ML17261A865

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Clarifies & Suppls 890106 Response to Violations Noted in Insp Rept 50-244/88-22.Subsequent to 881005 & Prior to Initial Response,Manual Valve 4318A Locked in Closed Position & Added to Locked Valve Program
ML17261A865
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/17/1989
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To: RUSSELL W T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.1, TASK-2.E.1.2, TASK-TM NUDOCS 8903020621
Download: ML17261A865 (32)


See also: IR 05000244/1988022

Text

'cCEMRATEDD1STKBt'EON

DEMONSTRXT10.i

H'STEMREGULATORY

INFORMATION

DISTRIBUTION

SYSTEM(RIDS)SSIONNBR-8903020621

DOC.DATE:

89/02/17NOTARIZED-

NODOCKETCIL:50-244

RobertEmmetGinnaNuclearPlant,Unit1,Rochester

G05000244AUTH.NAMEAUTHORAFFILIATION

MECREDY,R.C.

Rochester

Gas&ElectricCorp.RECIP.NAME

RECIPIENT

AFFILIATION

RUSSELL,W.T.

Region1,OfcoftheDirectorSUBJECT:Forwardsaddiinfoto890106responsetoInspRept50-244/88-22.

DISTRIBUTION

CODE:IEOIDCOPIESRECEIVED:LTR

1ENCLQSIZE:jTITLE:General(50Dkt)-Insp

Rept/Notice

ofViolation

ResponseNOTES:License

Expdateinaccordance

with10CFR2,2.109(9/19/72).

05000244~

RECIPIENT

IDCODE/NAME

PD1-3PDINTERNAL:

AEODDEDRONRR/DESTDIRNRR/DLPQ/QAB

10NRR/DREP/EPB

10NRR/DRISDIR9ANUDOCS-ABSTRACT

OGC/HDS2RGN1FILE01EERNAL:LPDRNSICCOPIESLTTRENCL111111111111111111111111RECIPIENT

IDCODE/NAME

STAHLE,CAEOD/DEIIB

NRRSHANKMAN,

SNRR/DLPQ/PEB

11NRR/DOEADIR11NRR/DREP/RPB

10NRR/PMAS/ILRB12

01EBEJREGFILE0NRCPDRCOPIESLTTRENCL11111111112211111111NCTE'ZOALL"RIDS"RZCIPIZNIS:

PZZASEHELPUS10REDUCEHASTE!CCÃZACZ'IHEDOCUMENZCDPXBOLDESK,ROOMPl-37(EXT.20079)K)ELIMINATE

VÃ3RHMEFRYDIPIVUBUTIGN

LISTSFORDOCUMENTS

YOUDGNITNEEDfTOTALNUMBEROFCOPIESREQUIRED:

LTTR23ENCL23

February17,1989Mr.WilliamT.RussellRegionalAdministrator

U.S.NuclearRegulatory

Commission

RegionI475Allendale

RoadKingofPrussia,Pennsylvania

19406Subject:Supplemental

Information

Inspection

Report88-22R.E.GinnaNuclearPowerPlantDocketNo.50-244.DearMr.Russell:Followingsubmittal

ofourresponse,

datedJanuary6,1989toInspection

Report88-22,wehavediscussed

withmembers'f

.yourStaffboththespecificissuesraisedintheInspection

ReportandthemoregeneralsubjectoftheCondensate

StorageTankdesignandoperational

considerations.

Basedonthesediscussions

andourfurtherreview,webelieveit,appropriate

toclarifyandsupplement

ourpreviousresponse.

Theadditional

information

generally

fallsinthreeareas.First,weareclarifying

ourresponsetoindicatethatonOctober5,1988,manualvalve4318Awasbeingmaintained

asaclosedvalve.Subsequently,

andpriortoourresponsetotheInspection

Report,valve4318Awaslockedintheclosedpositionandwasadded.toourlockedvalveprogram.Second,wehaveperformed.

a.50..59safetyevaluation

ofthepresenceofmanualvalve4318AintheCondensate

StorageTanksystem.Basedonreviewstodate,wehavedetermined

thatvalve4318Ahasbeeninstalled

attheplantforanumberofyears,however,wehavenotbeenabletodocumentwhetheritwaspartoftheoriginalplantdesignorwasinstalled

afterinitiallicensing.

Therefore,

wehaveperformed

theattached50.59safetyevaluation

andhavedetermined

thatthepresenceofthevalvedoesnotconstitute

anunreviewed

safetyquestionorinvolveachangeintheplantTechnical

Specifications.

2Finally,wewishtore-emphasize

apointcontained

inouroriginalresponse.

Inadditiontothespecificreviewswhichwehaveperformed

asidentified

inourpreviousresponseandinthisresponse,

weareperforming

acomprehensive

reviewoftheCondensate

StorageTankincluding

allconnecting

lines.Thisreviewisconsidering

allpreviousplantdesignrequirements

andalsoStationBlackout(lossofallAC)considerations.

Ourresponses

totheInspection

Reportdonotaffectourintenttocompletethisimportant,

evaluation.

PleasecontactusifyouormembersofyourStaffhavefurtherquestions

orconcerns.

Verytrulyyours,RobertC.MeredyGeneralManagerNuclearProduction

RCMN021Attachments

xc:U.S.NuclearRegulatory

Commission

(original)

~~~~DocumentControlDeskWashington,

D.C.20555xc:GinnaSeniorResidentInspector

L

ATTACHMENT

IViolation

"10CFR50,AppendixB,sectionIIIrequires,

inpart,measuresshallbeestablished

toassurethatappropriate

qualitystandards

arespecified

andincludedindesigndocuments,

anddeviations

fromsuchstandards

arecontrolled.

TheQualityAssurance

ManualGinnaStation,section3,step3.1.3requiresmodifications

involving

achangetothefacilityasdescribed

intheUpdatedFinalSafetyAnalysisReport(UFSAR)haveasafetyevaluation

inaccordance

with10CFR50.59"Contrary

totheabove,onOctober5,1988amodification

involving

achangetotheCondensate

StorageTank,described

inChapterl0oftheUFSARasthemainsourceofwaterfortheAuxiliary

Feedwater

System,wasinstalled

withoutasafetyevaluation

inaccordance

with10CFR50.59."R~esonseRG&Edeniesthisviolation.

RG&EagreesthattheGinnaQAmanualspecifies

thata50.59evaluation

should,beperformed

foranyfacilitymodification

involving

achange.tothefacilityasdescribed

intheUFSAR.However,wedonotagree.thattheaddition'oftheTygontubingtotheCondensate

StorageTanksconstitutes

suchachange.WhatisshownintheUFSARandwasexistingplantconfiguration

isa3/4inchsamplinglinewhichisisolatedbyclosedmanualvalve4318A(UFSARFigure10.7-5).Thisconfiguration

wasnotchangedbytheadditionoftheTygontubeonOctober5,1988.TheTygontubehasbeenaddeddownstream

ofthisvalveanddoesnotaffecttheCSTs.asexplicitly

described

intheUFSAR.Evenifweconsider(andwedid)theapplicability

of10CFR50.59toitemsimplicitly

described

intheUFSAR,currentdraft(December

1988)industryguidancedefinesthisimplicitinclusion

ordescription

asfollows:"Ifthechangealtersthedesign,function,

ormethodofperforming

thefunctionofthelargerstructure,

system,orcomponent

[inthiscasetheCSTs]asdescribed

intheSARthenasafetyevaluation

isrequired."

BecausetheTygontubewasinstalled

beyondamanualclosedvalveitwasandstillisunderstood

thatthismodification

doesnotaltertheCSTs'esign

functionormethodofperformance.

Inaddition,

anyfailureoftheTygontubingcannotinteractwiththeCSTsoraffectanyofthesurrounding

equipment..

(Itshouldbenotedthatvalve4318Aisnowmaintained

lockedclosedunderourlocked,valveprogram.)

When.thismodification

wasmadebyRG&E,theappropriate

consideration

wasgiventothegoverning

requirements

of10CFR50.59.Appropriate

screening

criteriawereappliedtodetermine

theapplicability

of*10CFR50.59.Althoughthedocumentation

maintained

forscreening

thismodification

andconcluding

that50.59didnotapplywasbrief,goodengineering

judgmentwasimplemented

anddocumentation

wasprovided.

RG&Ebelievesthatthedocumentation

supporting

thismodification

adequately

addresses

thesafetyissues.Becausewebelieveintheimportance

ofproperlyapplyingthe50.59requirement,

wehavecontinued

toinstitute

additional

programmatic

guidanceonimplementing

10CFR50.59.Additional

ReviewAmoredetailedreviewoftheadditionoftheTygontubinghasbeendocumented

(seeAttachment

III).Evenunderthescrutinyofa50.59safetyevaluation

(asenclosed),

anUnreviewed

SafetyQuestion(USQ)doesnotresult.ProrammaticImrovements

Asdiscussed

inAttachment

II,aprogrammatic

approachto50.59hasbeenandiscontinuing

tobedeveloped

atGinna.Procedures

havebeenwrittentoensurethatappropriate

screening

criteria,formsarefilledoutinaccordance

withtheGinna50.59program.Thesescreening

formsprovideadequatebasisfor.applying50.59.on*acase-by-case

basis,andwillprovidefor'nadequatedocumentation

ofthebasisfortheconclusions

oftheapplicability

screen'ing

inthosecaseswhere50.59doesnotapply.Inaddition,

RG&Eisinstituting

trainingprogramsontheimplementation

of50.59tomakecertainthatallpersonnel

involvedinperforming

suchevaluations

understand

theRG&E50.59programand'hetechnical

considerations

involvedinapplyingtheprogrammatic

guidance.

Inthefuture,RG&Ewillbeconsidering

theconsolidation

oftheseveralexisting50.59reviewprograms,

suchasthoseforprocedure

reviewsand'Nonconformance

Reportreviews,intoasingleprogram.Thecurrentprogramsdo,however,adequately

addresstherequiredreviews.DateofFullComlianceRG&Ebelievesitiscurrently

incompliance

with10CFR50.59andwiththeGinnaQualityAssurance

Manualasitrelatestotheissuesidentified.

~iQ'IIQ'QgCVQVP%lgpP(v~~

ATTACHMENT

III.Introduction

Inadditionto'addressing

theNoticeofViolation,

weareresponding

tosomeoftheStaff'sassociated

concernsraisedwithintheinspection

reportitself.WewouldliketheStafftounderstand

thestatusofourprograms,

including

thecriticalreviewofourmodification

processandtheinstitution

ofour50.59process.WebelievethatitisevidentthatRG&Ehasaclearunderstanding

ofnotonlytheconcernsexpressed

inthisinspection

report,buttheevolvingconcernsthatrelatetotheseindustrywideissues.ItisourintentthattheStaffunderstand

thatwehavemadestridesindeveloping

comprehensive

programsthatnotonlyaddressconcernsinaspecificmanner,butlookatthebroaderpictureandcanbeseenasanoverallimprovement.

II.50.59ProramImrovements

IqthebodyofInspection

Report88-22,theNRCexpressed

aconcernthatRG&E'sfailuretoperformSafetyEvaluations

hasbeenanNRCidentified

concernformorethan20monthsandisindicative

ofprogrammatic

weaknessin'thecontrolofstationmodifications.

GinnaStationprocedures

areclearintherequirement

todevelopaSafetyEvaluation

insupportofmodifications.

Inadditiontoreviewing

physicalchanges,RG&Ehasadetailedscreening

programand.50.59guidanceforrevisions

madetoprocedures.

Thesafetyevaluation

processforbothmodifications

andprocedure

changeshasbeenimprovedthroughthecontinuing

development

ofdetailedguidance.

Thisguidancedocuments

theimpactsthateachevaluator

mustconsiderforaspecifictypeofchange.Specificexamplesforthesechangesarealsoprovided.

RG&Ehastakenapositiveapproachtodealingwiththe10CFR50.59process.Inmanyrespects,

thishasbeendifficult

becauseoftheevolvingnatureofNRC/industry

guidanceinthisarea.Thisisevidenced

bythefactthateventhemostrecentindustryguidanceisstillconsidered

adraft.Also,aspartofthiseffort,RG&Ewillconducttheretraining

ofaffectedpersonnel.

Thiswillincludediscussion

ofspecificprocedural

requirements,

identified

interfaces,

andtherequirements

oftheGinna50.59program.Anotherconcernexpressed

bythestaffwasthatRG&Eisnotperforming

50.59evaluations

forallmodifications

thatinvolveplantequipment

described

intheUFSAR.RG&Eiscommitted

totherequirements

toperform50.59evaluations,

butdoesnotbasethisdecisiontoperforma50.59evaluation

simplyonwhetherornotthe~4~~y

equipment

isdescribed

intheUFSAR.Itisourposition.thatifachangeaffectsthefacility,

asdescribed

intheUFSAR,eitherexplicitly

orimplicitly,

a50.59evaluation

shouldbecompleted.

Thisisnotourlastdetermining

factor,however.RG&Econservatively

appliestherequirements

of50.59withoutlosingperspective

ontheintentoftheregulation.

RG&Ebelievesthatthisregulation

mustbeappliedsothatitremainsmeaningful.

Wehavedeveloped

clear.safetyevaluation

guidance,

andextensive

screening

criteriatoaccomplish

thisgoal.Wehavedonethisinanefforttonotrelyexcessively

uponthehighlevelofengineering

expertise

ofourexistingpersonnel,

buttofurnishclearprogrammatic

controls.

Weunderstand

thatthisprogramdevelopment

hastakentimeandisstillunderway,

butwebelievethattheStaffshouldbeawarethatwesawtheneedforsuchguidanceandhavetakenappropriate,

steps.RG&Ehasneitherignorednordownplayed

theStaff'sconcerns,

buthassystematically

setupanoverallsystemtoaddresstherootcauseofthoseproblems.

III.GDC-34ConcernsAnotherissueraisedaspartoftheInspection

ReportisthattheRG&Ereview"doesnotaddresswhethergoodcommercial-grade

engineering

practices

meetstherequirements

ofGeneralDesignCriterion

(GDC)34".Thefollowing

discussion

providessupplemental

information

toclarifythisterminology

andplaceitinacontextthatmoreaccurately

reflectsRG&E'spastpractices

regarding

thedesignandqualityassurance

controlsappliedtotheCSTs.IrTheR.E.GinnaNuclearPowerplantwasdesignedtotheproposedAIFGDCissuedforcommentonJuly10,1967.Itshouldbenotedthatthereisnocomparable

1967AIFGDCwhichaddresses

theresidualheatremovalissueidentified

inGDC34.Theplantwasnotoriginally

designedtomeettheGeneralDesignCriteria(GDC)ofAppendixAof10CFR50,including

GDC34,sincethesecriteriawereissuedinFebruaryof1971.Specifically,

theAFWCSTsweredesignedtotheAmericanWaterWorksAssociation

Standard(AWWA)D100,1965edition.SinceissuanceoftheGinnaProvisional

Operating

License,theAFWSystemhasbeenscrutinized

aspartoftheTMINUREG-0737

effortandtheGinnaSystematic

Evaluation

Program(SEP).DuringtheSEPreviewofTopicIII-1(Classification

ofStructures,

Components,

andSystems-SeismicandQuality),

theFranklinResearchCenterrecognized

thattheCSTsasoriginally

designedmightnotbecapableofmeetingcurrentcompressive

stressrequirements.

Additional

information

regarding

thecompressive

stresscapabilities

oftheCSTswasrequested

intheNRCSERonthistopic.Theinformation

suppliedbyRG&EwasacceptedbytheNRC.

TheCSTs,duetotheirlocationintheServiceBuilding(non-seismicstructure),

lackofprotective

features,

andtheiroriginaldesignpedigree,

havethepotential

forbeingrenderedinoperable

bytheeffectsofseveralpostulated

hazards(i.e.,safeshutdownearthquake,

tornadoes,

floods,missiles,

highenergylinebreakeffectsontheAFWSystem).Itshouldbenotedthatthesepostulated.

hazardsareremoteeventswithlowprobability

ofoccurrence

duringthelifetimeoftheplant.TheGinnaStationdesignaccommodates

theseremoteoccurrences

byincorporating

aSeismicCategoryIsourceofwater(ServiceWaterSystem)available

tothesuctionoftheAFWpumpsandbyhavingavailable

asecond"Standby"

AFWSystem.(TheSAFWSystempermitsdeliveryofAFWflowtotheSteamGenerators

assumingtheoccurrence

ofahighenergylinebreakintheIntermediate

Building.)

Inaddition,

anothersourceofwateravailable

istheyardfirehydrantsystemwhichcanfunctionindependent

ofallACpower.Asaresult,theCSTsarenotrequiredtoremainfunctional

following

thesepostulated

hazards.Withtheuseofindependent

AFWSystemsandtheavailability

ofindependent

andredundant

sourcesofwater,meansareavailable

atGinnaStationtoremovereactordecayheatfromthesecondary

sideoftheSteamGenerators

ataratesufficient

toachieveandmaintainasafeshutdowncondition

following

anydesignbasisevent.Asstatedin10CFR50,AppendixB,SectionIII,designandqualityassurance

controlsshouldbe"commensurate

withthoseappliedtotheoriginaldesign",including

allregulatory

commitments

madesinceGinnaProvisional

Operating

License.ThesecontrolsassurethattheCSTsandchangesmadetheretomeetquality"standards

atleastasstringent

asthoseoriginally

appliedtotheCSTs.TheQAcontrolsplacedontheCSTsarecommensurate

withthecontrolsnecessary

toassurethattheCSTswillproperlyfunctionforthedesignbasiseventsthatrequire-theiroperability

whilebeingsubjected

totheeffectsofthesesamedesignbasisevents.TheCSTsfunctionforUFSARChapter15events,unmitigated

firds,andstationblackout.

Theadverseeffectsoftheseeventshavealimitedimpactontheoperability

oftheCSTs,duetotheCSTs'ocation

intheServiceBuildingandtheassumptions

madefortheseeventscenarios

(forinstance,

theassumption

ofacoincident

lossofoffsitepower,butnottheassumption

ofacoincident

hazardsuchasasafeshutdownearthquake).

Section2.2oftheR.E.GinnaQAmanualrecognizes

thattheCSTsaresafetyrelated,butnotSeismicCategoryIandidentifies

thecontrolsthatapplytothesetanks.TheGinnaAFWdesignwasfoundtobeacceptable

asoriginally

licensedin1969,asreviewedagainstNUREG-0737,

ItemsII.E.1.1andII.E.1.2,

following

theTMIaccident,

andasreviewedagainstSEPTopicsX,"Auxiliary

Feedwater

System",andV-10.B,"Residual

HeatRemovalSystemReliability".

(NotethattheTMIandSEPreviewsessentially

reviewedtheGinnaAFWSystemsagainstthecriteriaofBTPASB10-1,andBTPRSB5-1.)AsaresultofNUREG-0737andtheSEPeffort,RGGEmadenumerouscommitments

andupgradestotheAFWSystems.Theseupgradeswerereviewedbythe

staffandapprovedinaccordance

withtheissuanceofGinna'sfulltermoperating

licenseinDecember1984.TheQAanddesigncontrolsappliedtotheAFWSystem,including

theCSTs,areconsistent

withthesecommitments

andthedesignbaselineestablished

withtheapprovalofthefulltermlicense.RG&Eisawareofthesafetyimportance

oftheCSTsandbelievesthatthequalityassurance

controlsappliedtotheCSTsmeettheoriginaldesignbasis,aswellastheregulatory

commitments

madesincetheProvisional

Operating

Licensewasissued.Whenconsidered

withintheoverallcontextoftheGinnaStationdesign,theQArequirement

appliedtoCSTsareappropriate.

Duetotheissuancerecentlyof10CFR50.63,andRegulatory

Guide1.155,RG&Eisperforming

anadditional

reviewofthedesigncontrolsplacedontheCSTsinthecontextofthisregulatory

guidanceandwillincludeappropriate

upgrades.

IV.Evaluation

ofCSTModifications

Anotherissuediscussed

intheinspection

reportwasthatatechnical

evaluation

fortheinstallation

ofTygontubingdownstream

ofmanualvalve4318Aandcopperpipinghadnotbeenprovidedattheendoftheinspection

period.RG&Ehasperformed

these50.59safetyevaluations

forbothoftheseconcerns(seealsotheresponsetotheNotice'of

Violation

regarding

theTygontubing,whichcontendsthataproper50.59screening

wasperformed

for.theadditionof,theTygontubingpriortoitsinstallation).

ForboththeTygontubingandtheinstallation

oftheHotWater.Systemthesafetyevaluations

concludethatnounreviewed,

safetyquestions

havebeenintroduced.

Theseevaluations

areprovided'inAttachment

III.Znaddition,

asaresultofyourrequest,a50.59safetyevaluation

hasbeenprovidedfortheinstallation

ofmanualvalve4318A.Thisevaluation

alsoconcludes

thatnounreviewed

safetyquestionexists.andisalsocontained

inAttachment

III.

ATTACHMENT

IIISafetEvaluation

fortheHotWaterSstemConnection

TheHotWatersystemconnections

totheCSTsareshownonP&IDs33013-457

and1234.Suctiontothehotwatercirculation

waterpump(MK102)istakenfromtheCSTsthroughmanualvalves8271,8275(CSTB),8270,8274(CSTA),and8276.Hotwaterisrecirculated

backtotheCSTsthrough8299J,8282(CSTA),and8283(CSTB).Thefollowing

sectionsevaluatetheimpacttoplantsafetyoftheconnection

.oftheHotWatersystemtothemainAFWCSTs.Postulated

HazardsandSafeShutdownCaabilitThefollowing

discussion

appliestothepostulated

Hazardslistedbelow:~Adverseweatherphenomena

include;ng

floods,highwinds,snow,andtornadoes

~SafeShutdownEarthquake

~HighEnergyLineBreaks~Externally

orinternally

generated

missilesTheHotWatersystemislocatedadjacenttotheCSTsintheServiceBuilding.

Asaresult,theadverseeffectsofpostulated

hazardsthatcanpotentially

failtheHotWatersystem(andtherebyintroduce

apotential

interaction

withtheCSTs)alsohavethepotential

tofailtheCSTs,sinceinbothcases:1.NeithertheCSTsnortheHotWatersystemarerequiredtobedesignedtowithstand

theeffectsofthehazardspostulated

fortheR.E.Ginnaplant.2.NeithertheCSTsnortheHotWatersystemareprotected

bydesignfeaturessuchasphysicalbarriersto'reserve

theirintegrity

following

postulated

hazards.TheServiceBuildingisnotaSeismicCategoryIstructure

capableofwithstanding

adverseweathereffectsornaturalphenomena.

Forpostulated

hazardsthatpotentially

failtheCSTs,analternate

andindependent

meansofachieving

andmaintaining

asafeshutdowncondition

(thesafeshutdownfunctionofconcernistheremovalofreactordecayheat)isavailable

viatheServiceWatersystemsupplying

.watertoeitherthemainorstandbyAFWsystems.

Asaresult,nosignificant

degradation

inthecapability

ofachieving

andmaintaining

asafeshutdowncondition

willresultduetothehotwatermodification

interface

withtheCSTs.Thecontingency

actionsandalternate

meansofremovingreactordecayheatfollowing

apostulated

hazardremainvalidforthecurrentCSTconfiguration.

ThefailureoftheHotWatersystemfollowing

aseismiceventwhichcouldleadtothedrainingoftheCSTsontotheServiceBuilding'loorisboundedbythepresentanalysisoffailureofCSTsperEWR1023,May20,1975.Thisfloodingscenarioisthesameasthatpreviously

analyzedsincetheHotWatersystemdoesnotintroduce

anewsourceofwater.Inaddition,

theHotWatersystemdoesnotintroduce

anyhighenergylinebreakofconcern,orthepotential

forinternally

generated

missiles.

FiresThemainAFWsystemtakingsuctionfromtheCSTsisusedtoremovedecayheatfollowing

severalpostulated

'nmitigated

fires.Unmitigated

firescanresultinalossofoffsitepowerwhichwouldsubsequently

resultinalossoftheInstrument

Airsystem(IAS).AreviewofPAID33013-457

showsthatthe"effect"ofa,fireresulting

inalossoftheIASisminimalontheCSTsasconfigured

withHotWatersystemconnection.

IftheHotWatersystemisnotinuse,itcanbeisolatedfromtheCSTsviamanualvalves8275,8274,and8299J.Ifthe.HotWatersystemisinuseduringafire,,HotWaterpumps(MK102and115)wouldstoponloss'fACpower.AlthoughtheHotWatersystemcouldbecomeapotential

drainagepathforCST.inventory,

theelevation

ofthehotwaterusers(laundryandhotshowersareatanelevation

equaltothetopoftheCSTs)andtheflowresistance

oftheHotWatersystempipingessentially

maketheHotWatersystemaclosedsystemtodrainage..

AlthoughtheHotWatersystemintroduces

combustibles

intotheServiceBuildingviathegassupplytoheaterMK106,thesafeshutdowncomponents

locatedintheServiceBuilding(CSTs,pipingtotheAFWpumps)shouldnotbeadversely

affected.

Thisisinaccordance

withtheexistinganalysiswhichdealswithfiresintheServiceBuilding.

Thesearemechanical

components

thatmustmaintaintheirpressureboundaryintegrity

toaccomplish

theirsafeshutdownfunction.

TheAppendixRanalysisforGinnaassumesthatexposurefiresdonotcausemechanical

components

tolosepressureboundaryintegrity.

Asaresult,thismodification

doesnotaffectsafeshutdownforfires.Forfiresrequiring

operation

ofthemainAFWsystem,theCSTswillbeoperable,

enablingtheremovalofreactordecayheattoachieveandmaintainasafeshutdowncondition

duringandfollowing

postulated

fires.MitiationofChater15EventsThefollowing

discussion

assessesthesafetyimpactoftheconnection

oftheHotWatersystemtotheCSTsforthefollowing

postulated

UFSARChapter15events,whicharetheonlyeventsforwhichtheAFWsystemisreliedon"asamitigation

feature:

~MainSteamLineBreaks(MSLB)~MainFeedLineBreaks(MFLB)~LossofNormalFeedwater

~LossofACtotheStationAuxiliaries

~LossofExternalElectrical

Loads~LossofCoolantAccidents

(LOCAs)~SteamGenerator

TubeRupture(SGTR)Toassessthepotential

degradation

inthecapability

ofmitigating

theaboveevents,'heHotWatersystemisexaminedforitspotential

adverseinteraction

withtheCSTs.ThefunctionoftheCSTsistomaintainaninventory

of22,500gallonsofcondensate-

gradewaterfortheremovalofreactordecayheatfor2hoursindependent

ofanyACpowersource(TMIItem.II.E.1.1).

TheCSTsalsofunctionastheinitialAFWinventory

sourcefollowing

theoccurrence

ofanyoftheaboveChapter15events(whichresultinthesubsequent

lossof.mainfeedwater

andautoinitiation

ofAFW).Hence,theadverse"effects"

oftheseChapter15eventsareexaminedforthepotential

tofailtheHotWatersystemandtherebydepletetheCSTinventory

throughanadverseinteraction.

Therearetwo"effects"

thatimpactthecurrentCSTconfiguration.

1.MSLBsandMFLBsintheintermediate

buildingcreateadverseeffects(pipewhip,jetimpingement,

temperature,

pressure,

humidity)

thathavethepotential

tofailthemainAFWsystem.MlthreemainAFWpumps(2motordrivenpumps,1turbinedrivenpump)andasignificant

portionofAFWpipingarelocatedintheintermediate

building.

Theeffectsofsomepostulated

MSLBsandMFLBscanfailthemain'AFWsystem.2.MostoftheChapter15eventsassumethecoincident

lossofoffsitepower.LossofnormalACpowerresultsinalossoftheInstrument

Airsystem(IAS)causingairoperatedvalves(AOVs)tofailonlossofsupplyair.ForthecaseofMSLBsorMFLBsintheintermediate

building,

ifthemainAFWsystemfailsthentheCSTsnolongerfunctionastheAFWwatersource.InthiscasethestandbyAFWsystemisplacedintoservice(10minutesforoperatoractionisavailable)

takingsuctionfromtheServiceWatersystem.Thisequipment

islocatedintheStandbyAuxiliary

Feedwater

PumpBuildingandisacompletely

independent

meansofremovingreactordecayheat.Therefore,

thepotential

effectsofMSLBsand,MFLBsontheHotWatersystemhavebeenboundedbythecurrentChapter15analysis.

Asdescribed

inthesectionon"Fires"above,thelossofnormalACpowerdoesnotcreateanadverseinteraction

betweentheHotWatersystemandtheCSTs.TheHotWatersystemiseffectively

aclosedsystem.CSTinventory

willnotbedepletedasaresultoftheassumedcoincidence

ofalossofoffsitepowerfortheChapter15events.Inconclusion,

theconnection

oftheHotWatersystemtotheCSTsdoesnotresultinadditional

consequential

failuresornewfailuremodesthatcreatethepotential

fornew"worstsinglefailures",

ordifferent

eventscenarios.

HotWaterSstemSafetEvaluation

Conclusion

Thissectionsummarizes

thesafetyevaluation

oftheHotWatersystemconnection

totheCSTs.Thissummarygroupspostulated

FiresunderthecategoryofHazards.Theconnection

oftheHotWatersystemtotheCSTsdoesnot,increasetheprobability

ofoccurrence

ofanaccidentpreviously

evaluated

intheGinnaUpdatedFSAR.Asdiscussed

previously,

thefailureoftheHotWatersystemdoesnotcreateaplanttransient

requiring

aprotective

responsefromasafetysystem.Theconnection

oftheHotWatersystemtotheCSTsdoesnotincreasetheconsequences

ofanaccidentpreviously

evaluated

intheGinnaUpdatedFSAR.Asdiscussed

above,thecapability

toachieveandmaintainasafeshutdowncondition

following

theoccurrence

ofpostulated

hazardsisnotdegraded.

TheHotWatersystemdoesnotadversely

interactwithCSTsfortheChapter15eventscenarios.

Asaresult,CSTinventory

isnotdegraded,

mainAFWperformance

isnotimpacted,

andthecapability

toremovereactordecayheatduringandfollowing

thepostulated

Chapter15eventsisnotdegraded.

Therefore,

theintegrity

ofbarrierspreventing

thereleaseoffissionproductsisnotimpacted.

Theconnection

oftheHotWatersystemtotheCSTsdoesnotincreasetheprobability

ofoccurrence

ofamalfunction

.ofequipment

important

tosafetypreviously

evaluated

intheGinnaUpdatedFSAR.Asdiscussed

above,theeffectsofpostulated

HazardsthatcouldfailtheHotWatersystemwouldlikelyalsofailtheCSTssincetheCSTswerenotor'iginally

designedtowithstand

sucheffects.Assuchtheeffectoffailing-the'HotWatersystemisboundedbytheoriginalanalysiswhichassumesfailureoftheCSTs.TheeffectsofChapter15eventshavenoimpactonthecapability

ofCSTstomaintaintheirinventory

forthoseeventsrequiring

theoperation

ofthemainAFWsystem.Thereistherefore

nochangeinthefailureprobability

oftheCSTsforChapter15events.Theconnection

oftheHotWatersystemtotheCSTsdoesnotincreasetheconsequences

ofamalfunction

oftheCSTsforHazardsorChapter15events.Theconsequences

ofsuchmalfunctions

are.therefore

unchanged.

Theconnection

oftheHotWatersystemtotheCSTsdoesnotcreatethepossibility

ofanaccidentofadifferent

typethananypreviously

evaluated

intheGinnaUpdatedFSAR.ThefailureoftheHotWatersystemanditspotential

forinteraction

withtheCSTsdoesnotcreatenewplanttransients

requiring

mitigation.

Theconnection

oftheHotWatersystemtotheCSTsdoesnotcreatethepossibility

ofamalfunction

ofequipment

important

tosafetyofadifferent

typethananypreviously

evaluated

intheUpdatedGinnaFSAR.ThefailureoftheHotWatersystemisessentially

thesameasafailureoftheCSTs.Theinstallation

oftheHotWatersystemdoesnotintroduce

anewordifferent

failuremode.

Theconnection

oftheHotWatersystemtotheCSTsdoesnotreducethemarginofsafety.TheAFWsystemcanstillfunctiontomitigateChapter15events,aswellastoremovedecayheatfor2hourswithoutanACpowersource.Inaddition,

safeshutdowncapability

isnotaffected,

andtheintegrity

offissionproductbarriersisnotcompromised.

Basedontheaboveconclusions,

the,connection

oftheHotWatersystemtothemainAFWCSTsdoesnotintroduce

anunreviewed

safetyquestionasdefinedby10CFR50.59.SafetEvaluation

fortheAdditionofonTubinTygontubingwasinstalled

downstream

ofclosedmanualvalve4318AtoprovideameansoflocalCSTlevelindication

independent

ofanyACpowersource.LocalCSTlevelindication

viatheTygontubingwouldbeusedtoallowlocaloperators

todetermine

whentoalignandplaceintooperation

theServiceWatersystemfollowing:

1.ControlComplexFires(SC-3.30.1)

2.CableTunnelFires(SC-3.30.2)

3.Auxiliary

BuildingBasement/Mezzanine

Fires(SC-3.30.3)

The22,500galloninventory

intheCSTsprovidesfor2hoursofreactordecayheatremoval.Thisisconsidered

sufficient

timetoalignandplaceintooperation

theServiceWatersystemintheremoteeventthatanACpowersourcecannotberestoredfor2hoursfollowing

thepostulated

unmitigated

firesidentified

.above.'ence,theTygontubingisnotessential

forsafe.shutdownfollowing

fires..However,itcanprovideoperators

withCSTlevelinformation

toprovideamoreaccuratemeansofdetermining

whenServiceWatershouldbealigned.Itshouldbenoted,thattheR.E.GinnaAppendixRAlternative

ShutdownReportdoesnotidentifyCSTlevelindication

asaplantprocessparameter

thatmulctbemonitored.

forsupporting

safeshutdown.

Theinstallation

ofTygontubingdownstream

ofmanual.valve4318Adoesnotincreasetheprobability

ofoccurrence

ortheconsequences

ofanaccidentormalfunction

ofequipment

important

tosafetypreviously

evaluated

in.theGinnaUpdatedFSAR.TheTygontubingisisolatedfromallplantprocesssystemsviaclosedmanualvalve4318A.Thepressureboundaryprovided,

byclosedmanualvalve4318Aprecludes

thepotential

foradverseprocessinteractions.

TheTygontubingisaflexiblematerialoflowmassthatisnotcapableofphysically

impacting

thesystems,structures,

orcomponents

intheimmediate

vicinity.

Theinstallation

ofTygontubingdownstream

ofmanualvalve4318Adoesnotcreatethepossibility

ofanaccidentormalfunction

ofadifferent

typethananypreviously

analyzedintheGinnaUpdatedFSAR.Asstatedabove,theTygontubingisisolated.

fromallplantsystemsandtherefore

doesnotcreatethepotential

forprocessinteractions

thatcanleadtodifferent

accidents

ormalfunctions.

Theinstallation'of

Tygontubingdownstream

ofmanualvalve4318Adoesnotreducethemarginofsafetyasdefined,inthebasisofanyTechnical

Specification.

TheTygontubingwillprovidealocalindication

ofCSTlevelforfiresthatresultinalossofallAC.Thisindication

providesabettermeansofdetermining

whentoalignServiceWaterintheunlikelyeventofanunmitigated

fire,prolonged

lossofallAC,anddepletion

oftheCSTs.AlthoughsafeshutdowncanbeachievedwithoutthislocalCSTlevelindication,

theTygontubingisbeneficial

forfirerecoveryefforts.SafetEvaluation

fortheAdditionofManualValve4318AThefollowing

constitutes

a10CFR50.59safetyevaluation

fortheadditionofmanualvalve4318AtoasamplinglineontheAuxiliary

Feedwater

(AFW)pumpsuctionheaderfromtheCondensate

StorageTanks.Thisevaluation

isbeingprovidedperanNRCrequest.Thefunctionofmanualvalve4318AistoprovideapressureboundaryfortheAFWCSTsandensurethatCSTdrainagedoesnotoccurviathe3/4inchdiametersamplingline.Thisevaluation

assumestheadditionofthemanualvalvetotheexistingsamplingline.Manualvalve4318AisnormallyclosedandisonlyopenedtoenablelocalCSTlevelindication

viatheTygontubing.Sincethe4318Aisnormallyclosed,itisnotsubjecttoeitherashorttermactivefailureoralongtermpassivefailure.Specifically,'he

valvedoesnothavetochangepositionthrougha'echanical

movementto-accomplish

afunctionnecessary

tomitigateanypostulated

designbasiseventsfortheGinnafacility.

(Itisnot.essential

tohavelocalCSTlevelindication

viatheCSTTygontubingtorecoverfrompostulated

unmitigated

fires.However,thisfeaturedoesenhanceplantsafetyshouldsuchafireoccur.)Itisnotnecessary

topostulate

aspuriousopeningof4318Asinceitismanuallyoperated.

Evenif4318Awasinadvertently

openedduetoanoperatorerror,theassumption

thatCSTdrainagegoesundetected

andthatadesignbasiseventsubsequently

occursisnotcredible.

If4318Aweretobecomeadrainagepathway,CSTlevelindication

woulddetectthelossofinventory.

Therefore,

operatoractioncanrestoretherequiredquantityofwaterorprovideasupplyfromtheServiceWaterSystem.Further,drainageoftheCSTwouldnothaveadetrimental

effectonrequiredequipment,

asisdescribed

intheevaluation

oftheHotWaterSystemConnection.

Theadditionofmanualvalve4318Adoesnotincreasetheprobability

ofoccurrence

ortheconsequences

ofanaccidentormalfunction

ofequipment

important

tosafetypreviously

evaluated

intheGinnaUpdatedFSAR.Manualvalve4318AisanormallyclosedvalvethatprovidesapressureboundaryfortheAFWsysteminventory

source(CSTs),consistent

withcommercial

gradeengineering

practice.

Thereisnosingleactiveorpassivefailurewhichresultsin4318Aopening.Asaresult,theinstallation

of4318Adoesnotimpactanydesignbasisevent.

Theadditionofmanualvalve4318Adoesnotcreatethepossibility

foranaccidentor'alfunction

ofadifferent

typethananypreviously

evaluated

intheGinnaUpdatedFSAR.Manualvalve4318Aisnormallyclosedandnoworstsinglefailurethatisrequiredtobepostulated

fortheGinnastationcancausethepressureboundaryprovidedby4318Atobedegraded.

Asaresult,theAFWinventory

source(CSTs)arenotimpacted.

Theadditionofmanualvalve4'318AdoesnotreducethemarginofsafetyasdefinedinthebasisofanyGinnaTechnical

Specification.

Thefunctionof4318AistomaintainapressureboundaryfortheCSTs.Thevalvedoesnotperformanessential

functiontomitigateanypostulated

designbasiseventforGinna.Manualvalve4318Ainconjunction

withtheTygontubingenhanceslocalindication

capability

inresponsetopostulated

unmitigated

fires'~>>>>.>>>>>>>>~>>P>>I->>