Text

Proposed Tech Specs,Removing Containment Isolation Valve Table 3.6-1 from TS
	ML17263A319
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Site:	Ginna
Issue date:	07/15/1993
From:	; ROCHESTER GAS & ELECTRIC CORP.
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ML17263A317	List: ML17263A316; ML17263A318; ML17263A319;
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	NUDOCS 9307220182
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ATTACHMENT AProposedTechnical Specification Changes(9307220182, 930715PDRADOCK05000244',PPDR I0 ATTACHMENT ARevisetheTechnical Specification pagesasfollows:Remove3.6-13.6-23.6-33.6-43.6-53.6-63.6-73.6-7A3.6-8.3.6-93.6-103.6-113.8-13.8-33.8-54~444.4-64.4-74.4-84.4-114.4-134.4-144.4-17Insert3.6-13.6-23.6-33.6-43.8-13.8-33.8-53.8-64'44.4-64.4-74.4-84.4-114.4-134.4-144.4-17 0Q'cFr$k,s4I Containment SstemAlicabilit Appliestotheintegrity ofreactorcontainment.

Todefinetheoperating statusofthereactorcontainment forplantoperation.

Secification:

3.6.1Containment Interita~Exceptasallowedby3.6.3,containment integrity

-shallnotbeviolatedunlessthereactorisinthecoldshutdowncondition.

Closedvalvesmaybeopenedonanintermittent basisunderadministrative control.b.Thecontainment integrity shallnotbeviolatedwhenthereactorvesselheadisremovedunlesstheboronconcentration isgreaterthan2000ppm.oc~Positivereactivity changes,shallnotbemadebyroddrivemotionorborondilutionwheneverthecontainment integrity isnotintact,unlesstheboronconcentration isgreaterthan2000ppm.3.6.2InternalPressureIftheinternalpressureexceeds1psigortheinternalvacuumexceeds2.0psig,thecondition shallbecorrected within24hoursorthereactorrenderedsubcritical.

Amendment No.CS3.6-1Proposed 1Iipy~@+4gt'hiN'Vy,+~~l'AilltlaIyl,IIIA~l'I 3.6.303.6.3.1Containment Isolation Boundaries Withacontainment isolation boundaryinoperable foroneormorecontainment penetrations',

either:a.Restoreeachinoperable boundarytoOPERABLEstatuswithin4hours,orb.Isolateeachaffectedpenetration within4hoursbyuseofatleastonedeactivated automatic valvesecuredintheisolation

position, oneclosedmanualvalve,orablindflange,orc.Beinatleasthotshutdownwithinthenext6hoursandincoldshutdownwithinthefollowing 30hours.3.6.4Combustible GasControl3.6.4.1Whenthereactoriscritical, atleasttwoindependent
-containment hydrogenmonitorsshallbeoperable.
OneofthemonitorsmaybethePostAccidentSamplingSystem.3.6.4.2Withonlyonehydrogenmonitoroperable, restoreasecondmonitortooperablestatuswithin30daysorbeinat~~~~leasthotshutdownwithinthenext6hours.3.6.4.3Withnohydrogenmonitorsoperable, restoreatleastonemonitortooperablestatuswithin72hoursorbeinatleasthotshutdownwithinthenext6hours.3.6.5Containment Mini-PureWheneverthecontainment integrity isrequired, emphasiswillbeplacedonlimitingallpurgingandventingtimestoaslowasachievable.
Themini-purge isolation valveswillremainclosedtothemaximumextentpracticable butmaybeopenforpressurecontrol,forALARA,forrespirable airqualityconsiderations forpersonnel entry,forsurveillance teststhatmayrequirethevalvetobeopenorothersafetyrelatedreasons.Amendment No.9,183.6-2Proposed 1ttaII\If4II'01tft,t Basis:Thereactorcoolantsystemconditions ofcoldshutdownassurethatnosteamwillbeformedandhencetherewouldbenopressurebuildupinthecontainment ifthereactorcoolantsystemruptures.
Theshutdownmarginsareselectedbasedonthetypeofactivities thatarebeingcarriedout.The(2000ppm)boronconcentration providesshutdownmarginwhichprecludes criticality underanycircumstances.
Whenthereactorheadisnottoberemoved,acoldshutdownmarginof1%~k/kprecludes criticality inanyoccurrence.
Regarding internalpressurelimitations, thecontainment designpressureof60psigwouldnotbeexceedediftheinternalpressurebeforeamajorsteambreakaccidentwereasmuchas1psig.<'>Thecontainment isdesignedtowithstand aninternalvacuumof2.5psig.~The2.0psigvacuumisspecified asanoperating limittoavoidanydifficulties withmotorcooling.Inordertominimizecontainment leakageduringadesignbasisaccidentinvolving asignificant fissionproductrelease,penetrations notrequiredforaccidentmitigation areprovidedwithisolation boundaries.
Theseisolation boundaries consistofeitherpassivedevicesoractiveautomatic valvesandarelistedinaprocedure underthecontrolofTechnical Specification 6.8.Closedmanualvalves,deactivated automatic valvessecuredintheirclosedposition(including checkvalveswithflowthroughthevalvesecured),
blindflangesandclosedsystemsareconsidered passivedevices.Automatic isolation valvesdesignedtoclosefollowing anaccidentwithoutoperatoraction,areconsidered activedevices.Twoisolation devicesareprovidedforeachmechanical penetration, suchthatnosinglecrediblefailureormalfunction ofanactivecomponent cancausealossofisolation, orresultinaleakageratethatexceedslimitsassumedinthesafetyanalyses~'>.
Intheeventthatoneisolation boundaryisinoperable, theaffectedpenetration mustbeisolatedwithatleastoneboundarythatisnotaffected byasingleactivefailure.Isolation boundaries thatmeetthiscriterion areaclosedanddeactivated automatic containment isolation valve,aclosedmanualvalve,orablindflange.Theopeningofclosedcontainment isolation valvesonanintermittent basisunderadministrative controlincludesthefollowing considerations:
(1)stationing anindividual qualified inaccordance withstationprocedures, whoisinconstantcommunication withthecontrolroom,atthevalvecontrols, (2)instructing thisindividual toclosethesevalvesinanaccident, situation, and(3)assuringthatenvironmental conditions willnotprecludeaccesstoisolatetheboundaryandthatthisactionwillpreventthereleaseofradioactivity outsidethecontainment.
Amendment No.CS3.6-3Proposed lP<A7
References:
(1)Westinghouse
Analysis, "ReportII(2)UFSAR-Section3.8.1.2.2 (3)UFSAR-Section6.2.4fortheBASTConcentration Reduction forR.E.Gonna,August1985,submitted viaApplication forAmendment totheOperating LicenseinaletterfromR.W.Kober,RGGEtoH.A.Denton,NRC,datedOctober16,-19853.6-4Proposed
'~IfiJTIlk' REFUELING Alicabilit Appliestooperating limitations duringrefueling operations.
ObectiveToensurethatnoincidentcouldoccurduringrefueling operations thatwouldaffectpublichealthandsafetySecification Duringrefueling operations thefollowing conditions shallbesatisfied.
Qoa~b.c~Containment penetrations shallbeinthefollowing status:i.Theequipment hatchshallbeinplacewithatleastoneaccessdoorclosed,ortheclosureplatethatrestricts airflowfromcontainment shallbeinplace,ii.Atleastoneaccess,doorinthepersonnel airlockshallbeclosed,andiii.Eachpenetration providing directaccessfromthecontainment atmosphere totheoutsideatmosphere shallbeeither:1.Closedbyanisolation valve,blindflange,ormanualvalve,or2.BecapableofbeingclosedbyanOPERABLEautomatic shutdownpurgeormini-purge valve.Radiation levels.inthecontainment shallbemonitored continuously.
Coresubcritical neutronfluxshallbecontinuously monitored byatleasttwosourcerangeneutronmonitors, eachwithcontinuous visualindication inthecontrolroomandonewithaudibleindication inthecontainment andcontrolroomavailable whenevercoregeometryisbeingchanged.WhencoregeometryisnotbeingchangedatAmendment No.2,Ã8Proposed
'1'Il'JV~lI flange.Ifthiscondition isnotmet,all3.8.23.8.3operations involving movementoffuelorcontrolrodsinthereactorvesselshallbe-suspended.
Ifanyofthespecified limitingconditions forrefueling isnotmet,refueling ofthereactorshallcease;workshallbeinitiated tocorrecttheviolatedconditions sothatthespecified limitsaremet;nooperations whichmayincreasethereactivity ofthecoreshallbemade.Iftheconditions of3.8.1.darenotmet,theninadditiontotherequirements of3.8.2,isolatetheshutdownpurgeandmini-purge penetrations within4hours.Basis:Theequipment andgeneralprocedures tobeutilizedduringrefueling arediscussed intheUFSAR.Detailedinstructions, theabovespecified precautions, andthedesignofthefuelhandlingequipment incorporating built-ininterlocks andsafetyfeatures,:
provideassurance thatnoincidentcould.occurduringtherefueling operations thatwouldresultinahazard3.8-3Proposed I,~l'(I'$g>i~"~I>>lI~0t~1fill1IN providedontheliftinghoisttopreventmovementofmorethanonefuelassemblyat'time.Thespentfueltransfermechanism canaccommodate onlyonefuelassemblyatatime.,In,addition, interlocks ontheauxiliary buildingcranewillpreventthe.trolley"frombeingmovedoverstoredrackscontaining spentfuel.Theoperability requirements forresidualheatremovalloopswillensureadequateheatremovalwhileintherefueling mode.Therequirement for23feetofwaterabovethereactorvesselflangewhilehandlingfuelandfuelcomponents incontainment isconsistent withtheassumptions ofthefuelhandlingaccidentanalysis.
Theanalysis<'~
forafuelhandlingaccidentinsidecontainment establishes acceptable offsitelimitingdosesfollowing ruptureofallrodsofanassemblyoperatedatpeakpower.Nocreditistakenforcontainment isolation oreffluentfiltration priortorelease.Requiring closureofpenetrations whichprovidedirectaccessfromcontainment atmosphere totheoutsideatmosphere establishes additional marginforthe,fuelhandlingaccidentandestablishes aseismicenvelopetoprotectagainstthepotential consequences ofseismiceventsduringrefueling.
Isolation ofthesepenetrations maybeachievedbyanOPERABLEshutdownpurgeormini-purge valve,blindflange,orisolation valve.AnOPERABLEshutdownpurgeormini-purge valveiscapableofbeingautomatically isolatedbyRllorR12.Penetrations whichdonotprovidedirectaccessfromcontainment atmosphere totheoutsideatmosphere supportcontainment integrity byeitheraclosedsystem,necessary isolation valves,oramaterialwhichcanprovideatemporary ventilation barrier,atatmospheric
pressure, forthecontainment penetrations duringfuelmovement.
Amendment No.3.8-5Proposed I~)Jir',~(~.P, References(1)UFSARSections9.1.4.4and9.1.4.5(2)ReloadTransient SafetyReport,Cycle14(3)UFSARSection15.7.3.33.8-6Proposed I~~x'i AccetanceCriteriaa0b.TheleakagerateLtmshallbe<0.75LtatPt.Ptisdefinedasthecontainment vesselreducedtestpressurewhichisgreaterthanorequalto35psig.Ltmisdefinedasthetotalmeasuredcontainment leakagerateatpressurePt.Ltisdefinedasthemaximumallowable leakagerateatpressurePt.IPCi~I~Ltshallbedetermined asLt=LalzaJwhichequals.1528percentweightperdayat35psig.Paisdefinedasthecalculated peakcontainment internalpressurerelatedtodesignbasisaccidents whichisgreaterthanorequalto60psig.Laisdefinedasthemaximumallowable leakagerateatPawhichequals.2percentweightperday.c~TheleakagerateatPa(Lam)shallbe<0.75La.Lamisdefinedasthetotalmeasuredcontainment leakagerateatpressurePa.TestFreuenca~Asetofthreeintegrated leakratetestsshallbeperformed atapproximately equalintervals duringeach10-yearserviceperiod.Thethirdtestof.eachsetshallbeconducted inthefinalyearofthe10-yearserviceperiodoroneyearbeforeorafterthefinalyearofthe10-yearserviceperiodprovided:
1~iiitheintervalbetweenanytwoTypeAtestsdoesnotexceedfouryears,following eachin-service inspection, thecontainment
airlocks, thesteamgenerator inspection/maintenance penetration, andtheequipment hatchareleaktestedpriortoreturning theplanttooperation, andanyrepair,replacement, ormodification ofacontainment barrierresulting fromtheinservice inspections shallbefollowedbytheappropriate leakagetest.4~44Proposed
'lI-i>.y$P"4p)4n.>'C5'3 4b.Thelocalleakagerateshallbemeasuredforeachofthe-following components:
1~~~lieContainment penetrations thatemployresilient seals,gaskets,orsealantcompounds, pipingpenetrations withexpansion bellowsandelectrical penetrations withflexiblemetalsealassemblies.
Airlockandequipment doorseals.illsFueltransfertube.ivVeIsolation valvesonthetestablefluidsystemslinespenetrating thecontainment.
Othercontainment components.,
whichrequireleakrepairinordertomeettheacceptance criterion foranyintegrated leakageratetest.4.4.2.2AccetanceCriterion Containment isolation boundaries areinoperable fromaleakagestandpoint whenthedemonstrated leakageofasingleboundaryorcumulative totalleakageofallboundaries isgreaterthan0.60La.4.4.2e3Corrective Action'a~Ifatanytimeitisdetermined thatthetotalleakagefromallpenetrations andisolation boundaries exceeds0.60La,repairsshallbeinitiated immediately.
4.4-6Proposed I+4k,1eF&i b.Ifrepairsarenotcompleted andconformance totheacceptance criterion of4.4.2.2isnotdemonstrated within48hours,thereactorshallbe.shutdown-.and depressurized,until repairsareeffectedandthelocalleakagemeetstheacceptance criterion.
c.Ifit,isdetermined thattheleakagethroughamini-purge supplyandexhaustlineisgreaterthan0.05Laanengineering evaluation shallbeperformed andplansforcorrective actiondeveloped.
4.4.2.4Test,Freuenca.Exceptasspecified inb.andc.below,individual penetrations andcontainment isolation valves.shallbetestedduringeachreactorshutdownforrefueling, orotherconvenient intervals, butinnocaseatintervals greaterthantwoyears.b..Thecontainment equipment hatch,fueltransfertube,steamgenerator inspection/maintenance penetration, andshutdownpurgesystemflangesshallbetestedateachrefueling shutdownoraftereachuse,ifthatbesooner.Amendment No.184.4-7Proposed 0~S4C,4I c~Thecontainment airlocksshallbetestedatintervals ofnomorethansixmonthsbypressurizing thespacebetweentheairlockdoors.Inaddition, following openingoftheairlockdoorduringtheinterval, atestshallbeperformed bypressurizing betweenthedualsealsofeachdooropened,within48hoursoftheopening,unlessthereactorwasinthecoldshutdowncondition atthetimeoftheopeningorhasbeensubsequently broughttothecoldshutdowncondition.
Atestshallalsobeperformed bypressurizing betweenthedualsealsofeachdoorwithin48hoursofleavingthecoldshutdowncondition, unlessthedoorshavenotbeenopensincethelasttestperformed eitherbypressurizing thespacebetweentheairlockdoorsorbypressurizing betweenthedualdoorseals.Amendment No.l'84.4-8Proposed
'Il'I<110JlS~e)l'q,e,riQ!M 4.4.4.2thetendoncontaining 6brokenwires)shallbeinspected.
Theacceptedcriterion thenshallbenomorethan4brokenwiresinanyoftheadditional 4tendons.Ifthiscriterion isnotsatisfied, all-ofthetendonsshallbeinspected andifmorethan5%ofthetotalwiresarebroken,-the.
reactorshallbeshut:down~and:depressurized.
Pre-Stress Confirmation Testa0Lift-offtestsshallbeperformed onthe14tendonsidentified in4.4.4.1aabove,attheintervals specified in4.4.4.1b.
Iftheaveragestressinthe14tendonscheckedislessthan144,000psi(60%ofultimatestress),alltendonsshallbecheckedforstressandretensioned, ifnecessary, toastressof144,000psi.b.Beforereseating atendon,additional stress(6%)shallbeimposedtoverifytheabilityofthetendontosustaintheaddedstressappliedduringaccidentconditions.
4.4.54.4.5.1Containment Isolation ValvesEachcontainment isolation valveshallbedemonstrated tobeOPERABLEinaccordance withtheGinnaStationPumpandValveTestprogramsubmitted inaccordance with10CFR50.55a.4.4.64.4.6.14.4.6.2Containment Isolation ResonseEachcontainment isolation instrumentation channelshallbedemonstrated OPERABLEbytheperformance oftheCHANNELCHECK,CHANNELCALIBRATION, andCHANNELFUNCTIONAL TESToperations fortheMODESandatthefrequencies showninTable4.1-1.Theresponsetimeofeachcontainment isolation valveshallbedemonstrated tobewithinitslimitatleastonceper18months.Theresponsetimeincludesonlythevalvetraveltimeforthosevalveswhichthesafetyanalysisassumptions takecreditforachangeinvalvepositioninresponsetoacontainment isolation.
signal.Amendment No.9,LL4.4-11Proposed
~~<<<<
TheSpecification alsoallowsforpossibledeterioration oftheleakageratebetween-tests,by-requiring'-that thetotal=-measured leakageratebeonly75%ofthemaximumallowable leakagerate.Thedurationandmethodsfortheintegrated, leakageratetestestablished byANSIN45.4-1972 provideaminimumlevelofaccuracyandallowfordailycyclicvariation intemp'erature andthermalradiation.
Thefrequency oftheintegrated leakageratetestiskeyedtotherefueling scheduleforthereactor,becausethesetestscanbestbeperformed duringrefueling shutdowns.
Refueling sshutdowns arescheduled atapproximately oneyearintervals.
Thespecified frequency ofintegrated leakageratetestsisbasedonthreemajorconsiderations.
Firstis-thelowprobability ofleaksintheliner,becauseof(a)theuseofweldchannelstotesttheleaktightness oftheweldsduringerection, (b)conformance ofthecompletecontainment toa0.1%perdayleakrateat60psigduringpreoperational testing,and(c)absenceofanysignificant stressesinthelinerduringreactoroperation.
Secondisthemorefrequenttesting,atthefullaccidentpressure, ofthoseportionsofthecontainment envelopethataremostlikelytodevelopleaksduringreactoroperation (penetrations andisolation valves)andthelowvalue(0.60La)ofthetotalleakagethatisspecified asacceptable.
Thirdisthetendonstresssurveillance program,whichprovidesassurance thananimportant partofthestructural integrity ofthecontainment ismaintained.
4.4-13Proposed II1~ka.~1.,~'i~0'II"Ig4n'f4t' Thebasisforspecification ofatotalleakageof0.60Lafrom'pen'etrations andisolation boundaries isthatonlya'portion,of, the'allowable integrated leakagerateshouldbefrom.those.sources,in ordertoprovideassurance thattheintegrated leakageratewouldremainwithinthespecified limitsduringtheintervals betweenintegrated leakageratetests.Becausemostleakageduringanintegrated leakratetestoccursthoughpenetrations andisolation valves,andbecauseformostpenetrations andisolation valvesasmallerleakageratewouldresultfromanintegrated leaktestthanfromalocaltest,adequateassurance ofmaintaining theintegrated leakageratewithinthespecified limitsisprovided.
ThelimitingleakageratesfromtheRecirculation HeatRemovalSystemsarejudgement valuesbasedprimarily onassuringthatthecomponents couldoperatewithoutmechanical failureforaperiodontheorderof200daysafteradesignbasisaccident.
Thetest4.4-14Proposed II'IJ~ici<w~QiI Thepre-stress confirmation testprovidesadirectmeasureoftheload-carrying capability ofthetendon.Ifthesurveillance programindicates byextensive wirebreakageortendonstressrelationthatthepre-stressing tendonsarenotbehavingasexpected, thesituation willbeevaluated immediately.
Thespecified acceptance criteriaaresuchastoalertattention tothesituation wellbeforethetendonload-carrying capability woulddeteriorate toapointthatfailureduringadesignbasisaccidentmightbepossible.
Thusthecauseoftheincipient deterioration couldbeevaluated andcorrective actionstudiedwithoutneedtoshutdownthereactor.Thecontainment isprovidedwithtworeadilyremovable tendonsthatmightbeusefultosuchastudy.Inaddition, thereare40tendons,eachcontaining aremovable wirewhichwillbeusedtomonitorforpossiblecorrosion effects.Operability ofthecontainment isolation boundaries ensuresthatthecontainment atmosphere willbeisolatedfromtheoutsideenvironment intheeventofareleaseofradioactive materialtothecontainment atmosphere orpressurization ofthecontainment.
Performance ofcyclingtestsandverification ofisolation timesassociated withautomatic containment isolation valvesiscoveredbythePumpandValveTestProgram.Compliance withAppendixJto10CFR50isaddressed underlocalleaktestingrequirements.
o
References:
(1)UFSARSection3.1.2.2.7 (2)UFSARSection6.2.6.1(3)UFSARSection15.6.4.3(4)UFSARSection6.3.3.8(5)UFSARTable15.6-9(6)FSARPage5.1.2-28(7)North-American-Rockwell Report550-x-32, Reliability
Handbook, February1963.(8)FSARPage5.1-28Autonetics 4.4-17Proposed I4>
ATTACHMENT BSafetyEvaluation IvjC,'4'I Attachment BPago1of4Theprimarypurposeofthisamendment istoremoveTable3.6-1,"Containment Isolation Valves",fromtheR.E.GinnaTechnical Specifications.
Thereference toTable3.6-1inTechnical Specification sections3.6.3.1,4.4.5.1,and4.4.6.2willbedeleted.ThebasesforTechnical Specification 3.6willincludeastatement thatthelistingofcontainment isolation valvesandboundaries willbemaintained inaprocedure underthecontrolsofTechnical Specification 6.8.Inaddition, theinoperability definition andactionrequiredstatement forTechnical Specifications 3.6.1and3.6.3.1willbeclarified.
TheSpecifications andBasesforcontainment integrity duringrefueling operations (3.8.1sectionaand3.8.3)willberevisedtomakethemmoreconsistent, withindustrystandards.
Technical Specifications 4.4.1.5,sectiona(ii)and4.4.2.4,sectionb,willberevisedtoincludethemodifiedsteamgenerator inspection/maintenance penetration.
Technical Specification 4.4.1.5,sectiona(ii)andtheBasesforsection4.4willalsobeclarified.
Thetemporary notesassociated withtheshutdownpurgesystemandmini-purge valves(Technical Specifications 3.6.5and4.4.2.4sectionaandd)willberemovedsincethenecessary flangesandvalveshavebeeninstalled.
Also,theacceptance criteriaforcontainment leakagecriteriaaslistedinTechnical Specification 4.4.1.4and4.4.2.2willbeclarified.
The1988Inservice Test(IST)Programprovidedacompletereviewofthecontainment isolation valvesforGinnaandtheirtestingrequirements.
Theinformation obtainedduringthisreviewwassubmitted totheNRCtodefinetheISTrequirements forthethirdten-yearintervalatGinna.Thissubmittal wassubsequently approvedbytheNRC.Asaresultofthissubmittal andapproval, numerousclarifications wererequiredofTechnical Specification Table3.6-1andvariousplantdocuments.
However,thisamendment willremoveTechnical Specification Table3.6-1.GenericLetter91-08providesguidanceonremovingcomponent listsfromtechnical specifications, including thetableofcontainment isolation valves,sincetheirremovalwouldnotaltertherequirements thatareappliedtothesecomponents.
RemovingTable3.6-1fromtheTechnical Specifications andincorporating therequiredinformation intostationprocedures willmaintainthelistingofthecontainment isolation boundaries withinalicenseecontrolled document.
Thislistingiscurrently maintained inProcedure A-3.3whichissubjecttothechangecontrolprovisions ofTechnical Specification 6.8asrequiredbyGenericLetter91-08.AcopyofProcedure A-3.3isprovidedinAttachment D.
1V+t44V0w>g.h4~IIgl),ag Attachment BPage2of4GenericLetter91-08alsoprovidedinstructions toaddanotetothecontainment isolation valveLCOwithrespecttoopeninglockedorsealedclosed.containment
.isolation
.valvesunder-administrative control.Anoterelatedto"closedvalves"onlywasaddedtoTechnical Specification 3.6.1sincemanytestconnections thatare'required tobeopendur'ingpoweroperation fortestingpurposesarenotlockedclosedatGinnaStation.Thesevalvesaremaintained closedbysystemlineupprocedures and"containment isolation boundary" controltagsandverifiedclosedbyoperatorwalkdowns.
Thisprovidesequivalent protection tolockingdevicessinceallplantpersonnel aretrainedwithrespecttotheuseofequipment controltags.Adiscussion ofthenecessary administrative controlsrequiredforopeningthesevalveswasalsoaddedtothebasesforTechnical Specification 3.6consistent withGL91-08.Theremaining changeswithrespecttotherequiredactionsofTechnical Specification 3.6.3.1allowconsistency withStandardTechnical Specifications.
However,"isolation boundary" wasusedinplaceof"isolation valve"sincenotallpenetrations havetwocontainment isolation valves.Forexample,penetrations underthespecifications forGeneralDesignCriteria57onlyrequireasingleisolation valve;thepipingprovidesanadditional boundary.
Theuseof"isolation boundary" isalsoconsistent withthecolumnheadingsofthecurrentContainment Isolation ValveTable3.6-1.Information onwhatqualifies asan"isolation boundary" isprovidedinthebasesforTechnical Specification 3.6.Thesecriteriaareconsistent withthenecessary GeneralDesignCriteria, orexemption, asappropriate.
"Isolation boundary" wasalsousedinplaceof"isolation valve"inTechnical Specifications 4.4.2.2,4.4.2.3,andtheBasesforsection4.4.Theinoperability definition basedonleakageforcontainment isolation boundaries wasalsoremovedfromTechnical Specification 3.6.3.1.Thisdefinition isfoundinTechnical Specification 4.4.2.3whichwassubsequently updatedtomakeitmoreconsistent with10CFR50AppendixJ.Thischangeeliminates duplication withintheTechnical Specifications andisconsistent, withStandardTechnical Specifications.
Theactionstatement associated withTechnical Specification 3.8.1sectionawasmodifiedtomakeitmorenearlyconsistent withStandardTechnical Specifications.
Themostsignificant changewaswithrespecttoremovingtherequirement ofhavingallautomatic containment isolation valvesoperableduringrefueling operations.
Theproposedspecification nowonlyrequiresthatallpenetrations providing directaccessfromthecontainment atmosphere totheoutsideatmosphere beeitherisolatedorcapableofbeingisolatedbyanautomatic purgevalve.Thischangeisconsidered acceptable sinceafuelhandlingaccidentwillnot,significantly pressurize thecontainment.
Inaddition, thefuelhandlingaccidentanalyzedforGinnadoesnottakecreditforisolation ofcontainment whileremaining wellwithin10CFR100guidelines (UFSARSection15.7.3.3.1.1).
Therefore, theremovalofthisrequirement doesnotaffecttheconsequences ofafuelhandlingaccident.
ltl~4ijsau<r',ggQ4~Ci4All4*<<~<ac"~~Qt.w'J.1TtjV<"'lU Attachment BPage3of4ThechangestoTechnical Specification 3.8.3nowspecifically identifywhichpenetrations mustbeclosedifthereisnoresidualheatremovalloop-'inservice(i.e.,'shutdown"purge.-and mini-purge).
Theremaining penetrations thatprovidedirectaccessfromthecontainment atmosphere totheoutsideatmosphere arealreadyrequiredtobeisolatedduringrefueling operations pernewTechnical Specification 3.8.1sectiona(iii).Thechangestothebasesareconsistent withStandardTechnical Specifications.
Consequently, thesearenottechnical changes.Thechangeswithrespecttocontainment leakagecriteriainTechnical Specification 4.4.1.4areclarifications only.Alltermscontained inthedefinition forLtisspecified intheTechnical Specifications consistent with10CFR50AppendixJ.Theadditionofthesteamgenerator inspection/maintenance penetration toboththeUFSARTableandthenecessary Technical Specification surveillance requirements istheresultofamodification toenhancecontainment closureduringmid-loopoperation
-(Generic.
Letter88-17).Nonewcontainment isolation valveswereaddedasaresultofthismodification.
Theadditionofthispenetration totheUFSARTableandTechnical Specifications 4.4.1.5,sectiona(ii)and4.4.2.4,sectionb,resultsinthenewpenetration tobetreatedconsistent withrespecttothePersonnel andEquipment Hatches,andthefueltransfertube(seeletterfromR.C.Mecredy,RGRE,toA.R.Johnson,NRC,datedMarch13,1990).ThefirstlineofTechnical Specification 4.4.1.5,sectiona(ii)isalsomodifiedtostate"following eachin-service inspection..."
Thehyphenation of"in-service" is'tocorrectatypographical erroronly.Thereplacement of"one"with"each"providesgreaterunderstanding ofthetestfrequency requirements.
Thesechangesareaminorclarification onlyanddonotinvolveatechnical change.Thetemporary notesassociated withthepurgeandmini-purge valvesinTechnical Specifications 3.6.5,4.4.2.4sectionaanddareremovedsincetheshutdownpurgeflangesandmini-purge valveshavebeeninstalled.
Thisisnotatechnical changesincethenoteswereonlyintendedtobeapplicable untilthecompletion ofthenecessary modifications.
Technical Specifications 4.4.5.1and4.4.6.2wererevisedtoremovethereference toTable3.6-1sincethisisbeingdeleted.-Thesespecifications werealsochangedtomakethemconsistent withStandardTechnical Specifications.
Inaccordance with10CFR50.91,thesechangestotheTechnical Specifications havebeenevaluated todetermine iftheoperation ofthefacilityinaccordance withtheproposedamendment would:1.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.
~~~'~,l~~I' IJIAttachment BPago4of4Theseproposedchangesdonotincreasetheprobability orconsequences ofapreviously evaluated accidentorcreateanewordifferent typeofaccident.
Furthermore, thereisnoreduction in'themarginofsafetyforanyparticular Technical Specification.
Thedetailedchangesaredescribed in,Attachment E.Therefore, Rochester GasandElectricsubmitsthattheissuesassociated withthisAmendment requestareoutsidethecriteriaof10CFR50.91;andanosignificant hazardsfindingiswarranted.
Isftv0 ATTACHMENT CResponseToNRCRequestForAdditional Information LetterFrom-A.R.
Johnson,NRC,toR.C.Mecredy,.RGRE,.datedMarch11,.1993 IPj;]l'I Attachment CPage1of17Asaresultofreviewing RG&E'sApplication forAmendment toOperating LicenseDPR-18withrespecttoremovingthelistofcontainment isolation valvesfromTechnical Specifications, theNRCresponded withaRequestforAdditional Information (seeletterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&E,datedMarch11,1993).Theissuesdiscussed inthisRAIhavealreadybeenaddressed withintheAmendment Request;however,aspecificresponsetoeachofthesixcommentsandquestions isprovidedbelow.Itshouldbenotedthattheresponses tothe56partQuestionP6relatedtoUFSARTable6.2-15andtheassociated figureshavenotbeenincorporated todate.Thenecessary changeswillimplemented duringthenextUFSARupdatecurrently scheduled forDecemberof1993.Thisisacceptable sincethelistingofcontainment isolation valveswillbemaintained inGinnaStationProcedure A-3.3.Consequently, theupdateoftheUFSARisnotnecessary withrespecttothesubjectTechnical Specification Amendment Request.RG&EwillalsoperformadetailedreviewofUFSARTable6.2-15andtheassociated figuresatthattimetoensureconsistency andcompleteness asrequested inyourMarchll,1993letter.ThelistingofCIVscontained inA-3.3hasbeenreviewedtoensurethatitiscomplete.
Firstparagraph ofyourSafetyEvaluation, secondsentence, referstoUFSARTable6.2-13,shouldthisbereferring toTable6.2-15?Thereference toUFSARTable6.2-13wasatypographical error.However,thenecessary listingofcontainment isolation valvesisnowmaintained inGinnaStationProcedure A-3.3.Consequently, allreferences toUFSARTable6.2-15inpreviously submitted Amendment RequestshavebeenreplacedwithProcedure A-3.3.2.According toGenericLetter91-08,"Removal.
ofComponent ListsfromTechnical Specifications (TS),"underthesectionentitled"Guidance ontheRemovalofComponent ListsfromTS,"itstatesinpart"...Alistofthosecomponents mustbeincludedinaplantprocedure thatissubjecttothechangecontrolprovisions forplantprocedures intheAdministrative ControlsSectionoftheTSAlthoughsomecomponents maybelistedintheUpdatedFinalSafetyAnalysisReport(UFSAR),theFSARshouldnotbethesolemeanstoidentifythesecomponents.
Licensees areonlyrequiredtoupdatetheFSARannually, andtheyareonlyrequiredtoreflectchangesmade6monthsbeforethedateoffiling.Thus,theFSARmaybeoutofdatebyasmuchas18months...".YourSafetyEvaluation doesnotaddresswhatTScontrolled procedure coversthislistofcontainment isolation valves.~ResenseThelistingofcontainment isolation valvesisnowmaintained inGinnaStationProcedure A-3.3.Thisprocedure issubjecttoTechnical Specification 6.8whichrequiresreviewbytheGinnaStationPlantOperations ReviewCommittee (PORC)andapprovalbythePlantManagerforanychanges.Thesafetyevaluation contained inAttachment Bhasbeenupdatedtoreflectthisinformation.
ssa~$~gqa"~'a~al~a~sSdassaars~-4'ssslCa
)IIAttachment CPago2of173.'Proposed TS3.6.3"Containment Isolation Boundaries,"
itemsband~~~~cstate:"b.Isolateeachaffectedpenetration within4hoursbyuseof'tleastonedeactivated automatic valvesecuredintheisolation
position, oneclosedmanualvalve,orablindflange,orC~Verifytheoperability ofaclosedsystemfortheaffectedpenetrations within4hoursandeitherrestoretheinoperable boundarytoOPERABLEstatusorisolatethepenetration asprovidedin3.6.3.1.b within30days,or"Thebasisforthischangeisgivenas"Specification nowconsiders closedsystemsasanacceptable interimpassiveboundaryandismoreconsistent withStandardTechnical Specification."
However,thisdoesnotreflecttheStandardTechnical Specifications (STS)requirement.
STS3.6.3.Cstates:'"Isolate theaffectedpenetration flowpathbyuseofatleastoneclosedandde-activatedautomatic valve,closedmanualvalve,orblindflange.(4-hourcompletion time)Verifytheaffectedpenetration flowpathisisolated(onceper31days)"Therefore, theproposedchangetoTS3.6.3.Cisnotacceptable.
RGGEhas"removed-the previously submitted TS3.6.3.Cwithrespecttotheinterimuseofaclosedsystemasanacceptable boundaryforafailedcontainment isolation valve.TS3.6.3isnowconsistent withStandardTechnical Specifications.
4.Theterm"Isolation Valve"isusedintheproposedBasesSectionof4.4(page4.4-14),according totheSE,shouldhavebeenreplacedwiththeterm"Isolation Boundary."
Resonse:Theterm"Isolation Valve"iscorrectforthissectionoftheBasessincemostcontainment leakageobservedduringtestingatGinnaStationandthroughout thenuclearindustryisthroughisolation valvesandnotthroughpassivecontainment barrierssuchasblindflanges.Consequently, thebasessectionwasnotchanged.ProposedTS3.6.1.astates,"Closedvalvesmaybeopenedonanintermittent basisunderadministrative control."
GenericLetter91-08andyoursafetyevaluation referto"LockedorSealClosedcontainment isolation valves"notjust"closedvalves."ShouldproposedTS3.6.1.abereferring tolockedorsealclosedCIVs?
I%>>'tiV,'L'4lsk1I Attachment CPage3of17Resonse:.The'""locked or"=sealed" closed"terminology "wasnot"used-inTS3.6;l.asinceseveraltestconnections that.may.
be-required,to beopenedduringpoweroperation
-fortesting.purposes are,.notlocked'"'closed atGinnaStation.Thesevalvesare-administratively
'maintained closedduringpoweroperation persystemlineupprocedures andhave"containment isolation boundary" controltagsinstalled.
-Thisissueisalsoaddressed
.intheNovember30,1992submittal, Attachment D,Item428.Thesafetyevaluation contained inAttachment Bwasrevisedtoreflectthisinformation.
6.CommentswithregardtoR.E.GinnaUpdatedFinalSafetyAnalysisReport(UFSAR)Table6.2-15andFigures6.2-13through6.2-78arecontained onthe'ollowing pages.Identified discrepancies associated withproposedUFSARTable6.2-15.Valve/Penetration
~BounderDiscreanc1.1052829Positionindication incontrolroomismarked"NA"foramanuallyoperatedvalve.Shouldthisbe"No"forconsistency7 Resonse:Yes.Thepositionindication incontrolroomcolumnwillbe.updatedtoidentify"No".forthisvalve.Valve/Penetration
~BoundarDiscreanc2.105859AValvedoesnot.appearontheUFSARFigure6.2-18,asindicatedbyproposedUFSARTable6.2-15.3.105859BValvedoesnotappearontheUFSARFigure6.2-18,asindicated byproposedUFSARTable6.2-15.Resonse:UFSARFigure6.2-18willbeupdatedtoincludevalves859Aand859B.Thesevalvesarelocatedontwobranchlinesbetween864Aand859C.
I1IV~I Attachmont CPago4of17Valve/Penetration
~BoundarDiscreanc4.105864AThenormaloperations.position ofthevalveislistedas"C"(closed)inproposedUFSARTable6.2-15,however,itisindicated as"IC"(lockedclosed)onUFSARFigure6.2-18.Resonse:UFSARFigure6.2-18iscorrectinshowingthatthevalveisnormallylockedclosed.Table6.2-15willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc5.109"859AValve-doesnotappearontheUFSARFigure6.2-22,asindicatedbyproposedUFSARTable6.2-15.6.109859BValvedoesnotappearontheUFSARFigure6.2-22,asindicated byproposedUFSARTable6.2-15.Resonse:UFSARFigure6.2-22willbeupdatedtoincludevalves859Aand859B.Thesevalvesarelocatedontwobranchlinesbetween864Band859C.Valve/Penetration
~BoundarDiscreanc7.109864BThenormaloperations positionofthevalveislistedas"C"(closed)inproposedUFSARTable6.2-15,however,itisindicated as"LC"(lockedclosed)onUFSARFigure6.2-22.Resonse:UFSARFigure6.2-22iscorrectinshowingthatthevalveisnormallylockedclosed.Table6.2-15willberevisedtocorrectthisdiscrepancy.
t~$+Yl:1~5 Attachment CPage5of17Val.ve/Penetration
~BoundarDiscreancS.1129.11210.112200A200B202Thevalvetypeislistedasa."Globe"valveinproposed-UFSARTable6.2-15,however,itisindicated asa"Gate"valveonUFSARFigure6.2-25.Also,proposedUFSARTable6.2-15indicates thatthisvalvetripsonCIS,however,thisisnotnotedwitha"T"onUFSARFigure6.2-25.Thevalvetypeislistedasa"Globe"valveinproposedUFSARTabl,e6.2-15,however,itisindicated asa"Gate"valveonUFSARFigure6.2-25.Also,proposedUFSARTable6.2-15indicates thatthisvalvetripsonCXS,however,thisisnotnotedwitha"T"on.UFSARFigure6.2-25.Thevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveonUFSARFigure6.2-25..Also,proposedUFSARTable6.2-15indicates thatthisvalvetripsonCXS,however,thisisnotnotedwitha"T"onUFSARFigure6.2-25.Resonse:Table6.2-15correctly identifies allthreevalvesasglobevalveswhichreceiveacontainment isolation signal.Figure6.2-25willberevisedtocorrectthediscrepancies.
Valve/penetration
~BoundarDiscreancIl.112371Thevalvetypeislistedasa"Globe"val.veinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveonUFSARFigure6.2-25.Resonse:Table6.2-15correctly identifies 871asaglobevalve.Figure6.2-25willberevisedtocorrectthisdiscrepancy.
~IIy+4"I"43pt-~kXI'4.,4I Attachment CPage6of17Valve/Penetration
~BoundarDiscreanc12.11213.112820204AThisvalveisindicated onUFSARFigure6.2-25,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.Thisvalveisindicated onUFSARFigure6.2-25,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.Resonse:Manualvalves820and204Aarenolongeridentified ascontainment isolation valvesintheGinnaStationTechnical Specifications
-(see-letter.fromA.R.Johnson,NRC,toR.CMecredy,RGGE,
Subject:
IssuanceofAmendment No.52toFacilityOperating LicenseNo.DPR-18,datedApril20,1993).TheCIVdesignations forthesevalvesonUFSARFigure6.2-25willberemovedtoreflectthischange.Valve/Penetration
~BoundarDiscreanc14.123b9725Thenormaloperations positionofthevalveislistedas"C"(closed)inproposedUFSARTable6.2-15,however,itisindicated as"LC"(lockedclosed)onUFSARFigure6.2-26.Resonse:UFSARFigure6.2-26correctly shows9725asbeingnormallylockedclosed.Table6.2-15willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc15.127749AThemaximumisolationtimeaslistedinproposedUFSARTable6.2-15is"NA",however,itislistedinthecurrentTechnical Specifications ashavingamaximumisolation timeof60seconds.16.128749BThemaximumisolationtimeaslistedinproposedUFSARTable6.2-15is"NA",however,itislistedinthecurrentTechnical Specifications ashavingamaximumisolation timeof60seconds.
I~JQWl\~I'li'.L'blh Attachment CPage7of17Resonse:TheTechnical Specifications containatypographical errorsince-'thesetwo.valvesdo-not-.=receive'..nor, requirea.containment
--'"isolation
-signal.-Consequently.,
-a-..60>>second..maximumisolation timeisnotapplicable.
Thisissuewasaddressed inaletterfromR.C.Mecredy,RGGE,toA.R.Johnson,NRC,
Subject:
Containment Isolation Valves745,749Aand749B,datedJuly9,1990.Valve/Penetration
~BoundarDiscreanc17.1431721ProposedUFSARTable6.2-15indicates thatthisvalvetripsonCIS,however,thisisnotnotedwitha"T"onUFSARFigure6.2-45.~Resonse"Table.6.2-15 correctly identifies 1721asreceiving acontainment isolation signal.Figure6.2-45willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc18.201aNAThesystemislistedinproposedUFSARTable6.2-15as"Reactorcompartment coolingunitA"andshouldbelistedas"Reactorcompartment coolingunitAsupply"forconsistency.
Resonse:Thesystemidentification forPenetration 201awillberevisedtoincludetheword"supply".
Valve/Penetration
~BoundarDiscreanc19.201bPI-2141Thisinstrument isstillnotindicated inUFSARFigure6.2-46(47JasaCIB,eventhoughyoustatedinyourresponsetotheSeptember 26,1991,RAIthatthisitemwascorrected.
24.209aPI-2140Thisinstrument isindicatedonUFSARFigure6.2-46(47]asaCIB,however,itisnotindicated inproposedUFSARTable6.2-15.
III0~'Je Attachment CPage8of17Resonse:TheCIBdesignation wasaddedtothewrong-pressure indicator onFigure6.2-47.Consequently, aCIBdesignation.
will..be.
addedto-PI--2141 andremovedfromPI-2140.-Pressure
-indicator.,PI-2140 isnotacontainment isolation valvesinceitlocated'pstream ofvalve4635(i.e.,notbetween4635andcontainment).
Val.ve/Penetration
~BoundarDiscreanc20.206b5733Thisvalveisindicated inUFSARFigure6.2-54,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.21.207b3B.32139.322573457015702Thisvalveisindicated inUFSARFigure6.2-56,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.Thisvalveisindicated onUFSARFigure6.2-71,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.ThisvalveisindicatedonUFSARFigure6.2-72,andinthecurrentTechnical Specifications asaCIV,however,itisnotindicated inproposedUFSARTable6.2-15.Resonse:Manualvalves5733,5734,5701and5702arenolongeridentified ascontainment isolation valvesintheGinnaStationTechnical Specifications (seeletterfromA.R.Johnson,NRC,toR.CMecredygRGEE,
Subject:
IssuanceofAmendment No.52toFacilityOperating LicenseNo.DPR-IB,datedApril20,1993).TheCIVdesignations forthesevalvesonUFSARFigures6.2-54,6.2-56,6.2-71and.6.2-72willberemovedtoreflectthischange.Valve/Penetration
~BoundarDiscreanc22.207b5736Thevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveinUFSARFigure6.2-56.
(I'Jyg'~,A~.*p>>}IEge*'AII' Attachment CPage9of17Resonse:Figure6.2-56iscorrectinshowingthat'736isa-gatevalve.-Table6.2-15will-be-revised-to--correct-.this-discrepancy..
-.,--Val.ve/Penetration
~BoundarDiscreanc23.209aNAThesystemislistedas"Reactorcompartment coolingunitBreturn"andaccording toUFSARFigure6.2-47itshouldbelistedas"Reactorcompartment coolingunitBsupply".Resonse:Thesystemidentification forPenetration 209awillberevisedtoreplace"return"with"supply".
Valve/penetration
~BounderDiscreanc25.2095NAThesystemislistedas"Reactorcompartment coolingunitAsupply"andaccording toVFSARFigure6.2-46itshouldbelistedas"Reactorcompartment coolingunitBreturn".Resonse:Thesystemidentification forPenetration 209bwillberevisedtoreplace"Asupply"with"Areturn"(not"Breturn"assuggested).
Valve/Penetration
~BoundarDiscreanc26.21010214SNote15islistedintheproposedVFSARTable6.2-15asapplicable.
However,note17appearstobemoreappropriate.
Inaddition, note17wouldmakeitconsistent withvalve10215S.Resonse:Table6.2-15willberevisedtocorrectthetypographical errorandreplacenote15withnote17.
III4,I%l Attachment CPage10of17Valve/Penetration
~BoundarDiscreanc27.3005879ThisvalveislistedinproposedUFSARTable6.2-15,andinthecurrentTechnical Specifications aasCIV,however,itisnotindicated asaCIVonUFSARFigure6.2-58.Resonse:AOV5879isnotacontainment isolation valve.Itisonlyusedbelowcoldshutdownconditions toprovidecontainment integrity whentheblindflangeisremoved.SeeUFSARTable6.2-15,Note29andTechnical Specification Table3.6-1,Note22.Valve/Penetrati on~Bounder28.305a1556DiscreancThemaximumisolationtimeaslistedinproposedUFSARTable6.2-15is"NA",however,itislistedinthecurrentTechnical Specifications ashavingamaximumisolation timeof60seconds.Resonse:TheTechnical Specifications containatypographical errorsincemanualvalve1556doesnotreceivenorrequireacontainment isolation signal.Consequently, a60secondmaximumisolation timeisnotapplicable.
Thisisanormallylockedclosedvalve.Val.ve/Penetration
~BoundarDiscreanc29.3079227ThemaximumisolationtimeaslistedinproposedUFSARTable6.2-15is6'0seconds,however,thecurrentTechnicalSpecifications hasthemaximumisolation timelistedas"note18neResonse:Acontainment isolation signalwasinstalled toAOV9227in1981underEngineering WorkRequestNo.1833.Subsequent tothismodification, theNRCacceptedthatnocontainment isolation signalwasrequiredforthisvalve(seeletterfromD.M.Crutchfield, NRC,toJ.E.Maier,RG&E,
Subject:
Containment Isolation, datedMay22,1982).RG&Ehasnotremovedthesubjectisolation signal.SinceAOV9227isacontainment isolation valve,a60secondmaximumisolation timewasaddedinordertobeconsistent withotherautomatic containment isolation valves.
IIgi,I
~~I"IAttachment CPago11of17Valve/'30.'308'IA-2010.'his.'nstrument
':isstill--not,.indicated inUFSARFigure6.2-65asaCIB,eventhoughyoustatedinyourresponsetotheSeptember 26I1991RAIthatthisitemwascorrected.
32.311TIA-2011Thisinstrument isstillnotindicated inUFSARFigure6.2-65asaCIB,eventhoughyoustatedinyourresponsetotheSeptember 26,1991RAIthatthisitemwascorrected.
34.315TIA-2012This.instrument isstillnotindicated inUFSARFigure6.2-65asaCIB,eventhoughyoustatedinyourresponsetotheSeptember 26,1991RAIthatthisitemwascorrected.
40.323TI'A-2013 Thisinstrument isstillnotindicated inUFSARFigure6.2-65asaCIB,eventhoughyoustatedinyourresponsetotheSeptember 26,1991RAIthatthisitemwascorrected.
Resonse:Thenecessary CIBdesignations willbeaddedtoUFSARFigure6.2-65forTIA-2010, TIA-2011, TIA-2012, andTIA-2013.
Valve/Penetration
~BoundarDiscreanc31.30836e319NANAThispenetration wasindicated aspenetration 319onthecurrentTechnical Specifications.
Thispenetration wasindicated aspenetration 308onthecurrentTechnicalSpecifications.
Resonse:Thevalvesforpenetrations 308and319arereversedinTechnical Specification Table3.6-1.
~~1$1~fpt Attachment CPage12of17Valve/Penetration
~Boundary Discreanc33.313-BlindFlangeTheBlindFlange-isindicated inUFSARFigure6.2-69as"CIV",shouldthisbe"CIB"?Resonse:Figure6.2-69willberevisedCIB.toreplacetheCIVdesignation withValve/Penetration
~BoundarDiscreanc35.317BlindFlangeTheBlindFlangeisindicated inUFSARFigure6.2-70as"CIV",shouldthisbe"CIB"PResonse:Figure6.2-70willberevisedCIB.toreplacetheCIVdesignation withValve/Penetration
~BoundarDiscreanc37.320Resonse:4641Thisvalvewasindicated as4647,inthecurrentTechnical Specifications.
Valve4647isatypographical errorintheTechnical Specifications.
Thisdrainvalveisinserieswithvalve12500Hwhichisidentified onUFSARTable6.2-15asaCIV.Thesecondcontainment boundaryisaCLICforthispenetration.
Valve/Penetration
~BoundarDisereanc41.332a922Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Globe"valveinUFSARFigure6.2-74.AlsoproposedUFSARTable6.2-15indicates that'hisvalve'snormaloperating positionis"C"(closed),
however/itisindicated asopeninUFSARFigure6.2-74.Inaddition, themaximumisolation timeaslistedinproposedUFSARTable6.2-15is3seconds,however,thecurrentTechnical Specificationshasthemaximumisolation timelistedasIINAII lP Attachment CPage13of1742.332a924Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicatedasa"Globe"valveinUFSARFigure6.2-74.AlsoproposedUFSARTable6.2-15indicates thatthisvalve'snormaloperatingpositionis"C"(closed),
however,itisindicated asopeninUFSARFigure6.2-74.Inaddition, themaximumisolation timeaslistedinproposedUFSARTable6.2-15is3seconds,however,thecurrentTechnicalSpecifications hasthemaximumisolation timelistedas"NA".43.332b923Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Globe"valveinUFSARFigure6.2-74.AlsoproposedUFSARTable6.2-15indicates thatthisvalve'snormaloperating positionis"C"(closed),
however,itisindicated asopeninUFSARFigure6.2-74.Inaddition, themaximumisolation timeaslistedinproposedUFSARTable6.2-15is3seconds,however,thecurrentTechnical Specifications hasthemaximumisolationtimelistedas"NA".44.332d921Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Globe"valveinUFSARFigure6.2-74.AlsoproposedUFSARTable6.2-15indicates thatthisvalve'snormaloperating positionis"C"(closed),
however,itisindicated asopeninUFSARFigure6.2-74.Inaddition, themaximumisolation timeaslistedinproposedUFSARTable6.2-15is3seconds,however,thecurrentTechnicalSpecifications hasthemaximumisolationtimelistedas"NA".
I'cV4-~wtV4I46T'/P Attachment CPage14of17Resonse:Table6.2-15iscorrectinidentifying 921,922,923,and924asgatevalvesand'inshowing.that-'-these valves:are..normally closed.Figure6.2-74will-be.revisedto-correct--these-discrepancies.
Thethreesecondisolation timeforthesesolenoidvalvesisconsistent withStandardReviewPlan6.2.4.II.6.n sincethesevalvesareopentocontainment atmosphere andreceiveaCIS.Valve/Penetration
~BoundarDiscreanc45.4013521Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicated asa"G1obe"valveinUFSARFigure6.2-76.Resonse:Figure6.2-76iscorrectinshowing3521asaglobevalve.Table6.2-15willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc46.401PT-469AInstrument isindicated asInsideContainment inproposedUFSARTable6.2-15,however,itisindicated asoutsidecontainment inUFSARFigure6.2-76.Resonse:Figure6.2-76iscorrectinshowingPT-469Aislocatedoutsidecontainment.
Table6.2-15willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc47.4023520Thevalvetypeislistedasa"Gate"valveinproposedUFSARTable6.2-15,however,itisindicated as.a"Globe"valveinUFSARFigure6.2-76.Resonse:Table6.2-15iscorrectinidentifying 3520asagatevalve.Figure6.2-76willberevisedtocorrectthisdiscrepancy.
ItC1kt~1 Attachment CPago15of17Valve/Penetration
~BoundarDiscreanc48.4033995XThevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveinUFSARFigure6.2-78.Resonse:Figure6.2-78iscorrectinshowing3995Xasagatevalve.Table6.2-15willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BoundarDiscreanc49.4034011AThevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveinUFSARFigure6.2-78.Resonse:Table6.2-15iscorrectinidentifying that4011Aisaglobevalve.Figure6.2-78willberevisedtocorrectthisdiscrepancy.
Valve/Penetration
~BounderDiscreanc50.4043994EThevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveinUFSARFigure6.2-78.Resonse:Figure6.2-78iscorrectinshowing3994Easagatevalve.Table6.2-15willberevisedtocorrectthisdiscrepancy.
Val,ve/Penetration
~BoundarDiscreanc51.4044012AThevalvetypeislistedasa"Globe"valveinproposedUFSARTable6.2-15,however,itisindicated asa"Gate"valveinUFSARFigure6.2-78.Resonse:Table6.2-15iscorrectinidentifying that4012Aisaglobevalve.Figure6.2-78willberevisedtocorrectthisdiscrepancy.
I1Iw*%I'0'gIt Attachment CPage16of17LocationDiscreanc52.Note17Ifthisnotedescribes valvesthatarenotCIVs,thentoavoidconfusion, thenoteshouldstatethatthesevalvesarenotCIVs.Resonse:Table6.2-15note17willberevisedtospecifically statethatthesubjectvalvesarenotCIVs.LocationDiscreanc53.Figure6.2-13Thereisnoindication onthefigureofwherethe"CIB"isforeitherpenetration 2or29.Resonse:Figure6.2-13willbereplacedwithtwoseparatefiguresforPenetration 2and29.ThesenewfigureswillidentifythelocationoftheCIBsasnecessary.
LocationDiscreanc54.Figure6.2-65The"CIB"Capdownstream of12500H/12500K doesn'tshowupontheproposedUFSARTable6.2-15foreitherpenetration 320or312.Thefiguredoesnotindicatetheassociation betweenpenetrations andfancoolers.Resonse:TheCIBdesignation isincorrect onFigure6.2-65sincetheCLICandvalves12500Hand12500Kprovidethenecessary twocontainment boundaries.
ThefigurewillberevisedtodeletetheCIBdesignation andprovidearelationship betweenthefancoolersandassociated penetrations.
LocationDiscreanc55.Figure6.2-76"CIV"appearsonthefigure(aboveCIV11031andtotheleftofvalve3409A)butdoesnotappeartobeassociated withanyparticular valve.Resonse:Figure6.2-76willbeupdatedtoremovethesubjectCIVdesignation.
I1Ie~0~M0 Attachment CPage17of17LocationDiscreanc56.Thereisalackofconsistency forUFSARFigures'6;2-'13':through
'6.2--78.with--respect to""the'ymbols-used-to--represent "the*directionofflowthroughthecheckvalves,andthesymbolsusedtorepresent airoperatedvalves.Inaddition, notallfiguresindicate"CLIC"or"ClosedSystem"whereitisapplicable.
Resonse:Allfigureswillbereviewedtoensureconsistency withrespecttoair-operated valvedesignations, checkvalveflowdirections, andtheuseofclosedsystemindications.
1f ATTACHMENT DGinnaStationProcedure A-3.3 fC ROCHESTER GASANDELECTRICCORPORATION GINNASTATIONCONTROLLED COPYNUMBEROCREV.NO,1NTAINMENT INTERITYPRRAMTEHNIALREVIEWPORCREVIEWDATEPLANTSUPERINTENDENT EFFECTIVE DATECATEGORY1.0Fo~~<FORMATlOR OevREVIEWEDBY:THISPROCEDURE CONTAINS~lPAGES
'0 A-3.3:1NTAINMENT INTERITVPRRAM1.0~PPQ$E:Todelineate thecontainment integrity programasrequiredbyTechnical Specifications 3.6and3.8,andGenericLetter88-17forconditions abovecoldshutdown, refueling operations, andreducedinventory conditions, respectively.
2.02.12.22.3Technical Specifications 3.6and3.8.GenericLetter88-17,LossofDecayHeatRemoval.UpdatedFinalSafetyAnalysisReport,Section6.2.4.2.4DesignAnalysisDA-NS-93402-21, EWRNo.10084,Containment Isolation SystemReview.2.6LetterfromR.C.Mecredy,RG&EtoA.R.Johnson,NRC-
Subject:
AOV-745,MOV-749AandMOV-749B, dated7/9/90.Inter-Office Correspondence, JohnCookandMarkFlahertytoPORC,Subject;Containment Integrity DuringRefueling, dated2/20/92.2.70-1.1B-Establishing Containment Integrity.
2.&0-2.3.1A-Containment ClosureCapability in2HoursDuringRCSReducedInventory Operation.
2.92.102.112.122.13PTI'-23Series.S-30.7,Containment Isolation ValveVerification.
PT-39,PrimarySystemLeakageEvaluation Inservice Inspection.
0-15.2,RequiredValveLineupforReactorHeadRemoval.0-15.7,FuelHandlingInstruction Pre-Loading andPeriodicValveAlignment Check.
IP A-3.3:23.0Thecontainment integrity programisdesignedtoprovideassurance thatthenecessary containment isolation boundaries areavailable forallrequiredplantconditions.
Thisprogramisorganized toaddressthreeplantconditions:
a.Containment Integrity duringRefueling.
3.2b.Containment Integrity duringReducedRCSInventory.
c.Containment Integrity aboveColdShutdown.
Therequirements foreachoftheseconditions isdiscussed below.Containment Integrity duringRefueling.
3.2.1Duringplantconditions requiring containment integrity forrefueling, eachpenetration musthaveasinglebarriertothereleaseofradioactive material.
Thissinglebarriermayconsistofanyoneofthefollowing alternatives:
a.Aclosedsysteminsideoroutsidecontainment suchthata"directaccess"releasepathtotheoutsideofcontainment atmosphere isnotprovided.
b.Aclosedisolation valve(including checkvalvewithflowsecured),
blindflangeormanualvalve.c.Anautomatic isolation valvethatclosesonaContainment Ventilation Isolation (CVI)signalfromhighcontainment radioactivity.
3.2.2Inadditiontotherequirements above,Technical Specification 3.8requiresthat"...allautomatic containment isolation valvesshallbeoperableoratleastonevalveineachlineshallbelockedclosed."Sincethenormalcontainment isolation signalisnotavailable duringtherefueling modeofoperation, forthosepenetrations withautomatic isolation valves,thosevalvesmustbecapableofbeingclosedremotely.
Ifthosevalvesarenotcapableofbeingclosedremotely(i.e.inoperable) thenceaffectedpenetration mustbeisolatedbyalockedclosedmanualvalveorblindflange.Ifamanualvalveorblindflangeisnotavailable, thenaheldclosedautovalve(perA-1401)withmotivepowerremovedprovidesequivalent isolation.
3.2.3Ithnotintendedthatthebarriersprovidedforcontainment isolation duringrefueling berestricted tobarrierstestedtotherequirements ofAppendixIto10CFR50.Thebasisforrefueling integrity istopreventthereleaseofradioactivity resulting fromafuelhandlingeventduringrefueling operations.
Sincethereisnopotential forcontainment pressurization, anydevicewhichprovidesanatmospheric pressureboundaryissufficient.
3.2.4Containment integrity forrefueling isverifiedthroughperformance of0-15,2and0-15.7.
A-3.3:3Containment Integrity DuringReducedRCSInventory.
Containment integrity duringreducedinventory conditions isprovidedbymaintaining available onebarrierforeachpenetration.
Sincethereisapotential forcontainment pressurization duringlossofcorecooling,thisbarriershouldbeoneofthetwobarriersusedfornormalcontainment isolation withRCSgreaterthan200'F.Allpenetrations arerequiredtobecapableofbeingclosedwithin2hoursfollowing alossofRHR.This2hourtimeframecanbeextendedifthetimetoreachsaturation andcoreuncoveryisincreased duetolowdecayheatlevels.3.3.2Containment integrity duringreducedRCSinventory isverifiedthroughperformance of0-2.3.1A.
3.4Containment Integrity aboveColdShutdownincluding normalpoweroperation.
3.4.1Reference 2.4providesthedesignbasisforthecontainment isolation configuration andtesting.Anychangetothisprocedure, including Attachment A,mustbereviewedbyNuclearSafetyandLicensing.
3.4.2Attachment Aprovidesalistingforeachpenetration ofthevalvesandotherboundaries requiredforcontainment integrity abovecoldshutdown.
Theseboundaries areleaktestedperAppendixJto10CFR50exceptwherespecificexemptions havebeenapproved.
Thistableisorganized asfollows:3.4.2.1~~~5ggm-description ofthesystemwhichpenetrates containment.
3.4.2.23.4.2.33.4.2.4-uniqueidentification numberforthepenetration.
-containment isolation valvesorboundaries forthepenetration.
di'fhbareavailable foreachpenetration.
Thisisusedsincemanyprocesslineshavemultiplebranchlinespriortoenteringorexitingcontainment.
Thefirstcharacter definesthebranchlinewhichthecontainment isolation valveorboundaryisolates.
Thesecondcharacter definestheisolation barrierwhichthevalveprovides(i.e.,firstorsecond).Asanexample,Penetration 107liststhefollowing containment boundaries:
17231728ala2AOV1723isonecontainment barrierwhileAOV1728isasecondbarrier.Abovecoldshutdown, bothvalvesmustbeoperableandcapableofbeingclosed.IfAOV1723wereinoperable, thenAOV1728isthepreferred valvetobeclosedinaccordance withTechnical Specification 3.6.3.Conversely, AOV1723isthepreferred valvetobeclosedifAOV172&wereinoperable.
IC' A-3.3:4Asanexampleofpenetrations withmultiplebranchlines,Penetration 124bliststhefollowing containment boundaries:
157215731574ala2a2Abovecoldshutdown, allthreevalvesmustbeoperableandcapableofbeingclosed.Ifmanualvalve1572wereinoperable, thenBOTHmanualvalves1573and1574mustbeclosedinaccordance withTechnical Specification 3.6.3.However,if1573wereinoperable, only1572mustbeclosed(valve1574isnotaffected).
3.4.2.53.4.2.63.4.2.7~VLvVT~-typeofcontainment isolation valve(e.g.,MOV).~-Specificnotesrelatedtothecontainment isolation valveorboundary.
-Maximumallowed.closuretimeinsecondsforthosevalveswhichreceiveacontainment isolation signal.3.4.3Priortoheatupabovecoldshutdown, containment integrity isverifiedthroughperformance ofpr'ocedure 0-1.1B,PIT-23A,PT-39andS-30.7,Closedsystemsinsideandoutsidecontainment areverifiedthroughtherequiredsystemlineups.3.53.5.1ClosedSystems:Closedsystemsinsideandoutsidecontainment areusedforseveralpenetrations asacontainment isolation barrier.Theintegrity oftheseclosedsystemsasabarrieristypically confirmed bynormalsystemoperation orperiodictest.SincetheseclosedsystemsareexemptfromtestingperAppendixJto10CFR50,exceptasnotedbelow,theallowable leakage(e.g.packingleaksandheatexchanger tubeleaks)hasbeenbasedupontheguidanceofASME/ANSI OMa-1988, OM-10forthesizeofisolation valveassociated withtheclosedsystem.Thisguidanceallowsaleakagerateof.5gpmperinchofnominalvalvediameter.
3.5.1.1ServiceWaterSystem(Penetrations 201a,201b,209a,209b,308,311,312,315,316,319,320and323)-Allpipinginsidecontainment forthesepenetrations uptoandincluding thefirstavailable isolation valveonallbranchlinesprovideonecontainment barrier.'Iceintegrity ofthispipingisverifiedbynormalServiceWatersystemoperation andcontainment leakagedetection systems.
A-3.3:5Allowable leakagefortheservicewatersystemsincontainment areasfollows:201a/209b209a/201b319/308316/311320/315312/323SWto/fromRxCompartment CoolerASWto/fromRxCompartment CoolerBSWto/fromFanCoolerASWto/fromFanCoolerBSWto/fromFanCoolerCSWto/fromFanCoolerD1.25gpm1.25gpm4.0gpm4.0gpm4.0gpm4.0gpmComponent CoolingWaterSystem(Penetrations 124a,124c,125,126,127,128,130,and131)-Allpipinginsidecontainment forthesepenetrations uptoandincluding thefirstavailable isolation valveonallbranchlinesprovideonecontainment barrier.Theintegrity ofthispipingisverifiedbynormalComponent CoolingWatersystemoperation andcontainment leakagedetection systems.Theonlyexception isforpenetrations 124aand124c(ExcessLetdownHeatExchanger cooling)whicharenormallyisolated.
Allowable leakageforthecomponent coolingwatersystemsinsidecontainment areasfollows:~L~R~124a/cCCWto/fromExcessLtdHx1.0gpm127/126CCWto/fromRCPA2.0gpm128/125CCWto/fromRCPB2.0gpm131/130CCWto/fromRxSuptCooling3.0gpmSteamGenerator (Penetrations 119,123b,206b,207b,321,322,401,402,403,and404)-Thesteamgenerator tubes,shellandallconnected pipinginsidecontainment forthesepenetrations uptoandincluding thefirstavailable isolation valveonallbranchlinesprovideonecontainment barrier.Theintegrity ofthispipingisverifiedbynormalpoweroperation andcontainment leakagedetection systems.Primarytosecondary steamgenerator tubeleakageislimitedperTechnical
~Specification 3.1.5.2to0.1gpm.Theallowable leakageforthelinesassociated withthesteamgenerator closedsystemarebasedonthenominalisolation valvesizeforthatline.Formainsteamandmainfeedwater linesallowable leakagewillbelimitedtothatallowedfortheAuxiliary andStandbyFeedwater systems.5XKcHlLu&hh119123b401402403404206b207b321322SAFWtoSGASAFWtoSGBMSfromSGAMSfromSGBMFWtoSGAMFWtoSGBSGASampleSGBSampleSGABlowdownSGBBlowdown1.5gpm1.5gpm1.5gpm1.5gpm1.5gpm1.5gpm.375gpm.375gpm1.0gpm1.0gpm I
A-3.3:6ChargingSystem(Penetrations 100,102,106,and110a)-Allpipingoutsidecontainment fromthepenetration uptothedischarge ofthethreepositivedisplacement pumps,including thefirstavailable isolation valveonallbranchlines,provideonecontainment barrier.Theintegrity ofthispipingisverifiedbynormalChargingsystemoperation andoperatorrounds.Theallowable leakageforthelinesassociated withchargingsystemoutsidecontainment is1.0gpm.~Pn100102106110aChargingtoRCSLoopBAltChargingtoLoopARCPASealWtrInletRCPBSealWtrInlet1.0gpm1.0gpm1.0gpm1.0gpmSafetyInjection (Penetrations 101and113)-Allpipingoutsidecontainment fromcheckvalves889A/Band870A/Btothedischarge ofeachSafetyInjection pump,including thefirstavailable isolation valveonallbranchlines,provideonecontainment barrier.Theintegrity ofthispipingisverifiedbysystemlineupsandbythemonthlyandquarterly pumptests.Theallowable leakageforthesafetyinjection systemisspecified inPT-39.Containment Spray(Penetrations 105and109)-Allpipingoutsidecontainment fromcheckvalves862A/BtoMOVs860A/B/C/D, including thefirstavailable isolation valveonallbranchlines,provideonecontainment barrier.Theintegrity ofthispipingisverifiedbysystemlineupandbythemonthlyandquarterly pumptests.Theallowable leakageforthecontainment spraysystemisspecified inPT-39.ResidualHeatRemoval(Penetrations 111,140,141,and142)-Allpipingoutsidecontainment including thefirstavailable isolation valveonallbranchlinesprovideonecontainment barrier.Theintegrity ofthispipingisverifiedbymonthlyandquarterly pumptestsandbynormalsystemoperation duringshutdown.
Theallowable leakagefortheresidualheatremovalsystemisspecified inPT-39.HydrogenMonitoring System(Penetrations 332a,332b,and332d)-Allpipingoutsidecontainment including thefirstavailable isolation valveonallbranchlinesprovideonecontainment barrier.Theintegrity ofthispipingisverifiedbyannual10CFRSOAppendixJtesting.ChargingSystem-SealWaterReturn(penetration 108)-Allpipingoutsidecontainment fromMOV-313totheVCT,including thefirstavailable isolation valveonallbranchlines,providesonebarrier.Theintegrity ofthispipingisverifiedbynormalsystemoperation andoperatorrounds.Theallowable leakageforthesealwaterreturnlinesoutsidecontainment is1.5gpm.MRCQIRK:None.
ATl'ACHMENT AA-3.3:7~asternSteamGenerator Inspection/
Maintenance FuelTransferTubeChargingLinetoLoopBSafetyInjection PumpBDischarge Alternate ChargingtoColdLegA29100101102Valval~BNIdINANASAC0581528153370BCLOG870B889BCLOC12407PI-923APT-923885B383BCLOGisolation Positionala2al,a2a2a2ala2alala2blblblb2ala2Valve~2eBlindFlangeBlindFlangeBlindFlangeManualManualCheckNACheckCheckNAManualNANAManualCheckNANotesMaximumisolation Yimo~sacs.Construction FireServiceWater103NA5129alWeldedCapa2Manual9Containment SprayPumpA105862ACLOC2829869A285628252825A864A859A859B859Cala2NAblb2clC2dld2d2d2CheckNAManualManualManualManualManualManualManualManualManual1026,136,136121212ReactorCoolantPumpASealWaterInletSumpADischarge toWasteHoldupTankReactorCoolantPumpSealWaterReturnLineandExcessLetdowntoVCT106107108304ACLOG17231728313CLOGala2ala2ala2CheckNAAOVAOVMOVNA14606060 AITACHMENT AA-3.3:8~Ss~teContainment SprayPumpBReactorCoolantPumpBSealWaterInletSafetyInjection TestLineResidualHeatRemovaltoColdLegBLetdowntoNonregenerative HeatExchanger SafetyInjection PumpADischarge StandbyAuxil-iaryFeedwater LinetoSteamGenerator ANitrogentoAccumulators Pressurizer ReliefTanktoGasAnalyzerPenetration No.109110a110b112113119120a120bValvai~Blvall862BCLOG2830869B285828262826A864B859A859B859C304BCLOG8797202840284728482853959CLOC371200A200B202203CLOG371427'70A889ACLOG12406PI-922APT-922Cap(PT-922) 885A9704A9723CLIC8468623539546iaolation
~aitionala2NAblb2clc2dld2d2d2ala2al,a2alalalalala2a2a2alalalalala2NAalala2blblblblb2alala2ala2ala2Valve~TCheckNAManualManualManualManualManualManualManualManualManualCheckNAManualMOVManualManualManualManualAOVNAAOVAOVAOVAOVReliefNAAOVAOVCheckCheckNAManualNANANAManualMOVManualNAAOVCheckAOVManual~ates1026,136,1361212121517666635163616361118Maximumiaoiation Tima60606060606060
ATI'ACHMENT AA-3.3:9~sstemMakeupwatertoPressurizer ReliefTankNitrogentoPressurizer ReliefTankContainment PressureTransmitter PT945andPT946ReactorCoolantDrai.nTanktoGasAnalyzerLineStandbyAuxil-iaryFeedwater LinetoSteamGenerator BExcessLetdownHeatExchanger CoolingWaterSupplyPostAccidentAi.rSampletoCommonReturnExcessLetdownHeatExchanger CoolingWaterReturnPostAccidentAi.rSampletoFanCComponent CoolingWaterfromReactorCoolantPumpBComponent CoolingWaterfromReactorCoolantPumpAComponent CoolingWatertoReactorCoolantPumpAComponent CoolingWatertoReactorCoolantPumpBPcncttation 12la121b121c123a123b124a124b124c124d125126127128Valve/~B508529528547PT9451819APT9461819B1600A165517899704B97259724CLIC743CLIC157215731574745CLIC156915701571759BCLIC759ACLIC749A750ACLIC749B750BCLICbohtionPosiuonala2ala2ala2blb2NAala2alalala2ala2ala2a2ala2ala2a2ala2ala2ala2a2ala2a2Valve~TQBAOVCheckCheckManualNAManualNAManualSOVManualAOVMOVManualManualNACheckNAManualManualManualAOVNAManualManualManualMOVNAMOVNAMOVCheckNAMOVCheckNANotes6181920,37191919373019373019MaximumIsolation Time~ceca.6060 A%I'ACHMENT AA-3.3:10~asternReactorCoolantDrainTankandPressurizer ReliefTanktoContainment VentHeaderComponent CoolingWaterfromReactorSupportCoolingComponent CoolingWatertoReactorSupportCoolingContainment Mini,-Purge ExhaustResidualHeatRemovalPumpsuctionfromHotLegAResidualHeatRemovalPumpASuctionfromSumpBResidualHeatRemovalPumpBSuctionfromSumpBReactorCoolantDrainTankDischarge LineReactorCompartment CoolingUnitASupplyReactorCompartment CoolingUnitBReturnHydrogenRecombiner B(Pilot)Penettation 129130131132140141142143201a201b202aValve/~80UNI1713179317861787814CLIC813CLIC79707971Cap70127632786CLOG850ACLOG851A1813A850BCLOG851B1813B1003A1003B1709G1722172147574775CLIC463646584776PI-2141coats2lal)CLIC1076B1021181isolation Positionaia2blb2ala2ala2a1a2a2alalala2ala2a2bl,b2ala2a2bl,b2alalalala2alala2alalalalala2ala2Valve~TeCheckManualAOVAOVMOVNAMOVNAAOVAOVNAMOVManualManualNAMOVNAMOVMOVMOVNAMOVMOVAOVAOVManualManualAOVManualManualNAManualNAManualNANANAManualSOVNotes191929176616211630322116303223282228Maximumisolation Time~i60606060606060 ATTACHMENT AA-3.3:11~Ss~teHydrogenRecombiner B(Main)Containment PressureTransmitter PT947andPT948PostAccidentAirSamplefromFanDPostAccidentAirSamplefromCommonHeaderPenetration No.202b203a203b203cValve/~Sound1084B1021381PT9471819CPT9481819D156315641565156615671568iaolation Poat>onala2ala2blb2ala2a2ala2a2Valve~atesManualSOVNAManualNAManualManualManualManualManualManualManualMaximumiaolation Time~scca.PurgeSupplyDuctHotLegLoopBSamplePressurizer LiquidSpaceSample204205206aACD935869955956D966C953956E966Bal,a2NANAala2NAala2BlindFlangeAOVAOVManualAOVAOVManualAOV256060SteamGenerator 206bASampleCLIC57355749ala2a2NAAOVManual1860Pressurizer SteamSpaceSample207a951956F966ANAala2AOVManualAOV60SteamGenerator 207bBSampleCLIO57365754ala2a2NAAOVManual1860ReactorCompartment CoolingUnitBSupplyReactorCompartment CoolingUnitAReturnOxygenMakeuptoRecombiners A6B209a209b21046354637CLIC463847584759PI-2232CLIO1080A102148110214S1021581102158alala2alalalalala2ala2NAa2NAManualManualNAManualManualReliefNANANAManualSOVSOVSOVSOV23282228llll ATI'ACHMENT AA-3.3:12~SstemPurgeExhaustDuctAuxiliary SteamSupplytoContainment Auxiliary SteamCondensate ReturnHydrogenRecombiner A(Pilot)HydrogenRecombiner A(Main)Containment AirSamplePostAccidentContainment AirSampleInletContai.nment AirSamplePostAccidentContainment AirSamplePostAccidentContainment AirSampleOutFireServiceWaterServi.ceWaterfromFanCoolerAMini-Purge SuPPlYInstrument AirtoContainment ServiceAirtoContai.nment Penetration
<<o.300301303304a304b305a305b305C305D305E307308309310a310bValve/~~eeaauU~ACD92587961516165615261751076A10205811084A1020981155415551556159815991557155815591560156115621596159792279229462946334655FIA-2033CeaeQXFIA.%33)
TIA-2010CLIC744574785392539371417226boiation~Positonal,a2NAala2ala2ala2ala2ala2a2ala2ala2a2ala2a2ala2ala2alalalalalala2ala2ala2ala2Valve~Tp~BlindFlangeAOVManualManualManualManualManualSOVManualSOVManualManualManualAOVAOVManualManualManualManualManualManualManualAOVAOVCheckManualManualReliefNANANANAAOVAOVAOVCheckManualCheckotes252228Maximumisolation Time~s.6060606060
ATlACHMENTAA-3.3:13~asternServiceWaterfromFanCoolerBServiceWatertoFanCoolerDLeakageTestDepressuriza-tionPenetration N.311312313Valve/~BNlee463046344656FIA-2034TZA-2011CLZC4642464612500KPI-2144CLZCNACap7444bobtionPositionalalalalalala2alalalala2ala2a2Valve~peManualManualReliefNANANANAManualManualManualNANABlindFlangeNAMOVNotes2228232826MaximumboiationTimeServiceWaterFromFanCoolerCServiceWatertoFanCoolerBLeakageTestSupplyDeadweight TesterServiceWaterToFanCoolerAServiceWatertoFanCoolerC315316317318319320464346474659FZA-2035CstmCXFlh.xtLt)
TIA-2012CLIC46284632PI-2138CLICSAT01Cap7443NA46274631PI-2142CLIC4641464512500HPZ-2136CLZCalalalalalala2alalala2ala2a2al,a2alalala2alalala1a2ManualManualReliefNANANANAManualManualNANABlindFlangeNAMOVNAManualManualNANAManualManualManualNhNA22282328262723282328SteamGenerator 321ABlowdownSteamGenerator 322BBlowdown57385752CLIC57375756CLZCalala2alala2AOVManualNAAOVManualNA18186060 I
A%I'ACHMENT AA-3.3:14~asternServiceWaterfromFanCoolerDDemineralized WatertoContainment HydrogenMonitorInstrumentation LineHydrogenMonitorInstrumentation LineContainment PressureTransmitters PT944,PT949,andPT950Penetration 323324332a332b332cValvcil~~464446484660FIA-2036CecaOt(FIA3t3atTIA-2013CLIC84188419922924CLOG7452Cap@452)923CLOC7456Capp456)PT9441819GPT9491819EPT9501819Falalalalalala2ala2alala2blb2ala2blb2ala2blb2clc2Valve~22+ManualManualReliefNANANANAAOVCheckSOVSOVNAManualNASOVNAManualNANAManualNAManualNAManualNotes22283131MaximumbolationTime~a.HydrogenMonitorInstrumentation LineMainSteamfromSteamGenerator A332d401921CLOC7448Cap(7448) 34113413A34553505A3505C35093511351335153517352136153669110271102911031PS-2092PT-468PT-469PT-469APT-482EndCapsCLICala2blb2alalalalalalalalalalalalalalalalalalalalalala2SOVNAManualNAReliefManualManualMOVManualReliefReliefReliefReliefAOVManualManualManualManualManualManualNANANANANANANh3124242424888883318 ATl'ACHMENT AA-3.3:15~SstemPenetration Valve/~BondahoiationPositionValve~TeNotesMaximumSolatioaTime~secs.MainSteamfrom402BSteamGenerator 34103412A34563504A3504C35083510351235143516352036143668110211102311025PS-2093PT-478PT-479PT-483EndcapsCLZCalalalal'alalalalalalalalalalalalalalalalala2ReliefManualManualMOVManualReliefReliefReli.efReli.efAOVManualManualManualManualManualManualNANANANANANA2424242488883318Feedwater LinetoSteamGenerator AFeedwater LinetoSteamGenerator B40340439933995X4000C40034003A4011A4099E8651CLIC39923994E3994X4000D40044012A4004A8650CLZCalalalalalalalala2alalalalalalalala2CheckManualCheckCheckManualManualManualManualNACheckManualManualCheckCheckManualManualManualNA3434341834343418Personnel Hatch1000Equipment Hatch2000NANANANAala2ala2NANANANA ATTACHMENT AA-3.3:16(2)(3)~atesThispenetration isclosedbyadouble-gasketed blindflangeonbothends.Bothflangesarenecessary forcontainment integrity purposessincethetestconnections betweenthetwogasketsforeachflangedonotmeettherequirements ofANSI-56.8.
Therefore, theinnermost gasketforeachflange(i.e.,gasketclosesttocontainment wall)providesasinglecontainment barrier.Thisvalveisnotacontainment isolation valveduetotheinstalled downstream weldedflange,butisnormallymaintained lockedclosedtoprovideadditional assurance ofcontainment integrity.
Theendofthefueltransfertubeinsidecontainment isclosedbyadouble-gasketed blindflangetopreventleakageofspentfuelpitwaterintothecontainment duringplantoperation.
Eachgasketprovidesasinglecontainment isolation barrier.Thisflangealsoservesasprotection againstleakagefromthecontainment following aloss-of-coolantaccident.
(4)(5)(6)(8)Thechargingsystemisaclosedsystemoutsidecontainment (CLOG).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished vianormalsystemoperation
(>>2235psig).Thesafetyinfection systemisaclosedsystemoutsidecontainment (CLOG).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished viainservice and/orshutdownleakagechecks.(SafetyIn)ection Pumpdischarge pressureis~1500psig)Thisvalveisnotlockedclosed~however,thevalveismaintained closedbytestingandsystemlineupprocedures andhasa"Boundary ControlTag"perPTT-23A.Thisprovidesequivalent assurance ofpropervalveposition.
Thepressureindicator onlyprovideslocalindication; therefore, asecondclosedisolation deviceisrequired(i.e.,indicator's rootvalve).However,therootvalve(12406or12407)islistedwiththeindicator, notasasecondbarrierduetothedesignoftheline.Thepressuretransmitter
assembly, byitsdesign,providesacontainment pressureboundary.
Sincethetransmitter providesdirectindication tothecontrolroom,operators wouldbeawareofitsfailure.Therefore, thetransmitter's rootvalve(s)isnormallymaintained open.(9)Thispenetration wasonlyutilizedduringinitialplantconstruction andismaintained inactive.
Sincethereisnotestconnection between5129andthethreadedcap,allobservedleakageduringtestingisappliedto5129.Therefore, theoutsidecapisnotaCIB.(10)Thecontainment spraysystemisaclosedsystemoutsidecontainment (CLOC).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished viainservice and/orshutdownleakagechecks.(Containment Spraypumpdischarge pressureis~285psig)Thisvalvereceivesacontainment isolation signalghowever,creditisnottakenforthisfunctionsincethevalveisinsidethemissilebarrieroroutsidethenecessary classbreakboundary.
Therefore, thisvalveisnotacontainment isolation valveandnotsubjectto10CFR50 ATI'ACHMENT AA-3.3:17AppendixJtestingnorTechnical Specification 3.6.3.isolation signalonlyenhancescontainment isolation.
Thecontainment (12)(13)Bothcontainment spraytestlineshavealockedclosedmanualvalvethatleadstoacommonlinewithtwonormallyclosedmanualvalves.Thevalvesinthiscommonlinemaybeopenedduringapumptestsincenecessary containment isolation ismaintained (seeSafetyEvaluation NSL-OOOO-SE015).
Thetestlineandrootvalvesforthepressureindicators canbeopenedduringtestingoftheCSpumpssincemanualvalves868A/Bareclosed,thusproviding thenecessary containment boundaryfortheshortdurationofthetest.(14)Thesecondisolation barrier(CLOC)is.providedbythevolumecontroltankandconnecting pipingperletterfromD.D.DiIanni,NRC,toR.W.Kober,RG&E,datedJanuary30,1987.Thisbarrierisnotrequiredtobetested.(15)(16)(17)(18)(19)(2o)(21)(22)Onlyoneisolation barrierisprovidedsincetherearetwoEventVcheckvalvesintheSIcoldlegs,andtwocheckvalvesandanormallyclosedmotor-operated valveintheSIhotlegs.Thisconfiguration wasacceptedbytheNRCduringtheSEP(NUREG-0821, Section4.22.2).Theresidualheatremovallinesforthispenetration areaclosedloopoutsidecontainment (CLOG).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished viainservice and/orshutdownleakagechecks.(Residual HeatRemovalpumpdischarge pressureis~175psig)AppendixJcontainment leakagetestingisnotrequiredperletterfromD.M.Crutchfield, NRC,toJ.E.Maler,RGGE,datedMay6,1981.TheMainSteam,MainFeedwater, StandbyAuxiliary Feedwater andS/GBlowdownpenetrations takecreditforthesteamgenerator tubesandshellasaclosedsysteminsidecontainment (CLIC).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished vianormalpoweroperation (750psig).Theisolation valvesoutsidecontainment forthesepenetrations donotrequireAppendixJtesting.Thecomponent coolingwaterlinesinsidecontainment forthispenetration areaclosedloopinsidecontainment (CLIC).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished viainservice and/orshutdownleakagechecks.(Component CoolingWaterpumpdischarge pressureis~85psig)Operations isinstructed tomanuallycloseAOV745following acontainment isolation signaltoprovideadditional redundancy.
Sumplinesareinoperation andfilledwithfluidfollowing anaccident; therefore, 10CFR50,AppendixJleakagetestingisnotrequiredforthispenetration.
SeeletterfromD.M.Crutchfield, NRC,toJ.E.Maier,RGM,datedMay6,1981.Thismanualvalveissub)ected toanannualhydrostatic leakagetest(>60psig)andisnotsub)ectto10CFR50,AppendixJleakagetesting.SeeNUREG-0821, Section4.22.3.
ATI'ACHMENT AA-3.3:18(23)(24)(25)TheServiceWaterSystemoperatesatahigherpressure(80psig)thanthecontainment accidentpressure(60psig)andismissileprotected insidecontainment.
Therefore, thismanualvalveisusedforflowcontrolonlyandisnotsubjectto10CFR50,AppendixJleakagetesting.SeeNUREG-0821, Section4.22.3.hThisvalvedoesnotreceiveanautomatic containment isolation signalbutisnormallyopenatpowersinceiteitherimprovesthereliability ofanessential standbysystemorisrequiredforpoweroperation.
However,thisvalvecaneitherbeclosedfromthecontrolroomorlocallywhenrequired.
Theflangesandassociated doublesealsprovidecontainment isolation andensurethatcontainment integrity ismaintained forallmodesofoperation abovecoldshutdown.
When'theflangesareremovedduringcoldshutdownconditions, containment integrity isprovidedbythevalve.Thisvalveisnotrequiredtobooperableabovecoldshutdownanddoesnotrequire10CFR50,AppendixJleakagetesting,noramaximumisolation time.(26)(29)(30)Motor<<Operated Valves7443and7444arepoweredfromnon-safety-related Bus15.However,thisisacceptable sincethevalvesaremaintained closedatpowerandareinserieswithablindflange.Inaddition, operators wouldbeawareofalossofBus15byalossofcontrolroomindication forthesetwovalves(SafetyEvaluation NSL-OOOO-SE021).
Thispenetration isdecommissioned andweldedshut.Theservicewatersystempipinginsidecontainment forthispenetration isaclosedsysteminsidecontainment (CLIC).Verification ofthisclosedsystemasacontainment isolation boundaryisaccomplished viainservice and/orshutdownleakagechecks.(ServiceWaterPumpdischarge pressureis~80psig)Thisendcapisusedforflowbalancing.
However,itcannotbeopenedabovecoldshutdownwithoutfirstperforming asafetyevaluation.
Thisvalvewillnolongerbeclassified asaCIVfollowing NRCapprovaloftheAmendment RequesttoremovethelistingofCIVsfromTechnical Specifications sinceanotherboundaryhasbeenidentified.
However,intheinterim,thevalvewillcontinuetobeidentified andtestedasaCIVconsistent withTechnical Specifications.
Thisnoteappliestovalves750A,750B,851Aand851B.(31)(32)(33)(34)Acceptable isolation capability isprovidedfortheseinstrument linesbytwoisolation boundaries outsidecontainment.
Oneoftheboundaries isaSeismicCategoryIclosedsystemwhichissubjecttoTypeCleakagetestingunder10CFR50AppendixJ.Thereisnosecondcontainment barrierforthisbranchline.Thisisaddressed bySafetyEvaluation NSL-OOOO-SE015.
TheseendcapsincludethosefoundonthesensinglinesforPS-2092,PT-468,PT-469,PT-469A,andPT-482(Penetration 401)andPS-2093,PT-479,andPT-483(Penetration 402).Thischeckvalvecanbeopenwhencontainment isolation isrequiredinordertoprovidenecessary feedwater orauxiliary feedwater tothesteam ATI'ACHMENT AA-3.3:19(35)generators.
Thecheckvalvewillcloseoncefeedwater isisolatedtotheaffectedsteamgenerator (NUREG-0821, Section4.22.1).AOV959cannotbetestedto10CFR50AppendixJrequirements sincetherearenoavailable testconnections.
Therefore, thefusesforAOV959areremovedwithboundarycontroltagsinplacetomaintainthisvalveclosed.Manualvalve957isalsomaintained closedtoprovideadditional assurance ofcontainment lntegrltyy however,valve957isnotacontainment isolation valvesub)ecttoTechnical Specification 3.6.3.(36)AOV371isacontainment isolation valveforbothpenetrations illand112.(37)TheTechnical Specifications currently identifya60secondmaximumisolation signalforthisvalve(745,749Aand749B).However,thereisnoautomatic containment isolation signaltothisvalveandnonerequired.
ATTACHMENT ETableofTechnical Specification Changes Pg Attachment P.Page1of3ChangesTechnical Specification ChangesEffectRemovedreference toTable3.6-1fromTechnical Specifications 3-.6.3.1, 4.4.5.1,and4.4.6.2.Addedstatement toBasesforTechnical Specification 3.6thatcontainment isolation boundaries arelistedinProcedure A-3.3.RemovedTable3.6-1fromTechnical Specifications andplacedinformation inProcedure A-3.3.Removeddefinition ofleakageinoperability fromTechnical Specification 3.6.3.1.Addedstatement relatedtointermittent operation ofboundaries tobothTechnical Specification 3.6.1andthebases.Removednoteassociated withTechnical Specification 3.6.5.Addeddefinition of"isolation boundary" toBasesforTechnical Specification 3.6.Updatedreference listcontained inBasesforTechnical Specifications 3.6,3.8,and4.4.Revisedactionstatement ofTechnical Specification 3.8.1sectiona.Notechnical change.Specifications arenowconsistent withGenericLetter91-08.Valvelistingremainsinalicenseecontrolled documentunderTechnical Specification changecontrols.
Definition isfoundinTechnical Specification 4.4.2.2.Eliminated redundant discussion ofleakageacceptance criteria.
Notechnical change.Specification nowconsistent withGenericletter91-08.Mini-purge valveshavebeeninstalled sospecification isconsidered effective.
Notechnical change.Notechnical change.Clarification of"isolation boundary" providesconsistency withUFSARTable6.2-15.Notechnical change.Clarification only.Specification nowconsistent withStandardTechnical Specifications.
IIlMf1~Iv:IIq"('~~ecIIa~I~*
Attachment EPage2of3'ChangesTechnical Specification ChangesEffect10.12.'13.14.15.'6.'Revisedactionstatement
.ofTechnical
.Specification 3.8.3.Revisedbases-for"Technical Specification 3.8.Added"Pt"andnecessary definitions toTechnical Specification 4.4.1.4sectiona.Addedtothedefinition of"Lt"inTechnical Specification 4.4.1.4sectionb.Addeddefinition of"Pa"and"Lam"toTechnical Specification 4.4.1.4.Addedsteamgenerator inspection/maintenance penetration toTechnical Specification 4.4.1.5sectiona(ii).RevisedfirstlineofTechnical Specification 4.4.1.5,sectiona(ii).Revisedacceptance criteriaprovidedinTechnical Specification 4.4.2.2No.,technical change.Specification nowspecifically addresses affectedcontainment penetrations.
No=technical change.Basesarenowconsistent withStandardTechnical Specifications andsupportchangesto3.8.1sectionaand3.8.3.Additionof"Pt"definition providesclarification oftestingtypeconsistent with10CFR50,AppendixJ.Alltermsin4.4.1..4, sectionaare'nowfullydefined.Notechnical change.Additionof"Lt"definition
.provides clarification consistent with10CFR50,AppendixJ.Alltermsin4.4.1.4,sectionbarenowfullydefined.Notechnical change.Additionof"Pa"and"Lam"providesclarification consistent with10CFR50,AppendixJ.Alltermsin4.4.1.4nowfullydefined.Notechnical change.Additionofthispenetration providestestingcriteriasimilartotheequipment hatchandcontainment'ir locks.Minorclarification only.Notechnical change.Clarification only.Notechnical change.
t>>I'i~'Iyg'amL44-Attachment EPage3of3ChangesTechnical Specification ChangesEffect17.18.19.20.21.22.Replaced"isolation valve"with"isolation boundary" inTechnical Specification 4.4.2.3andtheBasesforsection4.4.Removednotesassociated withTechnical Specification 4.4.2.4sectiona.Also,deletedreference tosectiond.Addedsteamgenerator inspection/maintenance penetration toTechnical Specification 4.4.2.4sectionb.RemovedTechnical Specification 4.4.2.4sectiondandassociated note.Revisedstatement forTechnical Specification 4.4.5.1.Revisedstatement forTechnical Specification 4.4.6.2.Minorclarification only.Specification andbasesarenowconsistent withtherevisedTechnical Specification 3.6.3.Mini-purge valveshavebeeninstalled sospecification isconsidered effective.
SectiondwillberemovedfromTechnical Specifications withthisamendment.
Additionofthispenetration providestestingcriteriasimilartotheequipment hatchandcontainment airlocks.Blindflangeshavebeeninstalled sospecification isconsidered effective.
Notechnical change.Specification nowconsistent withStandardTechnical Specifications.
Specification nowconsistent withStandardTechnical Specifications.
fII~i4~VrI~%ltIIIp~4 3.6Containment SstemAlicabilit Appliestothe'integrity ofreactorcontainment.
Todefinetheoperating statusofthereactorcontainment forplantoperation.
Secification:
3.6.1Containment Interita~Exceptasallowedby3.6.3,containment integrity shallnotbeviolatedunlessthereactorisinthecoldshutdowncondition.pg;"',pl'ossa)yi1je's,.';.':~~'imp'he
4'col'3.'.n4 svx8,'5x'v8:i<,::::const',03+!~
b.The"containment, integrity shallnotbeviolatedwhenthereactorvesselheadisremovedunlesstheboronconcentration isgreaterthan2000ppm.c~Positivereactivity changesshallnotbemadebyroddrivemotionorborondilutionwheneverthecontainment integrity isnotintactunlesstheboronconcentration isgreaterthan2000ppm.3.6.2,InternalPressureIftheinternalpressureexceeds1psigortheinternalvacuumexceeds2.0psig,thecondition shallbecorrected within24hoursorthereactorrenderedsubcritical.
Amendment No.3.6-1Proposed l
3.6.3Containment Isolation
-Vakvee.:4'oGFdai:i~e'8 3.6.3.1Withepe~nd~!afjccint'ainus',:;i:,:@platinum'houndarg';::a ppe~~SIe,;::;..';for one..:.ex
'::,miieIj'.co%tegn'meie$
~j4rii:,:;-::,:,8
',::,-:::,:h'
-..6-::ye~~keFOPERABX:8 statuswithin4hours,orb.c~Isolateeachaffectedpenetration within4hoursbyuseofatleastonedeactivated automatic valvesecuredintheisolation
position, on,::-:,':ll:::c'las'el n'a'jn'u'a~j@Lue~",;!or'.:g.;,:;;:Jjgggg',::;'g'jl'ap~g'e."
orde.Beinatleasthotshutdownwithinthenext6hoursandin-coldshutdownwithin-thefollowing 30,hours,.
3.6.4Combustible GasControl3.6.4.1Whenthereactoriscritical, atleasttwoindependent containment hydrogenmonitorsshallbeoperable.
OneofthemonitorsmaybethePostAccidentSamplingSystem.3.6.4.2Withonlyonehydrogenmonitoroperable, restoreasecondmonitortooperablestatuswithin30daysorbeinatleasthotshutdownwithinthenext6hours.3.6.4.3Withnohydrogenmonitorsoperable, restoreatleastonemonitortooperablestatuswithin72hoursorbeatleasthotshutdownwithin'the next6hours.3.6e5Containment Mini-PureWheneverthecontainment integrity isrequired, emphasiswillbeplacedonlimitingallpurgingandventingtimestoas,lowasachievable.
Themini-purge isolation valveswillremainclosedtothemaximumextentpracticable butmaybeopenforpressurecontrol,forALARA,forrespirable airqualityconsiderations forpersonnel entry,forsurveillance teststhatmayrequirethevalvetobeopenorothersafetyrelatedreasons.Amendment No.P,gP3.6-2Proposed
'IIh'TC.1ll.a4'II+'L'+40fll'1$oi'.~'~'"~,~~r'lf.<IIYIg~IlI%J6~+44lllhFIhjp\+<~$
Basis:Thereactorcoolantsystemconditions ofcoldshutdownassurethat'osteamwillbeformedandhence-there-wouldbenopressurebuildupinthecontainment ifthereactorcoolantsystemruptures.
'he-shutdown"margins areselectedbasedonthetypeofactivities thatarebeingcarriedout.The(2000ppm)boronconcentration providesshutdownmarginwhichprecludes criticality underanycircumstances.
Whenthereactorheadisnottoberemoved,acoldshutdownmarginof14~k/kprecludes criticality inanyoccurrence.
Regarding internalpressurelimitations, thecontainment designpressureof60psigwouldnotbeexceedediftheinternalpressurebeforeamajorsteambreakaccidentwereasmuchas1psig."Thecontainment isdesignedtowithstand aninternalvacuumof2.5psig.~~~The2.0psigvacuumisspecified asanoperating limittoavoidanydifficulties withmotorcooling.Amendment No.3.6-3Proposed Jp,>4'cactirI.>Af>>r~IIr)
References:
(1)Westinghouse
Analysis, "ReportfortheBASTConcentration Reduction forR.E.Ginna",August1985Pj~i~ip55'Xt;pppg~~N~.
8:I'i'i""':':fioiii:":
R:N"':>'Kobi""""'RGB'"'
(2)UFSAR-Section6.2.l.4]f3'ggj~GPSA'Rq:.'::.-,,
e8'actin'n;::~6,".!2~~4:
3.6-4Proposed
'it~II,h~A
'Ie\gal b.c~a:::~ii-:::;:,-p Et'::,:~:~':-pic-::'::;i:,:.:!8
!'::.:::,:,KiihogaSi~cs!:,zguudovnj:::,ipux'ga'<ll,a:i'iiiiiimLii il:;,,pii~7ja yves'l~v8.:".i Radiation levelsinthecontainment shallbemonitored continuously.
Coresubcritical neutronfluxshallbecontinuously monitored byatleasttwosourcerangeneutronmonitors, eachwithcontinuous visualindication inthecontrolroomandonewithaudibleindication inthecontainment andcontrolroomavailable whenevercoregeometryisbeingchanged.WhencoregeometryisnotbeingchangedatAmendment No.g,g.g3.8-1Proposed I~~
3.8.'23.8.3flange.Ifthiscondition isnotmet,alloperations involving movementoffuelorcontrolrodsinthereactorvesselshallbesuspended.
Ifanyofthespecified limitingconditions forrefueling.
isnotmet,refueling ofthereactorshallcease;workshallbeinitiated tocorrecttheviolatedconditions sothatthespecified limitsaremet;nooperations whichmayincreasethereactivity ofthecoreshallbemade.Iftheconditions of3.8.l.darenotmet,theninadditiontotherequirements of3.8.2,pi~MMKCC44Xw.'w'i&+5 55e~sh~g...6own~pqx'cge';:;and::ljqi,:ni:::,:.,'.p'urge;;..:penetiat,,:io'ns within4hours.Basis:Theequipment andgeneralprocedures tobeutilizedduringrefueling arediscussed inthePFSAR.Detailedinstructions, theabovespecified precautions, andthedesignofthefuelhandlingequipment incorporating built-ininterlocks andsafetyfeatures, provideassurance thatnoincidentcouldoccurduringtherefueling operations thatwouldresultinahazard3.8-3Proposed Ir~Ikya~/rL~*ad4"~*a~Id~QggCC providedontheliftinghoisttopreventmovementofmorethanonefuelassemblyatatime.The.spentfueltransfer.
mechanism canaccommodate onlyonefuelassemblyatatime.Inaddition, interlocks ontheauxiliary buildingcranewillpreventthetrolleyfrombeingmovedoverstoredrackscontaining spentfuel.Theoperability requirements forresidualheatremovalloopswillensureadequateheatremovalwhileintherefueling mode.Therequirement for23feetofwaterabovethereactorvesselflangewhilehandlingfuelandfuelcomponents incontainment isconsistent withtheassumptions ofthefuelhandlingaccidentanalysis.
Thereanalysis~~~~
forafuelhandlingaccidentinside.containment establishes acceptable offsitelimitingdosesfollowing ruptureofallrodsofanassemblyoperatedatpeakpower.Nocreditistakenforcontainment isolation oreffluentfiltration priortorelease.Requiring closureofpenetrations
."--h'1!hlly.
-,-,,16"-,':is%res:::::":"::::::::,:4:,'::::ilia:".::,,::ni::::.::;
ilia:::t"-Ph-::ilia%i!!ah:Out81'd'eimahtmCiajihere" establishes additional marginforthefuelhandlingaccidentandestablishes aseismicenvelopetoprotect,,:::;::s.,ii"i:::-':k:::"'\l!":-:i:,".I
~i!i"::-:,'-:i'!]i refueling Wax:.sole!toin~aI,jttTi'ie'j:,j efngaritioen's'Cmaliiibe:':
ii--i'---,::-s,,:::,
e::.,:-:.::~;-::::::-g-;pd':-
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-:"""-:-,-:,'i~
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onknai~t,:::;::~
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Zi!prcnu'Baiei';:,::a::;,:::;:::temp Origay::::::::::::y,
~t'-:li,,:,--,-,e:;:--
.,",:-,:::ii!)i!,:.'!imari.,
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T:-":.--'!!4 il::-,Iii---J,.pc,veLentgl Amendment No.g3.8-5Proposed IIQJ4'II,4>AtIF References (1)'2)(3)Re~~,':,Ug@Wg4@ct',::j:ovals>gbYg~.':::.:4~and;",:;;9.'.g.~@-:.'8 loadTransient SafetyReport,Cycle14-:!UFBAR::","!
SPP&Tpfli'i'5!~gi'3!'i!~3:
3.8-6Proposed 14,4'I,lI4*tfiIIfI\
AccetanceCriteria~"..s.-~~~"~!.-g.'i!j,;."'i',',,
',";:P'S,,"%',8,
'3l,S,",'ll!RS!ii,,
!il':C:Ollct'31lhlSll
.,:"!~!'VB'8'88' pgp/ab.Ltshallbedetermined asLt=La~>>~VMeh(~egup~f~Q QU~81~8%2!..::p'8x::,c5'At,::::v8'xgÃit~!$
.ex.'::>'Aay8~~eajI.A9'~.';::ra~e.ski'=:,-".:-,pi::~assur'e:
4a~~j~TestFreuenca~Asetofthreeintegrated leakratetestsshallbeperformed atapproximately equalintervals duringeach10-yearserviceperiod.Thethirdtestofeachsetshallbeconducted inthefinalyearofthe10-yearserviceperiodoroneyearbeforeorafterthefinalyearofthe10-yearserviceperiodprovided:
theintervalbetweenanytwoTypeAtestsdoesnotexceedfouryears.~~liefollowing
-eaeP;ea'c8 in-service inspection, thecontainment airlockj>"..:,,'gath~ePj>:"':.>jpy5jj'ii) y::e.:ne:r,:a.:t;ale"':::5;-:;:gg;:,;,:,i'.,:",.n:s,.p,:;e~c':,
':!i~a";,'n'>jjm'::a':;:-'i..-':n"t.,':i'nYaiiic.',e l~eaktestedpriorWoreturning theplanttooperation, andanyrepair,replacement, ormodification ofacontainment barrierresulting fromtheinservice inspections shallbefollowedby~theappropriate leakagetest.44-4Proposed IIISIIj4L0I
'b.Thelocalleakagerateshallbemeasuredforeachofthefollowing components:
~~ll~ill.Containment.-penetrations that.employ.resilient seals,gaskets,orsealantcompounds, pipingpenetrations withexpansion bellowsandelectrical penetrations withflexiblemetalsealassemblies.
Airlockandequipment doorseals.Fueltransfertube.iv>>Isolation valvesonthetestablefluidsystemsv~linespenetrating thecontainment.
Othercontainment components, whichrequireleakrepairinordertomeettheacceptance criterion foranyintegrated leakageratetest.4.4.2.2AccetanceCriterion p,CwA'Mt~!uxsaN>ss>>spg>>>>
wAl~gt&san,sas&~dANx>>!>>>>s>>esi a@a!p,i'noperab'li
',i,::".':if rlo!mj!!!a",;i!!ieaki'gal!i~>>>scan'dgoinC~>>iwhe'n,,:gha dem'oniti'."a'tk'd~fieaga'j~e",<or!ira!L:;::sanglijijb'oun,dayr:
oai~)ga'umui rCa'iy'e4.4.2>>3Corrective Actiona~Ifatanytimeitisdetermined thatthetotalleakagefromallpenetrations andisolation valvespcun'd'ariaS exceeds0.60La,repairsshallbeinitiated immediately.
4.4-6Proposed I,1IalFJ+
b.Ifrepairsarenotcompleted andconformance totheacceptance criterion of4.4.2.2is-notdemonstrated c~within48hours,thereactorshallbeshutdownanddepressurized untilrepairsareeffectedandthelocalleakagemeetstheacceptance criterion.
Ifitisdetermined thattheleakagethroughamini-purge supplyandexhaustlineisgreaterthan0.05Laanengineering evaluation shallbeperformed andplansforcorrective actiondeveloped.
4.4.2.4.TestFreuenca~Exceptasspecified inb.-,and.;)c.,
individual penetrations andcontainment isolation valvesshallbetestedduringeachreactorshutdownforrefueling, orotherconvenient intervals, butinnocaseatintervals greaterthantwoyears.-Xab.Thecontainment equipment hatch,fueltransferIpiiitdatx'oa, andshutdownpurgesystemflangesshallbetestedateachrefueling shutdownoraftereachuse,ifthatbesooner.Amendment No.4.4-7Proposed 1II)I c~Thecontainment airlocksshallbetestedatintervals ofnomorethansixmonthsby.pressurizing the-.space'=between theair.lockdoors.Znaddition, following openingoftheairlockdoorduringtheinterval, atestshallbeperformed bypressurizing betweenthedualsealsofeachdooropened,within48hoursoftheopening,unlessthereactorwasinthecoldshutdowncondition atthetimeoftheopeningorhasbeensubsequently broughttothecoldshutdowncondition.
Atestshallalsobeperformed bypressurizing betweenthedualsealsofeachdoorwithin48hoursofleavingthecoldshutdowncondition, unlessthedoorshavenotbeenopensincethelasttestperformed eitherbypressurizing thespacebetweentheairlockdoorsorbypressurizing betweenthedualdoorseals.Amendment No.4.4-8Proposed
\P,I~!
Amendment No.4.4-8Proposed IO'A'h thetendoncontaining 6brokenwires)shallbeinspected.
Theacceptedcriterion thenshallbenomorethan4brokenwiresinanyoftheadditional 4tendons.Ifthiscriterion isnot-satisfied, allofthe.tendonsshallbeinspected andifmorethan54ofthetotalwiresarebroken;-.the reactorshallbeshut-down and.depressurized.
4.4.4.2Pre-Stress Confirmation Testa~b.Lift-offtestsshallbeperformed onthe14tendonsidentifiedin4.4.4.1aabove,attheintervalsspecified in4.4.4.1b.
Iftheaveragestressinthe14tendonscheckedislessthan144,000psi(604ofultimatestress),alltendonsshallbecheckedforstressandretensioned, ifnecessary, toastressof144,000psi.Beforereseating atendon,additional stress(64)shallbeimposedtoverifytheabilityofthetendontosustaintheaddedstressappliedduringaccidentconditions.
4.4.5Containment Isolation Valves4.4.5.14.4.6Eachcontiiame'ntg>:isolation valveb"I6::,i(i:i::1gj.i accordance withtheGinnaStationPumpandaValveTestprogramsubmitted inaccordance with10CFR50.55a.Containment Isolation Resonse4.4.6.14.4.6.2Eachcontainment isolation instrumentation channelshallbedemonstrated OPERABLEbytheperformance oftheCHANNELCHECK,CHANNELCALIBRATION, andCHANNELFUNCTIONAL TESToperations fortheMODESand*atthefrequencies showninTable4.1-1.ThepeSp'Ofi's'@~time ofpi'ehj~econtainment isolation valve,',shallbedemonstrated tobewithinCheggtslimitatleastonceper18months.Theresponsetimeincludesonlythevalveva'1Vee'~+giehiithejaa'f aVy'::;";aaa,:
/Amendment No.4.4-11Proposed
'iCI~k TheSpecification alsoallowsforpossibledeterioration ofthe.leakageratebetweentests,byrequiring thatthetotalmeasuredleakagerate-be-only 75<ofthe.maximumallowable leakage.rate.--Thedurationandmethodsfortheintegrated leakageratetestestablished byANSIN45.4-1972 provideaminimumlevelofaccuracyandallowfordailycyclicvariation intemperature andthermalradiation.
Thefrequency oftheintegrated leakageratetestiskeyedtotherefueling scheduleforth'ereactor,becausethesetestscanbestbeperformed duringrefueling shutdowns.
Refueling shutdowns arescheduled atapproximately oneyearintervals.
Thespecified frequency ofintegrated leakage=rate tests.is,basedonthreemajorconsiderations.
Firstisthelowprobability ofleaksintheliner,becauseof(a)theuseofweldchannelstotesttheleaktightness oftheweldsduringerection, (b)conformance ofthecompletecontainment toaO.l>perdayleakrateat60psigduringpreoperational testing,and(c)absenceofanysignificant stressesinthelinerduringreactoroperation.
Secondisthemorefrequenttesting,atthefullaccidentpressure, ofthoseportionsofthecontainment envelopethataremostlikelytodevelopleaksduringreactoroperation (penetrations andisolation valves)andthelowvalue(0.60La)ofthetotalleakagethatisspecified asacceptable Thirdisthetendonstresssurveillance program,whichprovidesassurance thananimportant partofthestructural integrity ofthecontainment ismaintained.
4.4-13Proposed
.paII'L0$rt Thebasisforspecification ofatotalleakageof0.60Lafrompenetrations andisolation
~ee~SFugŽdaige8 isthatonlyaportion'of'theallowable integrated leakage.rate-shouldbe-from.thosesourcesinordertoprovideassurance thattheintegrated leakageratewouldremainwithinthespecified limitsduringtheintervals betweenintegrated leakageratetests.Becausemostleakageduringanintegrated leakratetestoccursthoughpenetrations andisolation valves,andbecauseformostpenetrations andisolation valvesasmallerleakageratewouldresultfromanintegrated leaktestthanfromalocaltest,adequateassurance ofmaintaining the"integrated leakageratewithinthespecified limitsisprovided.
ThelimitingleakageratesfromtheRecirculation HeatRemovalSystemsarejudgement valuesbased,primarily onassuring.that.thecomponents couldoperatewithoutmechanical failureforaperiodontheorderof200daysafteradesignbasisaccident.
Thetest4.4-14Proposed V'JtCV~p Thepre-stress confirmation testprovidesadirectmeasureoftheload-carrying capability ofthetendon.Ifthesurveillance programindicates byextensive wirebreakageortendonstressrelationthatthepre-stressing tendonsarenotbehavingasexpected, thesituation willbeevaluated immediately.
Thespecified acceptance criteriaaresuchastoalertattention tothesituation wellbeforethetendonload-carrying capability woulddeteriorate toapointthatfailureduringadesignbasisaccidentmightbepossible.
Thusthecauseoftheincipient deterioration couldbeevaluated andcorrective actionstudiedwithoutneedtoshut.downthereactor.Thecontainment isprovidedwithtwo'readilyremovable tendonsthatmightbeusefultosuchastudy.Inaddition, thereare40tendons,eachcontaining aremovable wirewhichwillbeusedtomonitorforpossiblecorrosion effects.Operability ofthecontainment isolation vakvee~hnund'ix'fi'8 ensuresthatthecontainment atmosphere willbeisolatedfromtheoutsideenvironment intheeventofareleaseofradioactive materialtothecontainment atmosphere orpressurization ofthecontainment.
Performance ofcyclingtestsandverification ofisolation timescoverebyeumpanVaveTes5'rogram.
CompiancewiAppendixJto10CFR50isaddressed underlocalleaktestingrequirements.
References:
(2)(4)(5)(6)FSARPage5.1.2-28(7)North-American-Rockwell Report550-x-32, Reliability
Handbook, February1963.Autonetics (8)FSARPage5.1-284.4-17Proposed gQ(ftIfCv1e.)t'II~~e)~%gbqggIQ

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