ML093451632

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Core Operating Limits Report (Colr), Cycle 19, Revision 0, CNEI-0400-190, Inspection of Engineering Instructions, Calculation Number CNC-1553.05-00-0522
ML093451632
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 11/16/2009
From: Hager N
Duke Energy Carolinas, Duke Energy Corp
To:
Office of Nuclear Reactor Regulation
References
CNC-1553.05-00-0522 CNEI-0400-190, Rev 0
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CNEI-0400-190 Page 1 of 32 Revision 0 Catawba Unit 1 Cycle 19 Core Operating Limits Report Revision 0 November 2009 Calculation Number: CNC-1553.05-00-0522 Duke Energy Company QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

CNEI-0400-190 Page 2 of 32 Revision 0 INSPECTION OF ENGINEERING INSTRUCTIONS CATAWBA Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( _______________ ) Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( _______________ ) Inspected By/Date:

MCGUIRE Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( _______________ ) Inspected By/Date:

CNEI-0400-190 Page 3 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and PIP Tracking Revision 0 of the Catawba Unit 1 Cycle 19 COLR contains limits specific to the reload core.

There is no PIP associated with this revision.

Implementation Schedule Revision 0 may become effective any time during No MODE between Cycles 18 and 19 but must become effective prior to entering MODE 6 which starts Cycle 19. The Catawba Unit 1 Cycle 19 COLR will cease to be effective during No MODE between Cycle 19 and 20.

Data files to be Implemented No data files are transmitted as part of this document.

CNEI-0400-190 Page 4 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR 0 November 2009 1-32, Appendix A* C1C19 COLR, Rev. 0

  • Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is included only in the electronic COLR copy sent to the NRC.

CNEI-0400-190 Page 5 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference this report are listed below:

TS COLR COLR Section Technical Specifications COLR Parameter Section Page 2.1.1 Reactor Core Safety Limits RCS Temperature and Pressure 2.1 9 Safety Limits 3.1.1 SDM SDM 2.2 9 3.1.3 Moderator Temperature Coefficient MTC 2.3 11 3.1.4 Rod Group Alignment Limits SDM 2.2 9 3.1.5 Shutdown Bank Insertion Limit SDM 2.2 9 Rod Insertion Limits 2.4 11 3.1.6 Control Bank Insertion Limit SDM 2.2 9 Rod Insertion Limits 2.5 15 3.1.8 Physics Tests Exceptions SDM 2.2 9 3.2.1 Heat Flux Hot Channel Factor FQ 2.6 15 AFD 2.8 21 OTT 2.9 24 Penalty Factors 2.6 17 3.2.2 Nuclear Enthalpy Rise Hot Channel FH 2.7 20 Factor Penalty Factors 2.7 21 3.2.3 Axial Flux Difference AFD 2.8 21 3.3.1 Reactor Trip System Instrumentation OTT 2.9 24 OPT 2.9 25 3.3.9 Boron Dilution Mitigation System Reactor Makeup Water Flow Rate 2.10 26 3.4.1 RCS Pressure, Temperature and RCS Pressure, Temperature and 2.11 26 Flow limits for DNB Flow 3.5.1 Accumulators Max and Min Boron Conc. 2.12 26 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc. 2.13 26 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 28 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 28 Concentration 5.6.5 Core Operating Limits Report Analytical Methods 1.1 6 (COLR)

The Selected License Commitments that reference this report are listed below:

SLC COLR COLR Section Selected Licensing Commitment COLR Parameter Section Page 16.7-9 Standby Shutdown System Standby Makeup Pump Water 2.16 29 Supply 16.9-11 Boration Systems - Borated Water Borated Water Volume and Conc. 2.17 29 Source - Shutdown for BAT/RWST 16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc. 2.18 30 Source - Operating for BAT/RWST

CNEI-0400-190 Page 6 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits as specified in Technical Specification 5.6.5, are as follows. All methods have been previously reviewed and approved by the NRC.

1. WCAP-9272-P-A, WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY, (W Proprietary).

Revision 0 Report Date: July 1985 Not Used for C1C19

2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, " (W Proprietary).

Revision 0 Report Date: August 1985

3. WCAP-10266-P-A, THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE, (W Proprietary).

Revision 2 Report Date: March 1987 Not Used for C1C19

4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, Code Qualification Document for Best-Estimate Loss of Coolant Analysis, (W Proprietary).

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 Recirculating Steam Generator Plants, (B&W Proprietary).

Revision 1 SER Date: January 22, 1991 Revision 2 SER Dates: August 22, 1996 and November 26, 1996.

Revision 3 SER Date: June 15, 1994.

Not Used for C1C19

CNEI-0400-190 Page 7 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 1.1 Analytical Methods (continued)

6. DPC-NE-3000-PA, Thermal-Hydraulic Transient Analysis Methodology, (DPC Proprietary).

Revision 3 SER Date: September 24, 2003

7. DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).

Revision 0 Report Date: November 15, 1991, republished December 2000

8. DPC-NE-3002-A, "UFSAR Chapter 15 System Transient Analysis Methodology".

Revision 4 SER Date: April 6, 2001

9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).

Revision 1 SER Date: February 20, 1997

10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).

Revision 3 SER Date: September 16, 2002

11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).

Revision 0 SER Date: April 3, 1995 Not Used for C1C19

12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report, (DPC Proprietary).

Revision 2 SER Date: December 18, 2002

13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."

Revision 1 SER Date: April 26, 1996 Not Used for C1C19

CNEI-0400-190 Page 8 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision 2 SER Date: June 24, 2003

15. DPC-NE-2011PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).

Revision 1 SER Date: October 1, 2002

16. DPC-NE-1005-P-A, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX", (DPC Proprietary).

Revision 1 SER Date: November 12, 2008

17. BAW-10231P-A, "COPERNIC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)

Revision 1 SER Date: January 14, 2004 Not Used for C1C19

CNEI-0400-190 Page 9 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.0 Operating Limits The cycle-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 in Section 1.1.

2.1 Reactor Core Safety Limits (TS 2.1.1)

The Reactor Core Safety Limits are shown in Figure 1.

2.2 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.2.1 For TS 3.1.1, SDM shall be greater than or equal to 1.3% K/K in MODE 2 with Keff < 1.0 and in MODES 3 and 4.

2.2.2 For TS 3.1.1, SDM shall be greater than or equal to 1.0% K/K in MODE 5.

2.2.3 For TS 3.1.4, SDM shall be greater than or equal to 1.3% K/K in MODE 1 and MODE 2.

2.2.4 For TS 3.1.5, SDM shall be greater than or equal to 1.3% K/K in MODE 1 and MODE 2 with any control bank not fully inserted.

2.2.5 For TS 3.1.6, SDM shall be greater than or equal to 1.3% K/K in MODE 1 and MODE 2 with Keff > 1.0.

2.2.6 For TS 3.1.8, SDM shall be greater than or equal to 1.3% K/K in MODE 2 during PHYSICS TESTS.

CNEI-0400-190 Page 10 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 640 2400 psia RCS Tavg (°F) 630 2280 psia 620 2100 psia 610 1945 psia 600 590 ACCEPTABLE OPERATION 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power

CNEI-0400-190 Page 11 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:

The MTC shall be less positive than the upper limits shown in Figure 2. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 K/K/°F.

The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 K/K/°F lower MTC limit.

2.3.2 The 300 ppm MTC Surveillance Limit is:

The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 K/K/°F.

2.3.3 The 60 PPM MTC Surveillance Limit is:

The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to

-4.125E-04 K/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) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps except under the conditions listed in Section 2.4.2. Shutdown banks are withdrawn in sequence and with no overlap.

2.4.2 Shutdown banks may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.

CNEI-0400-190 Page 12 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation Moderator Temperature Coefficient 0.8 0.7 0.6 0.5 (1.0E-04 DK/K/F)

Acceptable Operation 0.4 0.3 0.2 0.1 0.0 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 1 ROD manual for details.

CNEI-0400-190 Page 13 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231) 231 220 200 Fully Withdrawn Rod Insertion Position (Steps Withdrawn)

(Minimum = 222) 180 Control Bank B (100%, 161) 160 (0%, 163) 140 Control Bank C 120 100 80 Control Bank D 60 40 (0%, 47) 20 Fully Inserted (30%, 0) 0 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power The 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 CC RIL = 2.3(P) +47 {0 < P < 76.1} for CC RIL = 222 {76.1 < P < 100}

Bank CB RIL = 2.3(P) +163 {0 < P < 25.7} for CB RIL = 222 {25.7 < P < 100}

where P = %Rated Thermal Power NOTES: (1) Compliance with Technical Specification 3.1.3 may require rod withdrawal limits. Refer to the Unit 1 ROD manual for details.

(2) Anytime any shutdown bank or control banks A, B, or C are inserted below 222 steps withdrawn, control bank D insertion is limited to > 200 steps withdrawn (see Sections 2.4.2 and 2.5.2)

CNEI-0400-190 Page 14 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Fully Withdrawn at 223 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Start 0 223 116 0 Start 0 222 222 Stop 106 0 223 223 Stop 107 0 222 222 116 0 Start 223 223 116 0 Start 222 222 222 Stop 106 223 223 223 Stop 107 Fully Withdrawn at 224 Steps Fully Withdrawn at 225 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 224 Stop 108 0 0 225 Stop 109 0 0 224 116 0 Start 0 225 116 0 Start 0 224 224 Stop 108 0 225 225 Stop 109 0 224 224 116 0 Start 225 225 116 0 Start 224 224 224 Stop 108 225 225 225 Stop 109 Fully Withdrawn at 226 Steps Fully Withdrawn at 227 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 226 Stop 110 0 0 227 Stop 111 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop 111 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 Stop 111 Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 0 Start 0 228 228 Stop 112 0 229 229 Stop 113 0 228 228 116 0 Start 229 229 116 0 Start 228 228 228 Stop 112 229 229 229 Stop 113 Fully Withdrawn at 230 Steps Fully Withdrawn at 231 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 0 Start 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Start 230 230 230 Stop 114 231 231 231 Stop 115

CNEI-0400-190 Page 15 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.5 Control 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 except under the conditions listed in Section 2.5.2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.

2.5.2 Control banks A, B, or C may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.

2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F QRTP *K(Z)/P for P > 0.5 RTP F Q

  • K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,Y,Z) shall be increased by 3.0% 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 FQ surveillance limits as defined for COLR Sections 2.6.5 and 2.6.6.

2.6.2 FRTP Q = 2.60 x K(BU) 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height. K(Z) for Westinghouse RFA fuel is provided in Figure 4.

2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. K(BU) for Westinghouse RFA fuel is 1.0 at all burnups.

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:

D L FQ(X,Y,Z)

  • MQ(X,Y,Z) 2.6.5 [FQ(X,Y,Z)]OP = UMT
  • TILT

CNEI-0400-190 Page 16 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report where:

[ FQL (X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

OP FQL (X,Y,Z) includes allowances for calculational and measurement uncertainties.

FQD (X,Y,Z) = Design power distribution for FQ. FQD (X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.

MQ(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.

UMT = Total Peak Measurement Uncertainty. (UMT = 1.05)

MT = Engineering Hot Channel Factor. (MT = 1.03). The manufacturing tolerances for RFA fuel is implicitly included in the FQ LOCA surveillance limits (MQ).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

D L RPS FQ(X,Y,Z)

  • MC(X,Y,Z) 2.6.6 [FQ(X,Y,Z)] = UMT
  • TILT where:

L

[FQ(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures the FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR L

limits. [FQ(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.

D D FQ(X,Y,Z) = Design power distributions for FQ. FQ(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in

CNEI-0400-190 Page 17 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Appendix Table A-4 for power escalation testing during initial startup operations.

MC(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. MC(X,Y,Z) is provided in Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operations.

MT = Engineering Hot Channel Factor. (MT = 1.03). The manufacturing tolerances for RFA fuel is implicitly included in the FQ RPS surveillance limits (MC).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.7 KSLOPE = 0.0725 where:

KSLOPE = the adjustment to the K1 value from OTT trip setpoint required to RPS compensate for each 1% that FQM (X,Y,Z) exceeds FQL (X,Y,Z) .

2.6.8 FQ(X,Y,Z) Penalty Factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

CNEI-0400-190 Page 18 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel 1.200 (0.0, 1.00) (4.0, 1.00) 1.000 (12.0, 0.9615)

(4.0, 0.9615) 0.800 K(Z) 0.600 0.400 Core Height (ft) K(Z) 0.0 1.000

<4 1.000 0.200

>4 0.9615 12.0 0.9615 0.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

CNEI-0400-190 Page 19 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FH(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup FQ(X,Y,Z) FH(X,Y)

(EFPD) Penalty Factor(%) Penalty Factor (%)

4 2.00 2.00 12 2.00 2.00 25 2.00 2.00 50 2.00 2.00 75 2.00 2.00 100 2.00 2.00 125 2.00 2.00 150 2.00 2.00 175 2.00 2.00 200 2.00 2.00 225 2.00 2.00 250 2.00 2.00 275 2.00 2.00 300 2.00 2.00 325 2.00 2.00 350 2.00 2.00 375 2.00 2.00 400 2.00 2.00 425 2.00 2.00 450 2.00 2.00 451 2.00 2.00 476 2.00 2.00 488 2.00 2.00 503 2.00 2.00 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 FQ(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-0400-190 Page 20 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FH(X,Y) (TS 3.2.2)

The FH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.

1 2.7.1 [FLH (X, Y)] LCO = MARP (X,Y)

  • 1.0 + * (1.0 - P)

RRH where:

[FLH (X, Y)] LCO is defined as the steady-state, maximum allowed radial peak and 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.

Thermal Power P =

Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, FMH (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.

SURV FDH (X, Y)

  • M H (X, Y) 2.7.2 [ FLH (X,Y)] =

UMR

  • TILT where:

SURV

[ FLH (X,Y)] = Cycle dependent maximum allowable design peaking factor that ensures that the FH(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

SURV FLH (X,Y) includes allowances for calculational and measurement uncertainty.

D D FH (X,Y) = Design power distribution for FH. FH (X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.

CNEI-0400-190 Page 21 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report MH(X,Y) = The margin remaining in core location X,Y relative to the Operational DNB limits in the transient power distribution.

MH(X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for 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% that the measured radial peak, FMH (X,Y) exceeds its limit. (0 < P < 1.0) 2.7.4 TRH = 0.04 where:

TRH = Reduction in OTT K1 setpoint required to compensate for each 1% that the measured radial peak, FMH (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.

2.8 Axial Flux Difference - AFD (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.

CNEI-0400-190 Page 22 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

RFA Fuel MARPs 100% Full Power Core Height Axial Peak (ft) 1.05 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.8092 1.8553 1.9489 1.9953 1.9741 2.1073 2.0498 2.009 1.9333 1.8625 1.778 1.3151 1.2461 1.20 1.8102 1.854 1.9401 1.9953 1.9741 2.1073 2.0191 1.9775 1.9009 1.8306 1.7852 1.3007 1.2235 2.40 1.8093 1.8525 1.9312 1.9779 1.9741 2.0735 1.9953 1.9519 1.876 1.8054 1.732 1.4633 1.4616 3.60 1.8098 1.8514 1.9204 1.9641 1.9741 2.0495 1.9656 1.9258 1.8524 1.7855 1.6996 1.4675 1.3874 4.80 1.8097 1.8514 1.9058 1.9449 1.9741 2.0059 1.9441 1.9233 1.8538 1.7836 1.6714 1.2987 1.2579 6.00 1.8097 1.8514 1.8921 1.9212 1.9455 1.9336 1.8798 1.8625 1.8024 1.7472 1.6705 1.3293 1.2602 7.20 1.807 1.8438 1.8716 1.893 1.8872 1.8723 1.8094 1.7866 1.7332 1.6812 1.5982 1.2871 1.2195 8.40 1.8073 1.8319 1.8452 1.8571 1.8156 1.795 1.7359 1.7089 1.6544 1.601 1.5127 1.2182 1.1578 9.60 1.8072 1.8102 1.8093 1.7913 1.7375 1.7182 1.6572 1.6347 1.5808 1.5301 1.4444 1.1431 1.0914 10.80 1.798 1.7868 1.7611 1.7163 1.6538 1.6315 1.5743 1.5573 1.5088 1.4624 1.3832 1.1009 1.047 11.40 1.7892 1.7652 1.725 1.6645 1.6057 1.5826 1.5289 1.5098 1.4637 1.4218 1.3458 1.067 1.0142

CNEI-0400-190 Page 23 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-20, 100) (+10, 100) 100 Unacceptable Operation Unacceptable Operation 90 80 Percent of Rated Thermal Power 70 Acceptable Operation 60 50

(-36, 50) (+21, 50) 40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta I)

NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to the Unit 1 ROD manual for operational AFD limits.

CNEI-0400-190 Page 24 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature T Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' < 585.1 °F Nominal RCS Operating Pressure P' = 2235 psig Overtemperature T reactor trip setpoint K1 = 1.1978 Overtemperature T reactor trip heatup setpoint K2 = 0.03340/oF penalty coefficient Overtemperature T reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator 1 = 8 sec.

for T 2 = 3 sec.

Time constant utilized in the lag compensator for T 3 = 0 sec.

Time constants utilized in the lead-lag compensator 4 = 22 sec.

for Tavg 5 = 4 sec.

Time constant utilized in the measured Tavg lag 6 = 0 sec.

compensator f1(I) "positive" breakpoint = 19.0 %I f1(I) "negative" breakpoint = N/A*

f1(I) "positive" slope = 1.769 %T0/ %I f1(I) "negative" slope = N/A*

  • The f1(I) negative breakpoints and slopes for OTT are less restrictive than the OPT f2(I) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits the OPT f2(I) limits will result in a reactor trip before the OTT f1(I) limits are reached. This makes implementation of an OTT f1(I) negative breakpoint and slope unnecessary.

CNEI-0400-190 Page 25 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.9.2 Overpower T Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T" < 585.1 ºF Overpower T reactor trip setpoint K4 = 1.0864 Overpower T reactor trip penalty K5 = 0.02 / °F for increasing Tavg K5 = 0.00 / °F for decreasing Tavg Overpower T reactor trip heatup setpoint K6 = 0.001179/oF for T > T

penalty coefficient (for T>T) K6 = 0.0 /°F for T < T

Time constants utilized in the lead-lag 1 = 8 sec.

compensator for T 2 = 3 sec.

Time constant utilized in the lag 3 = 0 sec.

compensator for T Time constant utilized in the measured Tavg 6 = 0 sec.

lag compensator Time constant utilized in the rate-lag 7 = 10 sec.

controller for Tavg f2(I) "positive" breakpoint = 35.0 %I f2(I) "negative" breakpoint = -35.0 %I f2(I) "positive" slope = 7.0 %T0/ %I f2(I) "negative" slope = 7.0 %T0/ %I

CNEI-0400-190 Page 26 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.10 Boron Dilution Mitigation System - BDMS (TS 3.3.9) 2.10.1 Reactor Makeup Water Pump combined flow rate limits:

Applicable MODE Limit MODE 3 < 150 gpm MODE 4 or 5 < 70 gpm 2.11 RCS Pressure, Temperature and Flow DNB Limits (TS 3.4.1)

The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure >1000 psi:

Parameter Limit Accumulator minimum boron concentration. 2,500 ppm Accumulator maximum boron concentration. 3,075 ppm 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 Boron concentration limits during MODES 1, 2, 3, and 4:

Parameter Limit RWST minimum boron concentration. 2,700 ppm RWST maximum boron concentration. 3,075 ppm

CNEI-0400-190 Page 27 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable PARAMETER INDICATION CHANNELS LIMITS

1. Indicated RCS Average Temperature meter 4 < 587.2 ºF meter 3 < 586.9 ºF computer 4 < 587.7 ºF computer 3 < 587.5 ºF
2. Indicated Pressurizer Pressure meter 4 > 2219.8 psig meter 3 > 2222.1 psig computer 4 > 2215.8 psig computer 3 > 2217.5 psig
3. RCS Total Flow Rate > 388,000 gpm

CNEI-0400-190 Page 28 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.14.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.

Parameter Limit Spent fuel pool minimum boron concentration. 2,700 ppm 2.15 Refueling Operations - Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for MODE 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the MODE 6 reactivity requirement of Keff <

0.95.

Parameter Limit Minimum Boron concentration of the Reactor Coolant 2,700 ppm System, the refueling canal, and the refueling cavity.

CNEI-0400-190 Page 29 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.16 Standby Shutdown System - (SLC-16.7-9) 2.16.1 Minimum boron concentration limit for the spent fuel pool required for Standby Makeup Pump Water Supply. Applicable for MODES 1, 2, and 3.

Parameter Limit Spent fuel pool minimum boron concentration for TR 2,700 ppm 16.7-9.3.

2.17 Boration Systems Borated Water Source - Shutdown (SLC 16.9-11) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODE 4 with any RCS cold leg temperature < 210OF, and MODES 5 and 6.

Parameter Limit BAT minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required 2,000 gallons to maintain SDM at 68oF BAT Minimum Shutdown Volume (Includes the 13,086 gallons additional volumes listed in SLC 16.9-11) (14.9%)

NOTE: When cycle burnup is > 480 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.

RWST minimum boron concentration 2,700 ppm Volume of 2,700 ppm boric acid solution required 7,000 gallons to maintain SDM at 68 oF RWST Minimum Shutdown Volume (Includes the 48,500 gallons additional volumes listed in SLC 16.9-11) (8.7%)

CNEI-0400-190 Page 30 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report 2.18 Boration Systems Borated Water Source - Operating (SLC 16.9-12) 2.18.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODES 1, 2, and 3 and MODE 4 with all RCS cold leg temperatures > 210OF.

Parameter Limit BAT minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required 13,500 gallons to maintain SDM at 210oF BAT Minimum Shutdown Volume (Includes the 25,200 gallons additional volumes listed in SLC 16.9-12) (45.8%)

NOTE: When cycle burnup is > 480 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.

RWST minimum boron concentration 2,700 ppm Volume of 2,700 ppm boric acid solution required 57,107 gallons to maintain SDM at 210 oF RWST Minimum Shutdown Volume (Includes the 98,607 gallons additional volumes listed in SLC 16.9-12) (22.0%)

CNEI-0400-190 Page 31 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 480 EFPD)

This figure includes additional volumes listed in SLC 16.9 16.9-11 11 and 16.9-12 16.9 50.0 RCS Boron 45.0 Concentration BAT Level (ppm) (%level) 40.0 0 < 300 43.0 300 < 500 40.0 35.0 500 < 700 37.0 700 < 1000 30.0 BAT Level (% Level) 30.0 1000 < 1300 14.9 1300 < 2700 9.8

> 2700 9.8 25.0 Unacceptable 20.0 Operation Acceptable Operation 15.0 10.0 5.0 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)

CNEI-0400-190 Page 32 of 32 Revision 0 Catawba 1 Cycle 19 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke and is not included in the Duke internal copies of the COLR. The Catawba Reactor and Electrical 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.

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