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Category:Fuel Cycle Reload Report
MONTHYEARML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML23102A1552023-04-11011 April 2023 Core Operating Limits Report, 2 Cycle 32 Pattern Hoo, Revision 0 ML22306A2112022-11-0101 November 2022 Core Operating Limits Report, Surry 1 Cycle 32 Pattern Sjk Revision 0 ML22306A2192022-11-0101 November 2022 Core Operating Limits Report - Surry 2 Cycle 31 Pattern Msk Revision 2 ML22179A2782022-06-27027 June 2022 Core Operating Limits Report, Cycle 31 Pattern Msk Revision 1 ML21307A4282021-11-0303 November 2021 Core Operating Limits Report Cycle 31 Pattern Msk Revision 0 ML21144A0832021-05-18018 May 2021 Core Operating Report Surry 2 Cycle 30 Operating Pattern Syk Revision 1 ML21140A3922021-05-18018 May 2021 Core Operating Limits Report - Surry 1 Cycle 31 Pattern Rna Revision 0 ML20140A1612020-05-12012 May 2020 Core Operating Limits Report: Surry 2 Cycle 30, Pattern Syk, Revision 0 ML19317D4602019-11-0707 November 2019 Core Operating Limits Report; Surry 1 Cycle 30 Pattern Apo Revision 0 ML18302A1222018-10-22022 October 2018 Core Operation Limits Report, Surry 2 Cycle 29 Pattern Sup, Revision 0 ML18128A1952018-05-0101 May 2018 Core Operating Limits Report Cycle 29 Pattern Zeu, Revision 0 ML17163A1772017-06-0606 June 2017 Core Operating Limits Report, Cycle 28 Pattern PRI, Revision 0 ML16312A0632016-11-0202 November 2016 Core Operating Limits Report for Cycle 28 Pattern APT, Revision 0 ML16112A2512016-03-0707 March 2016 Re Cycle 27 Startup Physics Tests Report ML16042A4032016-02-0404 February 2016 Core Operating Limits Report, Cycle 27 Pattern Hgg, Revision 2 ML15345A2422015-12-0808 December 2015 Virginia Electric and Power Company (Dominion) Surry Power Station Unit 2 Core Operating Limits Report Surry 2 Cycle 27 Pattern Hgg Revision 1 ML14119A1862014-04-23023 April 2014 Core Operating Limits Report Cycle 26 Pattern Eba Revision 0 ML13308B9062013-10-28028 October 2013 Core Operating Limits Report, Surry 1 Cycle 26 Pattern Apx Revision 0 ML12312A0652012-10-30030 October 2012 Submittal of Core Operating Limits Report (Colr), Cycle 25 Pattern Who, Revision 0 ML12143A1412012-05-16016 May 2012 Core Operating Limits Report Surry 1 Cycle 25 Pattern Gnu Revision 0 ML1123605802011-08-24024 August 2011 Cycle 24 Pattern Upg Revision 1 ML1123605152011-08-24024 August 2011 Core Operating Limits Report, Cycle 24 Pattern Owl Revision 1 ML1110404212011-04-14014 April 2011 Cycle 24 Core Operating Limits Report, Revision 0 ML11306A0242011-02-14014 February 2011 Cycle 24 Startup Physics Tests Report ML1035501802010-12-20020 December 2010 Cycle 23 Core Operating Limits Report, Revision 2 ML1031905152010-11-12012 November 2010 Cycle 24 Core Operating Limits Report, Revision 0 ML0931700222009-11-12012 November 2009 Cycle 23 Core Operating Limits Report Revision 0 ML0924005442009-08-27027 August 2009 Cycle 22 Core Operating Limits Report, Revision 2 ML0924004262009-08-27027 August 2009 Surrey, Unit 1 - Cycle 23 Core Operating Limits Report, Revision 1 ML0916603562009-06-15015 June 2009 Cycle 22 Core Operating Limits Report, Revision 1 ML0911306312009-04-23023 April 2009 Cycle 23 Core Operating Limits Report ML0810802542008-04-17017 April 2008 Cycle 22 Core Operating Limits Report ML0734103472007-12-0505 December 2007 Cycle 22 Core Operating Limits Reports ML0734005282007-12-0505 December 2007 Cycle 21 Core Operating Limits Report ML0721904822007-07-31031 July 2007 Proposed Technical Specifications Change Addition of Astrum Methodology to Core Operating Limits Report References and Revised Large Break LOCA Analysis Supplemental Information ML0632101302006-11-16016 November 2006 Cycle 21 Core Operating Limits Report ML0613504262006-05-15015 May 2006 Virginia Electric and Power Company Surry Power Station Unit 1 Revision to Cycle 21 Core Operating Limits Report ML0611802292006-04-28028 April 2006 Cycle 21 Core Operating Limits Report ML0515902922005-05-31031 May 2005 Cycle 20 Core Operating Limits Report ML0434402752004-12-0909 December 2004 Transmittal of Cycle 20 Core Operating Limits Report ML0333003342003-11-17017 November 2003 Cycle 19 Core Operating Limits Report, Revision 0 ML0330104502003-10-20020 October 2003 Cycle 19, Revision 1 to Core Operating Limits Report ML0316009722003-05-21021 May 2003 Cycle 19 Core Operating Limits Report 2024-05-13
[Table view] Category:Letter
MONTHYEARML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - 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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