ML17037C433

Nine Mile Point, Unit 1 - Letter Regarding Surveillance Requirements and Limiting Conditions for Operations and Requesting an Application for Amendment to the Operating License That Will Change the Technical Specifications

ML17037C433
Person / Time
Site:	Nine Mile Point
Issue date:	08/08/1977
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G K Niagara Mohawk Power Corp
References
Download: ML17037C433 (20)

Text

=AUG81977DocketNo.50-220NiagaramohawkPowerCorporation ATTN:Nr.GeraldK.RhodeVicePresident

-Engineering 300ErieBoulevard WestSyracuse, NewYork13202Gentlemen:

RE:NINENILEPOINTNUCLEARSTATIOflUNITNO.1Distribution DocketORB83CParrishGLearSNowickiDVerrelli LocalPDRNRCPDRAttorney, OELDOI&E(3)DEisenhut TBAbernathy NRBuchanan ACRS(16)Inthepastseveralyears,asignificant numberofreliefvalvesandsafety-relief valveswerefoundtobeinoperable atBWRreactorfacili-ties.Thesevalveswereinstalled intheReactorCoolantSystemand/orAutomatic Depressurization System.Severalprogramshavebeendeveloped toreducetheincidence ofthesevalvefailures; however,additional failurescontinuetooccur.Consequently, wehaveconcluded thatchangestotheSurveillance Require-mentsandLimitingConditions forOperations forallBHR'sareneededtoprovideadditional assurance ofreliefvalveandsafety-relief valveoperabflity andreliability.

Therefore, werequestthatyoumodifyyoursurveillance testingprogramthroughtheadoptionoftheprogramcontained inthemodeltechnical specifications wehaveprepared.

Theelementsofthisprograminclude:Eachremotlyoperatedreliefvalveandsafety-relief valvefntheReactorCoolantSystemandAutomatic Depressurizatfon Systemwillbetestedonavariablefrequency schedulerelatedtodemonstrated reliability andoperability.

Thetestingintervalisbasedonthenumberofvalvefailuresduringtherequiredtestinterval.

Facilities withreliablevalveswillprogresstoalongertestintervalwhilethosewithvalvefailureswillprogresstoashortertestinterval.

Thisconceptshouldresultinthemaintenance ofamoreuniformlevelofreliability forthisequipment thanpreviously obtained.

2.Theincreased surveillance programwillbecomeeffective onHarch1,19T9.Noincreaseinvalve,testingisrequiredbeforethatdate.Theinitialtestinginterval.

oftheincreased surveillance programwillbebasedonthenumberofremotelyoperatedreliefvalvesandsafety-relief valvesfoundinoperable intheprevious18monthspP'September 1,1977toMarch1,1979).Thisleadtimewillpermittheresolution oftheHarkISafety-Relief ValveLoadsandDFPICE~SUANAMEWDATE~NRCFORM'318(9.76)NRCM02404V8OOVEANMENT PAINTIN4OFFICER1024420624 4Fhhr1*NI(I/'('I~fI)CItAIhrortSI*.~rl1lfESIih"11('",fhh"Ih(7.),rh,firIh,INN,h(It~Nttr r~pNiagaraHohawkPowerCorporation p,UG8197)timeissufficient topermitthedevelopment andimplementation ofimprovedsafetyandsafety-relfef valvemaintenance procedures and'othercorrective actionspriortoimplementing thetestprogram.3.Thereliefand/orsafety-relief valvelinerestraints inthetoruswillbeexaminedpriortoinitiating thetestprogramandatleastonceeachfuelcycle(f.e.,each18months)toverifycontinued structural integrity.

Werequestthatyousubmitwithin30daysfromyourreceiptofthis'letter,anapplication foramendment toyourlicensethatwillchangeyourtechnical specifications tobeinconformance wfththerequirements oftheenclosedmodeltechnical specifications andassociated'bases.

Intheeventyoushoulddesirefurtherdfscussion ofthismatter,pleasecontactus.Sincerely, OriginalsignedbV

Enclosure:

ModelTechnical Specifications GeorgeLear,ChiefOperating ReactorsBranch83DivisionofOperating ReactorsCC:ArvinE.Upton,EsquireLeBoeuf,Lamb,Lefby5NacRae1757NStreet,H.W.Washington, D.C.20036AnthonyZ.Rofsman,EsquireRofsman,KesslerandCashdan102515thStreet,N.H.5thFloorWashington, D.C.20005Nr.EugeneG.Saloga,Applicant Coordinator

.,NineNilePointEnergyInformation CenterP.0.Box81Lycoming, Nes(York13093OFFICS~SU/NAME&DATE~ORB3CParrish8/1/77ORBk3SNowickjf8/)/77ORBii3jDV~rlI8//77,ORB83GLearRS(S77'RCFORM318(9-76)NRCM0240AU,'0,OOVSANMSNT FIIINTINO OFFICS<ISTS02~24

<<FIF~r'F<I"I1I1<~I~k~rlrF<k<<<l<<'Ih<IIYll<<'tj'l~f'1.,Fkrl<<'.~W REACTORCOOLANTSYSTEM3/4.4.2SAFETYVALVESLIMITINGCONDITION FOROPERATION 3.4.2Atleastthefollowing reactorcoolantsystemcodesafetyvalvesandsafety-relief valvesshallbeoperablewithliftsettingswithin+1%oftheindicated pressures.

(2)*Safetyvalves9(1240)psig(3)Safety-relief valves9(1100)psig(3)Safety-relief valves9(1090)psig(3)Safety-relief valves9(1080)psigAPPLICABILITY:

WithAverageCoolantTemperature

>212'FortheModeSwitchinRun,orStartup/Hot Standby.ACTION:Withoneormorereactorcoolantsystemcodesafetyvalve(s)orasafety-relief valve(s)inoperable eitherrestorethevalve(s)tooperablestatuswithin15minutesorbe.shutdownwithin12hoursandreduceAverageCoolantTemperature to<212'Fwithinthe next24hours..SURVEILLANCE REUIREMENTS 4.4.2.1a.Inadditiontotheapplicable ASMEBoilerandPressureVesselCode,SectionXIrequirements, eachsafety-relief valveshallbedemonstrated operable:

Atleastonceper24hours,byverifying bellowsintegrity throughinstrument indication.

b.UntilMarch1,1979,atleastonceper18monthsby:1.Manuallyopeningeachremotelyoperated.safety-relief valvewiththereactoratorbelow5%ratedpowerandatnominaloperating

pressure, andverifying thateither:a.Theturbinebypassvalve(s)indicateacompensating valvemovement, orb.Thereactorcoolantsystempressuredecreases byanamountequivalent tothevalvepressurerelieving capacityforthetestconditions.

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REACTORCOOLANTSYSTEMSURVEILLANCE REUIREMENTS (Continued) 2.Conducting avisualinspection ofthesafety-relief valvelinerestraints inthetorustoverifystructural integrity forcontinued operation.

c.AfterMarch1,1979,byperformance ofthefollowing testprogram:1.Manuallyopeningeachremotelyoperatedsafety-relief valveinaccordance withthetestscheduleofTable4.4-10withthereactoratorbelow5Xratedpowerandasteamatnominaloperating pressureandverifying thateither:a.Theturbinebypassvalve(s)indicateacompensating valvemovement, orb.Thereactorcoolantsystempressuredecreases byanamountequivalent tothevalvepressurerelieving capacityforthetestconditions.

2.TheinitialNextRequiredTestIntervalofTable4.4-10shallbedetermined bythenumberofremotelyoperatedreliefandsafety-relief valvesfoundinoperable fromSeptember 1,1977toMarch1,1979.3.TheinitialvalvetestsofTable4.4-10shallbecompleted by,theearlierof:a.Thecompletion ofthenextrefueling outageoccurring afterMarch1,1979,orb.ThetimeperioddefinedbyMarch1,1979plustheinitialtestinterval, determined above.4.Atleastonceper18months,byconducting avisualinspection ofthesafety-relief valvelinerestraints inthetorustoverifystructural integrity forcontinued operation.

4.4.2.2Eachsafetyvalveandthesafetyvalvefunctionofeachsafety-reliefvalveshallbedemonstrated operablepertherequirements oftheASMEBoilerandPressureVesselCode()EditionandAddendathrough().V

TABLE4.4-10REHOTELYOPERATEDRELIEFANDSAFETY-RELIEF VALVETESTSCHEDULENUHBEROFREHOTELYOPERATEDRELIEFANDSAFETY-RELIEF VALVESFOUNDINOPERABLE DURINGTESTINGORTESTINTERVAL**

NEXTREQUIREDTESTINTERVAL*

012318months+25%184days+25K92days+25%31days+25%"Therequiredtestintervalshallnotbelengthened morethanonestepatatime.Earlytestsmaybeperformed priortoenteringthe"nextrequiredtestinterval" (i.e.,inadvanceofthenominaltimelessthenegative25Ktolerance band).Earlytestsmaybeusedasanewreference pointfortestsofthesameinterval, however,theyarenotacceptable forlengthening thetestinterval.

• • Setpoint-driftisnotconsidered tobeavalvefailureforthepurposesofthistestschedule.

I 3/4.4REACTORCOOLANTSYSTEMBASES3/4.4.2SAFETYVALVESThereactorcoolantsystemsafetyvalvesoperatetopreventthereactorcoolantsystemfrombeingpressurized abovetheSafetyLimitofpsig.Eachsafetyvalveisdesignedtorelieveibsperhooratthevalvesetpoint.ThesystemisdesignedtomeettheASMEBoilerandPressureVesselCoderequirements thatthenuclearsystemreliefvalvesshal=lfunctiontopreventopeningofthesafetyvalves.Althoughthesafetyvalvefunctionisnotexpectedtoberequiredunderthemostlimitingtransient, aninoperable valverequiresshutdowninordertocomplywithASMECoderequirements.

Thetestingfrequency applicable tothereliefvalvefunctionofthesafety-relief valvesisprovidedtoensureoperability anddemonstrate reliability ofthevalves.Therequiredtestingintervalvarieswithobservedvalvefailures.

Thenumberofinoperable valvesfoundduringbothoperation andtestingofthesevalvesdetermines thetimeintervalforthenextrequiredtestofthesevalves.Earlytestsmaybeperformed priortoenteringthenextrequiredtestinterval(i.e.,inadvanceofthenominaltimelessthenegative25%tolerance band).Earlytestsmaybeusedasanewreference pointfortestsofthesametimeinterval, however,theyarenotacceptable forlengthening thetestintervalsincetheywerenotperformed withinthe+25%tolerance bandasrequiredbyTable4.4-10.Oemonstration ofthesafetyvalves'ift settingswilloccuronlyduringshutdownandwillbeperformed inaccordance withtheprovisions ofSectionXIoftheASMEBoilerandPressureVesselCode.

EMERGENCY CORECOOLINGSYSTEMSAUTOMATIC DEPRESSURIZATION SYSTEMLIMITINGCONDITION FOROPERATION 3.5.2TheAutomatic Depressurization System(ADS)shallbeOPERABLEwithatleast(6)*OPERABLEADSvalves.APPLICABILITY:

WithAverageCoolantTemperature

>212'FortheModeSwitchinRun,orStartup/Hot Standby.ACTION:a.WithoneoftheaboverequiredADSvalvesinoperable, operation maycontinueprovidedtheactuation logicoftheremaining ADSvalvesisoperableandtheCSSandLPCIsystemsareoperable, andtheHPCIsystemisdemonstrated operablewithin4hours;restoretheinoperable ADSvalvetooperablestatuswit'iin14daysorbeshutdownwithin12hoursandreducetheAverageCoolantTemperature to<212'Fwithinthefollowing 24hours.b.WithtwoormoreoftheaboverequiredADSvalvesinoperable, beshutdownwithin12hoursandreducetheAverageCoolantTemperature to<212'Fwithinthefollowing 24hours.SURVEILLANCE REUIREMENTS 4.5.2Inadditiontotheapplicable ASMEBoilerandPressureVesselCode,SectionXIrequirements, theADSshallbedemonstrated operable:

a.Atleastonceper18monthsbyperformance ofasystemfunctional testwhichincludessimulated automatic actuation throughtheautomatic depressurization

sequence, butexcluding valveactuation.

b.UntilMarch1,1979,atleastonceper18monthsby:1.ManuallyopeningeachADSvalvewiththereactoratorbelow5Xratedpowerandatnominaloperating pressureandverifying thateither:a.Theturbinebypassvalve(s)indicateacompensating valvemovement, orb.Thereactorcoolantsystempressuredecreases byanamountequivalent tothevalvepressurerelieving capacityforthetestconditions.

umeroAvavestobeconsistent withECCSanalysis.

EMERGENCY CORECOOLINGSYSTEMSAUTOMATIC DEPRESSUR IZATIONSYSTEMSURVEILLANCE REQUIREMENTS (Continued) 2.Conducting avisualinspection ofthesafety-relief andreliefvalvelinerestraints inthetorustoverifystructural integrity forcontinued operation.

c.AfterMarch1,1979,byperformance ofthefollowing testprogram:l.ManuallyopeningeachADSvalveinaccordance withthetestscheduleofTable4.4-10withthereactoratorbelow5%ratedpowerandatnominaloperating pressureandverifying thateither:a.Theturbine".ypassvalve(s)indicateacompensating valvemovement, orb.Thereactorcoolantsystempressuredecreases byanamountequivalent tothevalvepressurerelieving capacityforthetestconditions.

2.TheinitialNextRequiredTestIntervalofTable4.4-10shallbedetermined bythenumberofremotelyoperatedreliefandsafety-relief valvesfoundinoperable fromSeptember 1,1977toMarch1,1979.3.TheinitialvalvetestsofTable4.4-10shallbecompleted by,theearlierof:a.Thecompletion ofthenextrefueling outageoccurringafterMarch1,1979,orb.ThetimeperioddefinedbyMarch1,1979plustheinitialte'stinterval, determined above.4.Atleastonceper18monthsbyconducting avisualinspection ofthesafety-relief andreliefvalvelinerestraints inthetorustoverifystructural integrity forcontinued operation.

3/4.5EMERGENCY CORECOOLINGSYSTEMBASES3/4.5.2AUTOMATIC DEPRESSURIZATION SYSTEM(ADS)-UponfailureoftheHPCIStofunctionproperlyafterasmallbreakloss-of-coolant

accident, theADSautomatically causesthesafety-relief valvestoopen,depressurizing thereactorsothatflowfromthelowpressurecoolingsystemscanenterthecoreintimetolimitfuelcladdingtemperature tolessthan2200'F.ADSisconservatively requiredtobeoperablewhenever.reactorvesselpressureexceeds(150)psigeventhoughlowpressurecoolingsystemsprovideadequatecorecoolingupto(350)psig.ADSautomatically controls(7)safety-relief valvesalthoughthesafetyanalysisonlytakescreditfor(6).Therefore itisappropriate topermit(one)valvetobeout-of-service withoutmaterially reducingsystemreliability.

Thetestingfrequency applicable toADSvalvesisprovidedtoensureoperability anddemonstrate reliability ofthevalves.Therequired.test',ng intervalvarieswithobservedvalvefailures.

The,numberofinoperable valvesfoundduringbothoperation andtestingofthesevalvesdetermines thetimeintervalforthenextrequiredtestofthesevalves.Earlytestsmaybeperformed priortoenteringthenextrequiredtestinterval(i.e.,inadvanceofthenominaltimelessthenegative25%tolerance band).Earlytestsmaybeusedasanewreference pointfortestsofthesametimeinterval, however,theyarenotacceptable forlengthening thetestintervalsincetheywerenotperformed withinthe+25%tolerance bandasrequiredbyTable4.4-10.

~-

0DocketNo.50-220~4l)'g0ig7NiagaraflohawkPowerCorporation ATTN:tfr.GeraldK.RhodeVicePresident

-Engineering 300ErieBoulevard WestSyracuse, NeviYork13202Gentlemen:

RE:NINEMILEPOINTNUCLEARSTATIONUNITNO.1Distribution

~~DocketORB¹3LocalPDRNRCPDRGLearCParrishJZwetzigSNowickiAttorney, OELDOI8E(3)DEisenhut TBAbernathy JRBuchanan ACRS(16)Ourreviewofdatareceivedfromreactorvesselmaterialsurveillance programsindicates thatthematerials usedinreactorvesselfabrication mayhaveawidervariation fnsensitivity toradiation damagethanoriginally anticipated.

Inaddition, somereactorvesselsincorporate morethanoneheatofmaterials, including vleldmetalsfntheirbeltlfneregions,butalloftheseheatsmaynotbeincludedinthereactorvesselmaterialsurveillance program.Althoughourreviewofthesedatadoesnotrevealabasisforconcernregarding continued reactorvesselintegrity overthenextseveralyears,theinformation doesindicatetheneedforadetailedreviewofthematerials employedinreactorvesselconstruction (fnlightofthisrecentdata)andareviewofthespecimens employedinthesurveillance programtodetermine ffthepresentspecimens reasonably represent thelimitingmaterials fnthe.reactorvesselbeltlfneregion.Inordertoperformthesereviews,wewillneedtheinformation listedfntheenclosure relativetoeachofyourreactorvessel(s) andassocfated surveillance specimens.

'Accordingly, youarerequested tosupplyonesignedorfgfnaland39copiesoftheinformation listedintheenclosure within60 daysofreceiptofthisletter.This.requestforgenericinformation wasapprovedbyGAOunderablanketclearance number8-180225(R0072);thisclearance expiresJuly31,1977.Sincerely, OriginalsipnedbyGeorgeLear,ChiefOoeratinReactors8nch¹3officc3a-losureand'cc:nextpageSURNAMCQSeDATC~lormhEC-318(Rev.9-53)AKCM0240DivisonopOpera)ORB¹3~owicki-----....5/..../7.7............

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