ML17264A344

Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint

ML17264A344
Person / Time
Site:	Ginna
Issue date:	02/09/1996
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A343	List: ML17264A342 ML17264A344 ML17264A345
References
NUDOCS 9602130462
Download: ML17264A344 (7)

Text

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATION FORAMENDMENT TPKRATINLlEEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"

),Rochester GasandElectricCorporation

("RGEcE"),

holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatLicensebeamended.ThisrequestforchangeinTechnical Specifications istoreviseTable3.3.2-1,Function5b,"Feedwater Isolation, SGWaterLevel-High"toraisetheallowable valueandtripsetpoint.

Thischangereflectsdesignimprovements inthereplacement steamgenerators beinginstalled atGinnaStationduringthe1996Refueling Outage.Adescription oftheamendment request,necessary background information, justification oftherequested change,safetyevaluation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.AmarkedupcopyoftheproposedGinnaStationTechnical Specifications whichshowstherequested changeissetforinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.'7602130462 960209'DRADQCK05000244PDR Theevaluation setforthinAttachment Ademonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Theproposedchangealsodoesnotinvolveasignificant hazardsconsideration.

WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectricCorporation RobertC.MecredyVicePresident NuclearProduction Subscribed andsworntobeforemeonthis9thdayofFebruary, 1996.g~MNotaryPublicJOANNES.GORMANNotaryPublicintheStateofNewYorkOrleansCountyCommission ExpiresNov.19

/Qpflf><,$~1>IIPO(V.'ll~t ATTACHMENT AR.E.GINNANUCLEARPOWERPLANTLICENSEAMENDMENT REQUESTTECHNICAL SPECIFICATIONS TABLE3.3.2-1Thisattachment providesadescription oftheamendment requestandnecessary justification fortheproposedchanges.Theattachment isdividedintosixsectionsasfollows.SectionAidentifies allchangestothecurrentGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.

SectionCprovidesdetailedjustification fortheproposedchanges.Asafetyevaluation, significant hazardsconsideration evaluation andenvironmental consideration oftherequested changesareprovidedinSectionsD,E,andF,respectively.

A.DESCRIPTION OFAlVKNDMENT REQUESTThisLicenseAmendment Request(LAR)proposestoreviseGinnaStationTechnical Specifications Table3.3.2-1asfollows(seeAttachment BandC):1.Technical Specification Table3.3.2-1,FunctionSb.i.Theallowable valueischangedfrom<68%to<94%.ii.Thetripsetpointvalueischangedfrom<67%to<85%.B.BACKGROUND 1.HistoryTheSteamGenerator WaterLevel-Highfeedwater isolation setpointisdesignedtopreventexcessive moisturecarryover tothemainsteamsystem,whichwouldcauseexcessive wearonthemainturbine.SteamGenerators separatewaterintwostages,aPrimarystageandasecondary stage.Primaryseparators arelocatedinthesteamdrumofthegenerator belowthesecondary separators, andgenerally workonthecentrifugal principle.

Thehighwaterlevelsetpointischosensuchthatwaterinthedowncomer isnotabovethetopoftheseprimaryseparators whichwouldfloodthemanddegradetheirperformance. GinnaStationisplanningtoreplaceitssteamgenerators duringthe1996Refueling Outage.Theoriginalsteamgenerators areWestinghouse Model44steamgenerators.

Theprimaryseparator floodpointforthesegenerators isatapproximately 75%narrowrangewaterlevel.Consequently, asetpointsufficiently belowthisvaluetoallowforinstrument andprocessmeasurement uncertainty ischosenforthecurrentsetpointvalueof67%narrowrange.Replacement steamgenerators arebeingmanufactured byBabcockandWilcoxInternational.

Thefloodpointfortheprimaryseparators onthesegenerators isabove100%narrowrangelevel.Consequently, newsetpoints sufficiently below100%toaccountforprocessmeasurement uncertainty arechosenforanallowable value(94%),andinstrument uncertainty forasetpointvalue(85%).Thisexpandedrangeallowstheoperatormoretimetorestoreleveltonominalconditions usingcontrolled meanspriortoinitiation offeedwater isolation.

HardwareModifications Priortoimplementing thisTechnical Specification changethesteamgenerators mustbereplaced.

Nootherhardwarechangesarerequired.

C.JUSTIFICATION Thedesignofthereplacement steamgenerators issuchthattheprimarysteamseparators arelocatedatahigherelevation inthesteamdrumthanintheexistingsteamgenerators.

Thebottomoftheactualseparator isapproximately 14inchesabovetheuppernarrowrangeleveltap.Therefore, itisacceptable tooperatewithwaterlevelsabove100%narrowrangelevelwithoutdegrading separator performance.

Sincewaterlevelabove100%cannotbemonitored, 100%ischosenasthelimit.ThUPSAliidlyhdIhipi(Si15..6,~i" denertrAmshericRelief ValveanFeewernrllveFailire)currentlyuse avalueof100%narrowrangelevel.Therefore, theaccidentanalysisisnotaffectedbythisproposedchange.Minimizing thechallenges tothissetpointisbeneficial.

Fastswingsinfeedwater valvepositioncausedbyactuation/clearing ofthissetpointmakeitdifficult tocontrolthefeedwater system,levelintheothersteamgenerator, andprimarysidetemperature.

Byraisingthissetpointthenumberofchallenges arereduced.D.SAFETYEVALUATION TheSteamGenerator WaterLevel-Highfeedwater isolation functionisdesignedtopreventexcessive moisturecarryover tothemainsteamsystem.Theproposedsetpointchangedoesnotdegradethecapability ofthemoistureseparators andtherefore thisfunctionisunchanged. TheUFSARaccidentanalysesthatmodelthisfunction(UFSARSection15.1.6)useavalueof100%narrowrangelevel.Therefore theaccidentanalysisisnotaffectedbythisproposedchange.Basedontheabove,theproposedamendment doesnotinvolveanunreviewed safetyquestionandwillnotadversely affectorendangerthehealthandsafetyofthegeneralpublic.E.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications doesnotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Theproposedsetpointchangedoesnotdegradetheperformance ofanyplantequipment Therefore, theprobability ofanaccidentisnotincreased.

Sincetherevisedtripsetpointandallowable valueremainboundedbytheaccidentanalysisvalueof100%steamgenerator narrowrangelevel,theconsequences ofanyaccidentarenotadversely affected.

Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangedoesnotinvolveaphysicalalteration totheplant(i.e.,nonewordifferent typesofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation, Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Therevisedsetpointandallowable valueremainboundedbytheaccidentanalysisassumptions.

Theexistingvaluesarebasedon'design considerations andnotaccidentanalysisparameters.

Thereplacement steamgenerators arenotrestricted bythesamedesignconsiderations withrespecttotheESFASSteamGenerator WaterLevel-Highfunction.

Therefore, thischangedoesnotinvolveareduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

F.ENVIRONMENTAL CONSIDERATION RGBhasevaluated theproposedchangesanddetermined that:Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionEabove;2.Thechangesdonotinvolveachangeinthetypesorincreaseintheamountsofanyeffluents thatmaybereleasedoffsitesinceequipment performance isunchanged, andtheaccidentanalysisisunchanged.

Thechangesdonotinvolveanyincreaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR,norareanyoperating ortestingpractices tobechanged.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).

Therefore, pursuantto10CFR51.22(b),

anenvironmental assessment oftheproposedchangesisnotrequired.