ML14169A493
| ML14169A493 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/22/2014 |
| From: | Hager N R Duke Energy Carolinas |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14169A328 | List: |
| References | |
| CNS-14-073 CNEI-0400-269, Rev 1 | |
| Download: ML14169A493 (31) | |
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Catawba Unit 1 Cycle 22 Core Operating Limits Report Revision 1 April2014 CNEI-0400-269 Page l of 31 Revision l Calculation Number: CNC-1553.05-00-0610, Revision 1 Date Prepared By:
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':t.l '2. J 'f.. S.G. Godwin r I Checked By:
'I I J-}//'1 (Sections l.l, 2.1, and 2.9 -2.18) Approved By: J::f.: riM.ff::t I QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5. ( (
CNEI-0400-269Page 2of 31Revision 1Catawba 1 Cycle 22Core Operating Limits ReportImplementation Instructions for Revision 1Revision Description and PIP TrackingRevision 1of the CatawbaUnit 1Cycle 22COLR contains limits specific to the reload coreand is revised to provide explicit implementation instructions to ensure the C1C22 COLR implementation occurs properly for analyzed core conditions. PIP#C-10-08327 is associated with this revision.Note: Several PIPs resulted in changes to COLR limitsin Revision 0. These changes were to COLR Section 2.10 Boron Dilution Mitigation System as a result of PIP #C-10-08327 and COLR Section 2.18 Boration Systems Borated Water Source as a result of PIP #C-14-02092.Implementation ScheduleThe CatawbaUnit 1Cycle 22 COLRrequires the reload 50.59 be approved prior to implementation and fuel loading.Revision 1may become effective any time during No MODEbetween Cycles 21and 22but must becomeeffective prior to entering MODE6 which starts Cycle 22ANDthe C1C22 COLR requires a BDMS Alarm Ratio less than or equal to 2 prior to entering MODE 5; the BDMS Alarm Ratio is being modified for both trains in Unit 1 in EC 110698 during 1EOC21.The Catawba Unit 1 Cycle 22COLR will cease to be effective during No MODEbetween Cycles22and 23.Data files to be Implemented No data files are transmitted as part of this document.Engineering Instruction Inspection Waiver Per EDM-130 "Engineering Drawings", the Engineering Instruction (EI) has been waived per Reference "CN -1438.88".
CNEI-0400-269Page 3of 31Revision 1Catawba 1 Cycle 22Core Operating Limits ReportREVISION LOG RevisionEffectiveDatePages AffectedCOLR0April20141-31, Appendix A*C1C22COLR, Rev. 01April 20141-31C1C22 COLR, Rev. 1*Appendix A containspower distribution monitoring factors used in Technical Specification Surveillance. Appendix A is included only in the electronic COLR copy
sent to the NRC.
CNEI-0400-269Page 4of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report1.0Core Operating Limits ReportThis Core Operating Limits Report (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Technical Specifications that reference this report are listed below along with the NRC approved analytical methods used todevelop and/or determine COLR parameters identified in Technical Specifications.
TSSectionTechnical SpecificationsCOLR Parameter COLR SectionNRC Approved Methodology (Section 1.1 Number)2.1.1Reactor Core Safety Limits RCS Temperature and Pressure Safety Limits2.16, 7, 8, 9, 10, 12, 15, 163.1.1Shutdown MarginShutdown Margin2.26, 7, 8, 12, 14, 15, 163.1.3Moderator Temperature CoefficientMTC2.36, 7, 8, 12, 14, 163.1.4Rod Group Alignment LimitsShutdown Margin2.26, 7, 8, 12, 14, 15, 163.1.5Shutdown Bank Insertion LimitShutdown Margin2.22, 4, 6, 7, 8,9,Rod Insertion Limits2.410,12, 14, 15, 163.1.6Control Bank Insertion LimitShutdown Margin2.22, 4, 6, 7, 8, 9,Rod Insertion Limits2.510, 12,14, 15, 163.1.8Physics Tests ExceptionsShutdown Margin2.26, 7, 8, 12, 14, 15, 163.2.1Heat Flux Hot Channel FactorF Q2.62, 4, 6, 7, 8, 9, 10, AFD2.812, 15, 16 OTT 2.9Penalty Factors2.63.2.2Nuclear Enthalpy Rise Hot Channel FH2.72, 4, 6, 7, 8, 9,FactorPenalty Factors2.710, 12,15, 163.2.3Axial Flux DifferenceAFD2.82, 4, 6, 7, 8, 15, 163.3.1Reactor Trip System Instrumentation OTT2.96, 7, 8, 9, 10, 12 OPT2.915, 163.3.9Boron Dilution Mitigation SystemReactor Makeup Water Flow Rate2.106, 7, 8, 12, 14, 163.4.1RCS Pressure, Temperature and Flow limits for DNBRCS Pressure, Temperature and Flow2.116, 7, 8, 9, 10, 123.5.1AccumulatorsMax and Min Boron Conc.2.126, 7, 8, 12, 14, 163.5.4Refueling Water Storage TankMax and Min Boron Conc.2.136, 7, 8, 12, 14, 163.7.15Spent Fuel Pool Boron ConcentrationMin Boron Concentration2.146, 7, 8, 12, 14, 163.9.1Refueling Operations -Boron ConcentrationMin Boron Concentration2.156, 7, 8, 12, 14, 165.6.5Core Operating Limits Report (COLR)Analytical Methods1.1NoneThe Selected License Commitments that reference this report are listed below SLC SectionSelected Licensing CommitmentCOLR Parameter COLR SectionNRC Approved Methodology (Section 1.1 Number)16.7-9Standby Shutdown SystemStandby Makeup Pump Water Supply2.166, 7, 8, 12, 14, 1616.9-11Boration Systems -Borated Water Source -ShutdownBorated Water Volume and Conc. for BAT/RWST2.176, 7, 8, 12, 14, 1616.9-12Boration Systems -Borated Water Source -OperatingBorated Water Volume and Conc. for BAT/RWST2.186, 7, 8, 12, 14, 16 CNEI-0400-269Page 5of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report1.1Analytical MethodsAnalytical methods used to determine core operating limits for parameters identified in Technical Specificationsand previously reviewed and approved by the NRC as specified in Technical Specification 5.6.5 are as follows.1.WCAP-9272-P-A, "WestinghouseReloadSafetyEvaluationMethodology," (WProprietary).Revision 0Report Date: July 1985 Not Used2.WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Modelusing the NOTRUMP Code, " (WProprietary).Revision 0 Report Date: August 1985Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: SafetyInjection into the Broken Loop and COSI Condensation Model," (WProprietary). (Referenced in Duke Letter DPC-06-101)Revision 1 July 19973.WCAP-10266-P-A, "The 1981 Version of Westinghouse Evaluation Model Using BASH Code", (WProprietary).Revision 2Report Date: March 1987 Not Used4.WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (WProprietary).Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)Report Date: March 1998 5.BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for RecirculatingSteam Generator Plants," (B&W Proprietary).Revision 1SER Date: January 22, 1991Revision 2SER Dates: August 22, 1996 and November 26, 1996.Revision 3SER Date: June 15, 1994.Not Used CNEI-0400-269Page 6of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report1.1Analytical Methods (continued)6.DPC-NE-3000-PA, "Thermal-Hydraulic Transient Analysis Methodology," (DPC Proprietary).Revision 5aReport Date: October 20127.DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).Revision 0aReport Date: May20098.DPC-NE-3002-A, "UFSAR Chapter 15 System Transient Analysis Methodology".Revision 4bReport Date: September 20109.DPC-NE-2004P-A, "DukePower Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).Revision 2aReport Date: December200810.DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).Revision 4aReport Date: December 200811.DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3and GDTACO," (DPC Proprietary).Revision 2Report Date: August 2012Not Used12.DPC-NE-2009-PA, "Westinghouse Fuel Transition Report," (DPC Proprietary).Revision 3aReport Date: September 201113.DPC-NE-1004-A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P." Revision 1aReport Date: January 2009Not Used CNEI-0400-269Page 7of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report1.1Analytical Methods (continued)14.DPC-NF-2010-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design." Revision 2aReport Date: December 200915.DPC-NE-2011-PA, "Duke Power Company Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).Revision 1aReport Date: June 200916.DPC-NE-1005-PA, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX", (DPC Proprietary).Revision 1ReportDate: November12, 200817.BAW-10231P-A, "COPERNIC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)Revision 1SER Date: January 14, 2004Not Used CNEI-0400-269Page 8of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.0Operating LimitsCycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified inSection 1.1.2.1Reactor Core Safety Limits(TS 2.1.1)The Reactor Core Safety Limits are shown in Figure 1.2.2Shutdown Margin-SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.2.1For TS 3.1.1, SDMshall be greater than or equal to 1.3% K/K in MODE2 with Keff < 1.0 and in MODES3 and 4.
2.2.2For TS 3.1.1, SDMshall be greater than or equal to 1.0% K/K in MODE5.
2.2.3For TS 3.1.4, SDMshall be greater than or equal to 1.3% K/K in MODE1 and MODE2.2.2.4For TS 3.1.5, SDMshall be greater than or equal to 1.3% K/K in MODE1 and MODE2 with any controlbank not fully inserted.
2.2.5For TS 3.1.6, SDMshall be greater than or equal to 1.3% K/K in MODE1 and MODE2 with Keff >1.0.
2.2.6For TS 3.1.8, SDMshall be greater than or equal to 1.3% K/K in MODE2during PHYSICSTESTS.
CNEI-0400-269Page 9of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 1Reactor Core Safety LimitsFour Loops in Operation 580 590 600 610 620 630 640 650 660 6700.00.20.40.60.81.01.2Fraction of Rated Thermal Power RCS Tavg (°F)
DO NOT OPERATE IN THIS AREA2100 psia2280 psia2400 psia1945 psiaACCEPTABLE OPERATION CNEI-0400-269Page 10of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.3Moderator Temperature Coefficient -MTC (TS 3.1.3) 2.3.1Moderator Temperature Coefficient (MTC) Limits are:MTC shall be less positive than the upper limits shown inFigure 2. BOC, ARO, HZP MTC shall be less positive than 0.7E-04K/K/°F.EOC, ARO, RTP MTC shall be less negative than the -4.3E-04K/K/°F lower MTC limit.
2.3.2300 ppm MTC Surveillance Limit is:
Measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04K/K/°F.2.3.360 PPM MTC Surveillance Limit is:Measured 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -4.125E-04K/K/°F.Where:BOC =Beginning of Cycle (burnup corresponding to most positive MTC)EOC =End of Cycle ARO =All Rods Out HZP =Hot Zero Thermal Power RTP =Rated Thermal Power PPM =Parts per million (Boron)2.4Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1Each shutdown bank shall be withdrawn to at least 222steps. Shutdown banks are withdrawn in sequence and with no overlap.2.5Control Bank Insertion Limits (TS 3.1.6)
2.5.1 Control
banks shall be within the insertion, sequence, and overlap limits shown in Figure 3. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown inTable 1.
CNEI-0400-269Page 11of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 2Moderator Temperature Coefficient Upper Limit Versus Power LevelNOTE:Compliance with Technical Specification 3.1.3 may require rod withdrawal limits. Refer tothe Unit 1 ROD manual for details.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.00102030405060708090100Moderator Temperature Coefficient (1.0E-04 DK/K/
o F)Percent of Rated Thermal PowerUnacceptable OperationAcceptable Operation CNEI-0400-269Page 12of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 3Control Bank Insertion Limits Versus Percent Rated Thermal PowerThe Rod Insertion Limits(RIL)for Control Bank D (CD), Control Bank C (CC), and Control Bank B (CB) can be calculated by:Bank CD RIL = 2.3(P)-69{30<P<100}Bank CCRIL = 2.3(P)+47{0<P<76.1}for CC RIL = 222 {76.1 < P <100}Bank CBRIL = 2.3(P)+163{0<P<25.7}for CB RIL = 222 {25.7 < P <100}where P = %Rated Thermal PowerNOTES:Compliance with Technical Specification 3.1.3 may require rod withdrawal limits. Refer to the Unit 1 ROD manual for details.
0 20 40 60 80 100 120 140 160 180 200 2200102030405060708090100Rod Insertion Position (Steps Withdrawn)Percent of Rated Thermal PowerFully Withdrawn(Maximum = 231) 231Control Bank BControl Bank CControl Bank D(0%, 163)(0%, 47)(30%, 0)(100%, 161)Fully InsertedFully Withdrawn(Minimum = 222)
CNEI-0400-269Page 13of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportTable 1Control BankWithdrawal Steps and SequenceControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00222 Stop10600223 Stop107002221160 Start02231160 Start0222222 Stop1060223223 Stop10702222221160 Start2232231160 Start222222222 Stop106223223223 Stop107ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00224 Stop10800225 Stop109002241160 Start02251160 Start0224224 Stop1080225225 Stop10902242241160 Start2252251160 Start224224224 Stop108225225225 Stop109ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00226 Stop11000227 Stop111002261160 Start02271160 Start0226226 Stop1100227227 Stop11102262261160 Start2272271160 Start226226226 Stop110227227227 Stop111ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00228 Stop11200229 Stop113002281160 Start02291160 Start0228228 Stop1120229229 Stop11302282281160 Start2292291160 Start228228228 Stop112229229229 Stop113ControlControlControlControlControlControlControlControlBank ABank BBank CBank DBank ABank BBank CBank D0 Start0000 Start0001160 Start001160 Start00230 Stop11400231 Stop115002301160 Start02311160 Start0230230 Stop1140231231 Stop11502302301160 Start2312311160 Start230230230 Stop114231231231 Stop115Fully Withdrawn at 222 StepsFully Withdrawn at 223 StepsFully Withdrawn at 224 StepsFully Withdrawn at 225 StepsFully Withdrawn at 226 StepsFully Withdrawn at 227 StepsFully Withdrawn at 230 StepsFully Withdrawn at 231 StepsFully Withdrawn at 228 StepsFully Withdrawn at 229 Steps CNEI-0400-269Page 14of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.6Heat Flux Hot Channel Factor -F Q(X,Y,Z) (TS 3.2.1) 2.6.1 F Q(X,Y,Z) steady-state limits are defined by the following relationships:
F RTP Q*K(Z)/Pfor P > 0.5Error! Bookmark not defined.Error! Bookmark not defined.
F RTP Q*K(Z)/0.5for P <0.5 where,P = (Thermal Power)/(Rated Power)Note: The measured F Q(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the F Qsurveillance limits as defined for COLR Sections 2.6.5 and 2.6.6.
2.6.2 F RTP Q= 2.70 x K(BU) 2.6.3K(Z) is the normalized F Q(X,Y,Z)as a function of core height. K(Z) for Westinghouse RFA fuel is provided in Figure 4.2.6.4K(BU) is the normalized F Q(X,Y,Z)as a function of burnup. F RTP Qwith the K(BU) penalty for Westinghouse RFA fuel is analytically confirmed in cycle-specific reload calculations. K(BU) is set to1.0 at all burnups.The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
2.6.5[F L Q(X,Y,Z)]OP=Y,Z)* M Q(X,Y,Z)UMT
- TILT F D Q (X, where:[L Q F(X,Y,Z)]OP=Cycle dependent maximum allowable design peaking factor that ensures F Q(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
L Q F(X,Y,Z)OPincludes allowances for calculation and measurement uncertainties.
D Q F(X,Y,Z)=Design power distribution for F Q.D Q F(X,Y,Z) is provided inAppendix Table A-1for normal operating conditions and in CNEI-0400-269Page 15of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportAppendix Table A-4for power escalation testing during initial startup operation.
M Q(X,Y,Z) =Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. M Q(X,Y,Z) is provided inAppendix Table A-1for normal operating conditions and inAppendix Table A-4for power escalation testing during initial
startup operation.UMT =Total Peak Measurement Uncertainty. (UMT = 1.05)MT =Engineering Hot Channel Factor. (MT = 1.03).TILT =Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.6[F L Q(X,Y,Z)]RPS=F D Q(X,Y,Z)* M C(X,Y,Z)UMT
- TILT where:[F L Q(X,Y,Z)]RPS=Cycle dependent maximum allowable design peaking factor that ensures F Q(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation withinthe AFD, RIL, and QPTRlimits.
[F L Q(X,Y,Z)]RPSincludes allowances for calculation and measurement uncertainties.
F D Q(X,Y,Z) =Design power distributions for F Q.F D Q(X,Y,Z) is provided inAppendix Table A-1for normal operating conditions and inAppendix Table A-4for power escalation testing during initial
startup operations.
M C(X,Y,Z) =Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. M C(X,Y,Z) is provided inAppendix Table A-2for normal operating conditions and inAppendix Table A-5for power escalation testing during initial
startup operations.UMT =Total Peak Measurement Uncertainty. (UMT = 1.05)MT = Engineering Hot Channel Factor. (MT = 1.03).
CNEI-0400-269Page 16of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportTILT =Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.7KSLOPE = 0.0725 where:KSLOPE = Adjustment to K 1value from OTT trip setpoint required to compensate for each 1%
M Q F(X,Y,Z) exceeds L Q F (X,Y,Z)RPS.2.6.8 F Q(X,Y,Z) Penalty Factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.
CNEI-0400-269Page 17of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 4K(Z), Normalized F Q(X,Y,Z) as a Function of Core Heightfor Westinghouse RFA Fuel0.0000.200 0.400 0.600 0.800 1.000 1.2000.02.04.06.08.010.012.0K(Z)Core Height (ft)
(0.0, 1.00)
(4.0, 1.00)(12.0, 0.9259)
(4.0, 0.9259)Core Height(ft)K(Z) 0.01.000<41.000>40.925912.00.9259 CNEI-0400-269Page 18of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportTable 2 F Q(X,Y,Z) and FH(X,Y) Penalty FactorsFor Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2BurnupF Q(X,Y,Z)FH (X,Y)(EFPD)Penalty Factor(%)Penalty Factor (%)42.002.00122.002.00 252.002.00
50 2.41 2.00752.002.001002.002.00 1252.002.00 1502.002.00 1752.002.00 2002.002.00 2252.002.00 2502.002.00 2752.002.00 3002.002.00 3252.002.00 3502.002.00 3752.002.00 4002.002.00 4252.002.00 4502.002.00 4752.002.00 4922.002.00 5002.002.00 5022.002.00 5072.002.00 5172.002.00 5272.002.00 Note:Linear interpolation is adequate for intermediate cycle burnups. All cycle burnups outside the range of the table shall use a 2% penalty factor for both F Q(X,Y,Z) and FH(X,Y) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
CNEI-0400-269Page 19of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.7Nuclear Enthalpy Rise Hot Channel Factor -FH (X,Y) (TS 3.2.2)
FHsteady-state limits referred to in Technical Specification 3.2.2 aredefined by the following relationship.
2.7.1 LCO L H Y)](X,[F= MARP (X,Y)
- 1.0 + 1 RRH*(1.0-P)where: LCO L H Y)](X,[Fis the steady-state, maximum allowed radial peakand includes allowances for calculation/measurement uncertainty. MARP(X,Y) =Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in
Table 3.P=Thermal PowerRated Thermal PowerRRH =Thermal Power reduction required to compensate for each 1% measured radial peak, M H F(X,Y),exceeds the limit. (RRH = 3.34, 0.0 < P <1.0)The following parameters are required for core monitoring per the surveillance requirements of Technical Specification 3.2.2.
2.7.2[L H F(X,Y)]SURV=TILT*UMR Y)(X, M*Y)(X, F H D Hwhere:[L H F(X,Y)]SURV=Cycle dependent maximum allowable design peaking factor that ensures FH(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
L H F(X,Y)SURVincludes allowances for calculation and measurement uncertainty.
F DH(X,Y)=Design radial power distribution for FH.F DH(X,Y) is provided inAppendix Table A-3for normal operation and inAppendix Table A-6for power escalation testing during initial startupoperation.
CNEI-0400-269Page 20of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report MH(X,Y)=Margin remaining in core location X,Y relative to Operational DNB limits in the transientpower distribution.
MH(X,Y) is provided inAppendix Table A-3for normal operation and in Appendix Table A-6for power escalation testing during initial startup operation.UMR =Uncertainty value for measured radial peaks(UMR = 1.0).UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable MH(X,Y).TILT =Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.7.3 RRH = 3.34 where:
RRH =Thermal Power reduction required to compensate for each 1% measured radial peak, M H F(X,Y)exceeds its limit. (0 < P <1.0) 2.7.4 TRH = 0.04 where:TRH =Reduction in OTT K 1setpointrequired to compensate for each 1% measured radial peak, M H F(X,Y)exceeds its limit.
2.7.5 FH(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.2.8Axial Flux Difference -AFD (TS 3.2.3) 2.8.1Axial Flux Difference (AFD) Limits are provided in Figure 5.
CNEI-0400-269Page 21of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportTable 3Maximum Allowable Radial Peaks (MARPS)RFA Fuel MARPs100% Full PowerCoreHeight(ft)1.051.11.21.31.41.51.61.71.81.92.13.03.250.121.80921.85531.94891.99531.97412.10732.04982.00901.93331.86251.77801.31511.24611.201.81021.85401.94011.99531.97412.10732.01911.97751.90091.83061.78521.30071.22352.401.80931.85251.93121.97791.97412.07351.99531.95191.87601.80541.73201.46331.46163.601.80981.85141.92041.96411.97412.04951.96561.92581.85241.78551.69961.46751.38744.801.80971.85141.90581.94491.97412.00591.94411.92331.85381.78361.67141.29871.25796.001.80971.85141.89211.92121.94551.93361.87981.86251.80241.74721.67051.32931.26027.201.80701.84381.87161.89301.88721.87231.80941.78661.73321.68121.59821.28711.21958.401.80731.83191.84521.85711.81561.79501.73591.70891.65441.60101.51271.21821.15789.601.80721.81021.80931.79131.73751.71821.65721.63471.58081.53011.44441.14311.091410.801.79801.78681.76111.71631.65381.63151.57431.55731.50881.46241.38321.10091.047011.401.78921.76521.72501.66451.60571.58261.52891.50981.46371.42181.34581.06701.0142 Axial Peak CNEI-0400-269Page 22of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 5Percent of Rated Thermal Power Versus Percent Axial Flux Difference LimitsNOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to the Unit 1 ROD manual for operational AFD limits.
0 10 20 30 40 50 60 70 80 90100-50-40-30-20-1001020304050Percent of Rated Thermal PowerAxial Flux Difference (% Delta I)(+10, 100)(-20, 100)(-36, 50)(+21, 50)Acceptable OperationUnacceptable OperationUnacceptable Operation CNEI-0400-269Page 23of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.9Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1Overtemperature T Setpoint Parameter ValuesParameterNominal ValueNominal Tavg at RTPT' <585.1 °FNominal RCS Operating PressureP' =2235psigOvertemperature T reactor trip setpoint
++K 1=1.1978Overtemperature T reactor trip heatupsetpoint penalty coefficient K 2= 0.03340/
o FOvertemperature T reactor trip depressurization setpoint penalty coefficient K 3= 0.001601/psiTime constants utilized in the lead-lag compensator for T 1= 8 sec. 2= 3 sec.Time constant utilized in the lag compensator for T 3= 0 sec.Time constants utilized in the lead-lag compensator for Tavg 4= 22 sec. 5= 4 sec.Time constant utilized in the measured Tavglag compensator 6= 0 sec.f 1 (I) "positive" breakpoint= 19.0 %I f 1 (I) "negative" breakpoint= N/A*f 1 (I) "positive" slope= 1.769 %T 0/ %I f 1 (I) "negative" slope= N/A**f 1 (I)negative breakpoints and slopes for OTT are less restrictive than the OPT f 2 (I) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits,OPT f 2 (I) limits will result in a reactor trip before OTT f 1 (I)limits are reached. This makes implementation of an OTT f 1 (I) negative breakpoint and slope unnecessary.
++T 0is assumed to be renormalized to 100% RTP following the MURpower uprate.
CNEI-0400-269Page 24of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report 2.9.2Overpower T Setpoint Parameter ValuesParameterNominal ValueNominal Tavg at RTPT" <585.1ºFOverpower T reactor trip setpoint
++K 4=1.0864Overpower Treactor trip penalty K 5=0.02 / °F for increasing Tavg K 5=0.00 / °F for decreasing TavgOverpower T reactor trip heatup setpoint penalty coefficient K 6= 0.001179/°F for T > T
K 6= 0.0 /°F for T <TTime constants utilized in the lead-lag compensator for T 1= 8 sec. 2= 3 sec.Time constant utilized in the lag compensator for T 3= 0 sec.Time constant utilized in the measured T avglag compensator 6= 0 sec.Time constant utilized in the rate-lag controller for T avg 7= 10 sec.f 2 (I) "positive" breakpoint= 35.0 %I f 2 (I) "negative" breakpoint=-35.0 %I f 2 (I) "positive" slope= 7.0 %T 0/ %I f 2 (I) "negative" slope= 7.0 %T 0/ %I++T 0is assumed to be renormalized to 100% RTP following the MURpower uprate.
CNEI-0400-269Page 25of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.10Boron Dilution Mitigation System -BDMS (TS 3.3.9) 2.10.1Reactor Makeup Water Pump combined flow rate limits:Applicable MODELimitMODE380 gpmMODE4 or 570 gpm2.11RCS Pressure, Temperature and Flow DNBLimits(TS 3.4.1)The RCS pressure, temperature and flow limits for DNB are shown in Table 4.2.12Accumulators (TS 3.5.1) 2.12.1Boron concentration limits during MODES1 and 2, and MODE3 with RCS pressure >1000 psi:ParameterApplicable BurnupLimitAccumulator minimumboron concentration.0-200EFPD2,500ppmAccumulator minimumboron concentration.200.1-250EFPD2,500ppmAccumulator minimumboron concentration.250.1-300EFPD2,413ppmAccumulator minimumboron concentration.300.1-350EFPD2,307ppmAccumulator minimumboron concentration.350.1-400EFPD2,226ppmAccumulator minimumboron concentration.400.1-450EFPD2,149ppmAccumulator minimumboron concentration.450.1-500EFPD2,079ppmAccumulator minimumboron concentration.500.1-527EFPD2,004ppmAccumulator maximumboron concentration.0-527EFPD3,075ppm CNEI-0400-269Page 26of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportTable 4Reactor Coolant System DNB Parameters No. OperablePARAMETERINDICATIONCHANNELSLIMITS1. Indicated RCS Average Temperature meter4
< 587.2 ºFmeter3< 586.9 ºFcomputer4< 587.7 ºFcomputer3< 587.5 ºF2. Indicated Pressurizer Pressuremeter4
> 2219.8 psigmeter3> 2222.1 psigcomputer4> 2215.8 psigcomputer3> 2217.5 psig3. RCS Total Flow Rate
> 388,000 gpm CNEI-0400-269Page 27of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.13Refueling Water Storage Tank -RWST (TS 3.5.4) 2.13.1Boron concentration limits during MODES 1, 2, 3, and 4:ParameterLimitRWST minimum boron concentration. 2,700 ppmRWST maximum boron concentration.3,075 ppm2.14Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.14.1Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are storedin the spent fuel pool.ParameterLimitSpent fuel pool minimum boron concentration. 2,700 ppm2.15Refueling Operations -Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for MODE6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that
core Keffremainswithin the MODE6 reactivity requirement of Keff0.95.ParameterLimitMinimum boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.
2,700 ppm CNEI-0400-269Page 28of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.16Standby Shutdown System -(SLC-16.7-9) 2.16.1Minimum boronconcentration limit for the spent fuel poolrequired for Standby Makeup Pump Water Supply. Applicable for MODES1, 2, and 3.ParameterLimitSpent fuel pool minimum boron concentration for TR 16.7-9-3.2,700 ppm2.17Boration SystemsBorated Water Source -Shutdown (SLC 16.9-11) 2.17.1Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODE4 with any RCS cold leg temperature <210
°F, and MODES5 and 6.ParameterLimitBAT minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required to maintain SDM at 68 o F2,000 gallonsBATMinimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11)13,086 gallons (14.9%)NOTE: When cycle burnup is 471EFPD, Figure 6may be used to determine the required BATMinimum Level
.RWSTminimum boron concentration 2,700 ppm Volume of 2,700 ppm boric acid solution required to maintain SDM at68 o F7,000 gallonsRWSTMinimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11)48,500 gallons (8.7%)
CNEI-0400-269Page 29of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits Report2.18Boration Systems Borated Water Source -Operating (SLC 16.9-12) 2.18.1Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODES1, 2, and 3 and MODE4with all RCS cold leg temperatures > 210
°F*.*NOTE: The SLC 16.9-12applicability is down to MODE 4 temperaturesof >210 oF. The minimum volumes calculated support cooldown to 200 oF to satisfy UFSAR Chapter 9 requirements.ParameterLimitBATminimum boron concentration7,000 ppmVolume of 7,000 ppm boric acid solution required to maintain SDM at 210 o F13,500 gallonsBATMinimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 25,200 gallons (45.8%)NOTE: When cycle burnup is 471EFPD,Figure 6may be used to determine the required BATMinimum Level
.RWSTminimum boron concentration 2,700 ppmVolume of 2,700 ppm boric acid solution required to maintain SDM at 210 o F57,107gallonsRWSTMinimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12)98,607 gallons (22.0%)
CNEI-0400-269Page 30of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportFigure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration(Valid When Cycle Burnup is 471EFPD)This figure includes additional volumes listed in SLC 16.9-11 and 16.9-120.05.010.015.020.025.030.035.040.0 45.050.00200400600800100012001400160018002000220024002600BAT Level (% Level)Primary Coolant Boron Concentration (ppmb)Acceptable OperationUnacceptable OperationRCS BoronConcentrationBAT Level(ppm)(%level)0 < 30043.0300 < 50040.0 500 < 70037.0700 < 1000 30.01000 < 130014.9 1300 < 27009.8> 2700 9.8 CNEI-0400-269Page 31of 31Revision 1Catawba 1 Cycle 22 Core Operating Limits ReportAppendix APower Distribution Monitoring FactorsAppendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the Catawba 1 Cycle 22Maneuvering Analysis calculation file, CNC-1553.05-00-0608.Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke and is not included in the Duke internal copiesof the COLR. The Catawba Electrical and Reactor Systems Engineering Section controls this information via computer files and should be contacted if there is a need to access this information. Appendix A is included in the COLR copy transmitted to the NRC.