ML093170022

Surry, Unit 2, Cycle 23 Core Operating Limits Report Revision 0

ML093170022
Person / Time
Site:	Surry
Issue date:	11/12/2009
From:	Funderburk C L Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
09-716
Download: ML093170022 (8)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261November12,2009U.S.NuclearRegulatoryCommissionAttention:DocumentControlDesk Washington,D.C.20555-0001SerialNo.09-716 NLOSlvlhDocketNo.50-281LicenseNo.DPR-37 VIRGINIA ELECTRICANDPOWER COMPANY (DOMINION)SURRYPOWER STATIONUNIT2CYCLE23CORE OPERATINGLIMITSREPORTREVISION0PursuanttoSurryTechnicalSpecification(TS)6.2.C,enclosedisacopyofDominion'sCoreOperatingLimitsReport(COLR)forSurryUnit2Cycle23PatternBOA, Revision O.Ifyouhaveanyquestionsorrequireadditionalinformation,pleasecontactMr.GaryMillerat(804)273-2771.

Sincerely,C.L.Funderburk,DirectorNuclearLicensingandOperationsSupportDominionResourcesServices,Inc.forVirginiaElectricandPowerCompany Enclosure CommitmentSummary:Therearenonewcommitmentsasaresultofthisletter.

cc:U.S.Nuclear Regulatory Commission Region"SamNunn Atlanta Federal Center61Forsyth Street,S.W.Suite 23T85 Atlanta,GA30303-8931Dr.V.Sreenivas NRC Project ManagerU.S.Nuclear Regulatory Commission One WhiteFlintNorthMaiIStop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738Ms.K.R.Cotton NRC Project ManagerU.S.Nuclear Regulatory Commission One WhiteFlintNorthMaiIStop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.09-716 Cycle23Core Operating Limits ReportPage2of2 COLR-S2C23,Rev.0 COLR-S2C23, Revision 0 CORE OPERATING LIMITS REPORTSurry2Cycle23 Pattern BOAPage1 of 6

1.0 INTRODUCTION

This Core Operating Limits Report(COLR)forSurry Unit2Cycle23hasbeenprepared in accordance with the requirements of Technical Specification 6.2.C.TheTechnicalSpecificationsaffectedbythisreportare:TS3.1.E-Moderator Temperature Coefficient TS 3.12.A.l, TS 3.12.A.2, TS 3.12.AJ,andTS 3.12.C.3.b.1.b

-Control BankInsertionLimits TS 3.12.B.landTS3.12.B.2-Power Distribution Limits TS 3.12.A.l.a, TS 3.12.A.2.a,andTS 3.12.0-Shutdown Margin

2.0 REFERENCES

1.VEP-FRD-42,Rev.2.1-A,"Reload Nuclear Design Methodology," August 2003 (MethodologyforTS 3.l.E-Moderator Temperature Coefficient; TS 3.12.A.l, TS 3.12.A.2, TS 3.12.A.3,andTS 3.12.C.3.b.1.b-ControlBank InsertionLimit;TS 3.12.B.landTS 3.12.B.2-Heat Flux Hot ChannelFactorand Nuclear EnthalpyRiseHotChannelFactor;TS 3.12.A.1.a, TS 3.12.A.2.a,andTS 3.12.0-Shutdown Margin)2a.WCAP-16009-P-A,"Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," (Westinghouse Proprietary), January 2005 (Methodology forTS3.12.B.landTS3.12.B.2-HeatFluxHotChannelFactor) 2b.WCAP-I0054-P-A,"WestinghouseSmallBreakECCSEvaluationModelUsingtheNOTRUMPCode,"August1985(WestinghouseProprietary)(MethodologyforTS 3.l2.B.landTS3.12.B.2-HeatFluxHotChannelFactor) 2c.WCAP-I0079-P-A,"NOTRUMP, A Nodal Transient Small Break and Oeneral Network Code," August 1985 (Westinghouse Proprietary)(MethodologyforTS 3.12.B.landTS 3.12.B.2-Heat Flux Hot Channel Factor)2d.WCAP-12610-P-A,"VANTAGE+FuelAssemblyReport,"June1990(WestinghouseProprietary)(Methodology forTS3.12.B.landTS 3.l2.B.2-HeatFluxHotChannelFactor) 3a.VEP-NE-2-A,Rev.0,"Statistical DNBR Evaluation Methodology,"June1987(MethodologyforTS3.12.B.landTS3.12.B.2-NuclearEnthalpyRiseHotChannelFactor)3b.VEP-NE-3-A,Rev.

0,"Qualification oftheWRB-lCHFCorrelationintheVirginiaPowerCOBRACode,"July1990(MethodologyforTS3.12.B.IandTS 3.l2.B.2-NuclearEnthalpyRiseHotChannelFactor)

COLR-S2C23, Rev.°Page2 of 6

3.0 OPERATING

LIMITSThecycle-specific parameterlimitsforthespecificationslisted insection1.0arepresented in the following subsections.

Theselimitshavebeendevelopedusingthe NRC-approved methodologiesspecifiedin TechnicalSpecification6.2.C.

3.1 Moderator

Temperature Coefficient (TS 3.I.E)3.1.1The Moderator TemperatureCoefficient(MTC)limitsare:

+6.0 pcm/Fatlessthan50percent ofRATEDPOWER,or

+6.0 pcm/Fat50percent of RATED POWER and linearlydecreasingto a pcm/F at RATED POWER 3.2 Control Bank Insertion Limits (TS 3.12.A.I, TS 3.I2.A.2,andTS3.12.C.3.b.1.b)3.2.1Thecontrolrodbanksshallbelimitedinphysical insertionasshowninFigure A-I.3.2.2Therod insertion limitfortheAandBcontrolbanksisthefully withdrawn positionasshownonFigure A-I.3.2.3Therod insertionlimitfortheAandBshutdownbanksisthefully withdrawn position as shown on Figure A-I.3.3 Shutdown Margin (TS 3.I2.A.1.a, TS 3.I2.A.2.a,andTS 3.I2.G)3.3.1 Whenever the reactorissubcriticaltheshutdown margin(SDM)shallbe 21.77%&Ik.COLR-S2C23,Rev.0Page3 of 6 3.4HeatFlux Hot Channel Factor-FQ(z)(TS 3.12.B.l)CFQ FQ(z)S--K(z)for P>0.5 P CFQ FQ(z)S--K(z)for P S 0.5 0.5 where: P=ThermalPower Rated Power 3.4.1 CFQ=2.32 3.4.2 K(z)is provided in Figure A-2.3.5 Nuclear Enthalpy Rise Hot Channel Factor-FMI(N)(TS 3.12.B.l)F!ili(N)S CFDHx{I+PFDH(I-P)}hPThermalPower were:=RatedPower 3.5.1 CFDH=1.56for Surry ImprovedFuel(SIP)3.5.2 PFDH=0.3 COLR-S2C23,Rev.0Page4 of 6 Figure A-I SURRYUNIT2 CYCLE 23 ROD GROUP INSERTION LIMITS Fully wId position=230steps 230 220 210 200 190 180 170 160 150:E140 III 0..2!130 III'It: c:: 120 o..'iii 110 o a..g-100 e C>90:§...80 70 60 50 40 30 20 10/(11(0.4938,230)

I/V///C-BANK (1.0,183)///iii"'"/"/!/i (0,151)!/I.//!//I/D-BANK//"//'.///I/V-(0,23)o 0.0 0.10.20.30.40.50.60.7FractionofRatedThermal Power0.80.9 1.0 COLR-S2C23,Rev.0Page5 of 6 Figure A-2K(Z)*NormalizedFQasaFunctionofCoreHeight(6,1.0)-r---r------r---(12,0.925)

I I!, I I 1.2 1.1 1.0 0.9 0.8 N Ci 0.7 u, e LLI N0.6:E0 z 0.5 I s 0.4 0.3 0.2 0.1 0.0 o 1 2 3 45678COREHEIGHT(FT) 910111213 COLR-S2C23,Rev.0Page6 of 6