OROPERATION 3.4.6.2ReactorCoolantSystemleakageshallbelimitedto:a.b.c~d.e.NoPRESSUREBOUNDARYLEAKAGE,1GPMUNIDENTIFIED LEDGE,600gallonsperdaytotalprimary-to-secondary leakagethroughallsteamgenerators and150gallonsperdaythroughanyonesteam.generator forFuelCycle15,10GPMIDENTIFIED LEAKAGEfromtheReactorCoolantSystem,Seallineresistance greaterthanorequalto2.27E-1ft/gpm~and,1GPMleakagefromanyreactorcoolantsystempressureisolation valvespecified inTable3.4-0.~ACTI0a.b.C.WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excluding PRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithin,limitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours.Withanyreactorcoolantsyst:empressureisolation valve(s)leakagegreaterthantheabovelimit,exceptwhen:1.,Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage*byanamountthatreducestheTosatisfyALARArequirements, measuredleakagemaybemeasuredindirectly (asfromtheperformance ofpressureindicators) ifaccomplished inaccordance withapprovedprocedures andsupported bycomputations showingthatthemethodiscapableofdemonstrating valvecompliance wi.ththeleakagecriteria.

Specification 3.4.6.2.e isapplicable withaveragepressurewi.thin20psiofthenominalfullpressurevalue.COOKNUCLEARPLANT-UNIT13/44-16AMENDMENT NO.462,466,~OrderdatedApri.l20,1981 I~~r(tV"tt~I'P,l EACORCOOSYSTBASES3445STEAMGENERATORS TUBEINTEGRITY TheSurveillance Requirements forinspection ofthesteamgenerator.

tubesensurethatthestructural integrity ofthisportionoftheRCSwillbemaintained.

Theprogramforinservice inspection ofsteamgenerator tubesisbasedonamodification ofRegulatory Guide1.83,Revision1.Inservice inspection ofsteamgenerator tubingisessential inordertomaintainsurveillance oftheconditions ofthetubesintheeventthatthereisevidenceofmechanical damageorprogressive degradation duetodesign,manufacturing errors,orinservice conditions thatleadtocorrosion.

Inservice inspection oRsteamgenerator tubingalsoprovidesameansofcharacterizing thenatureandcauseofanytubedegradation sothatcorrective measurescanbetaken.Theplantisexpectedtobeoperatedinamannersuchthatthesecond-arycoolantwillbemaintained withinthosechemistry limitsfoundtoresultinnegligible corrosion ofthesteamgenerator tubes.Ifthesecondary coolantchemistry isnotmaintained withintheseparameter limits,localized corrosion maylikelyresultinstresscorrosion cracking.

Theextentofcrackingduringplantoperation wouldbelimitedbythelimitation ofsteamgenerator tubeleakagebetweentheprimarycoolantsystemandthesecondary coolantsystem.Theallowabeprimary-to-secondary leakrateis150gallonsperdaypersteamgenerator foronefuelcycle(Cycle15).Axialorcircumferentia'ily orientedcrackshavingaprimary>>to-secondary leakagelessthanthislimitduringoperation willhaveanadequatemarginofsafetytowithstand theloadsimposedduringnormaloperation andbypostulated accidents.

'eakageinexcessofthislimitwillrequireplantshutdownandaninspection, duringwhichtheleakingtubeswillbelocatedandpluggedorrepaired.

Asteamgenerator whileundergoing creviceflushinginMode4isavailable fordecayheatremovalandisoperable/operating uponreinstatement ofauxiliary ormainfeedflowcontrolandsteamcontrol.Wastage-type defectsareunlikelywiththeallvolatiletreatment (AVT)ofsecondary coolant.However,evenifadefectofsimilartypeshoulddevelopinservice,itwillbefoundduringscheduled inservice steamgenerator tubeexaminations.

Pluggingorsleevingwillberequiredfora'lltubeswithimperfections exceeding therepairlimitwhichisdefinedinSpecification 4.0.5.4.a.

Steamgenerator tubeinspections ofoperating plantshavedemonstrated thecapability toreliablydetectdegradation thathaspenetrated 20%oftheoriginaltubewallthickness.

Tubesexperiencing outerdiameterstresscorrosion crackingwithinthethickness ofthetubesupportplatesarepluggedorrepairedbythecriteriaof4.4.5.4.a.lO.

COOKNUCLEARPLANT-UNIT1B3/44-2aAMENDMENT NO.403,454,446,~

p(lgoi,I4~~sym REACTORCOOLANTSYSTEMBASESMaintaining anoperating leakagelimitof150gpdpersteamgenerator (600gpdtotal)forFuelCycle15willminimizethepotential foralargeleakageeventduringsteamlinebreakunderLOCAconditions.

BasedontheNDEuncertainties, bobbincoilvoltagedistribution andcrackgrowthratefromthepreviousinspection, theexpectedleakratefollowing asteamlineruptureislimitedtobelow12.6gpmwhichwilllimitthecalculated offsitedosestowithin10percentof10CFR100guidelines.

Leakageintheintactloopsislimitedto150gpd.Iftheprojected endofcycledistribution ofcrackindications resultsinprimary-to-secondary leakagegreaterthan12.6gpminthefault'edloopduringapostulated steamlinebreakevent,additional tubesmustberemovedfromserviceinordertoreducethepostulated primary-to-secondary steamlinebreakleakagetobelow12.6gpm.PRESSUREBOUNDARYLEAKAGEofanymagnitude isunacceptable sinceitmaybeindicative ofanimpending grossfailureofthepressureboundary.

ShouldPRESSUREBOUNDARYLEDGEoccurthroughacomponent whichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperation maycontinueprovidedtheleakingcomponent ispromptlyisolatedfromtheReactorCoolantSystemsinceisolation removesthesourceofpotential failure.TheSurveillance Requirements forRCSPressureIsolation Valvesprovideaddedassurance ofvalveintegrity therebyreducingtheprobability ofgrossvalve'failure andconsequent intersystem LOCA.LealcagefromtheRCSPressureIsolation ValvesisIDENTIFIED LEAKAGEandwillbeconsidered asaportionoftheallowedlimit.3447CHEMISTRY Thelimitations onReactorCoolantSystemchemistry ensurethatcorrosion oftheReactorCoolantSystemisminimized andreducesthepotential forReactorCoolantSystemleakageorfailureduetostresscorrosion.

Maintaining thechemistry withintheSteadyStateLimitsprovidesadequatecorrosion protection toensurethestructural integrity oftheReactorCoolantSystemoverthelifeoftheplant.Theassociated effectsofexceeding theoxygen,chloride, andfluoridelimitsaretimeandtemperature dependent.

Corrosion studiesshowthatoperation maybecontinued withcontaminant concentration levelsinexcessoftheSteadyStateLimits,uptotheTransient Limits,'for thespecified limitedtimeintervals withouthavingasignificant effectonthestructural integrity oftheReactorCoolantSystem.Thetimeintervalpermitting continued operation withintherestrictions oftheTransient Limitsprovidestimefortakingcorrective actionstorestorethecontaminant concentrations towithintheSteadyStateLimits.COOKNUCLEARPLANT-UNIT1B3/44-4AMENDMENT NO.53,444,~

~,r~~ll