ML17292A890

Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages

ML17292A890
Person / Time
Site:	Columbia
Issue date:	06/06/1997
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17292A889	List: GO2-97-115, Withdraws Request for Amend of Slmcpr.Requested Changes to Included & TS Page 2.0-1,modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13, Forwarded W/Corresponding Bases Page ML17292A890
References
NUDOCS 9706170163
Download: ML17292A890 (6)

Text

EXIGENTREQUESTFORAMENDMENT OFSLMCPRMODIFICATION OFREQUESTAttachment 2'agelof1ATTACHM<22lT 2RevisedTechnical Specification PageandCorresponding BasesPage970bi70ib3 970bOb&PDRADOCK05000397PPORE SLs2.0I'.0SAFETYLIMITS(SLs).2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10%ratedcoreflow:THERMALPOWERshallbea25%RTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10%ratedcoreflow:M~~~'e:~pp.M-a'~pp2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbea1325psig.2.2SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs;and2.2.2Insertallinsertable controlrods.~ngepfThe'MCPRforATRIUM-9X fuelshallbea1.13fortworecirculation loop~operation ora1.14forsinglerecirculation loopoperation.

Forallotherfuel,theMCPRshallbea1.07fortworecirculation loopoperation ora1.08forsinglerecirculation loopoperation.

TheMCPRlimitsfortheATRIUM-9X fuelareapplicable toCycle13,.only.WNP-22.0-1Amendment No.149 SLs2.02.0SAFETYLIHITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10%ratedcoreflow:THERHALPOWERshallbea25%RTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10%ratedcoreflow:TheHCPRforATRIUH-9X fuelshallbea1.13fortworecirculation loopoperation ora1.14forsinglerecirculation loopoperation.

Forallotherfuel,theHCPRshallbea1.07fortworecirculation loopoperation orw1.08forsinglerecirculation loopoperation.

TheHCPRlimitsfortheATRIUH-9X fuelareapplicable toCycle13only.2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbex1325psig.2.2SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs;and2.2.2Insertallinsertable controlrods.WNP-22.0-1Amendment No.

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ReactorCoreSLs82.1.1.BASESAPPLICABLE SAFETYANALYSES2.1.1.1FuelCladdingInteoritv

{continued) bundleflowforallfuelassemblies thathavearelatively highpowerandpotentially canapproachacriticalheatfluxcondition.

Theminimumbundleflowis>28x10'b/hr.Thecoolantminimumbundleflowandmaximumflowareaaresuchthatthemassfluxis>0.25x10'.lb/hr-ft'.

Fullscalecriticalpowerteststakenatpressures downto14.7psiaindicatethatthefuelassemblycriticalpowerat0.25x10'b/hr-ft~

isapproximately 3.35HWt.At25seRTPabundlepowerofapproximately 3.35Hwtcorresponds toabundleradialpeakingfactorof>2.9,whichissignificantly higherthantheexpectedpeakingfactor.Thus,aTHERMALPOWERlimitof25"RTPforreactorpressures

<785psigisconservative.

CJ'COCP'atDOCl~CDCISClC5H02.1.1.2HCPRTheHCPRSLensuressufficient conservatism intheoperating HCPRlimitthat,intheeventof.anAOOfromthelimitingcondition ofoperation, atleast99.Kofthefuelrodsinthecorewouldbeexpectedtoavoidboilingtransition.

Themarginbetweencalculated boilingtransition (i.e.,MCPR1.00)andtheHCPRSLisbasedonadetailedstatistical procedure thatconsiders theuncertainties inmonitoring treoperaiate.OnespecificuncertaiincludedintheSLisheuncertainty inherentintcriticalpowercorrelations.

Reference 4describes thmethodology usedindetermining theMCPRSLForSiemenswerCorporation fuel.Reference 5describes themethodology usedindetermining theHCPRSLforABBCENOfuel.Thecriticalpowercorrelations are'based onasignificant bodyofpractical testdata,providing ahighdegreeofassurance thatthecriticalpower,asevaluated bythecorrelation, iswithinasmallpercentage ortheactualcriticalpower.Aslongasthecorepressureandflowarewithintherangeofvalidityofthecriticalpowercorrelations, theassumedreactorconditions usedindefiningtheSLintroduce conservatism intothelimitbecauseboundinghighradialpowerfactorsandboundingflatlocalpeakingdistributions areusedtoestimatethenumbercontinued WNP-282.0-3.Revision 5

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