ML021550252
| ML021550252 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/30/2002 |
| From: | Abbott J Duke Power Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CNEI-0400-24, Rev 22 | |
| Download: ML021550252 (32) | |
Text
CNEI-0400-24 Page 2 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 22 Revision 22 of the Catawba Unit 1 COLR contains limits specific to the Catawba 1 Cycle 14 core and may become effective any time during the NO MODE between Cycles 13 and 14.
This revision must become effective prior to entering MODE 6 which starts Cycle 14.
CNEI-0400-24 Page 3 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report REVISION LOG Revision EI Date Pages Affected COLR 0 - 1 Superceded N/A C1C07 2 - 5 Superceded N/A C1C08 6 - 8 Superceded N/A C1C09 9 - 11 Superceded N/A C1C10 12 - 14 Superceded N/A C1C11 15 - 17 Superceded N/A C1C12 18 October 2000 1 - 26 Appendix A C1C13 (Orig. Issue) 19 February 2001 1-4, 25, 26 C1C13 (Revision) 20 September 2001 1-4, 25, 26 C1C13 (Revision) 21 September 2001 1-4, 25, 26a, 26b C1C13 (Revision) 22 April 2002 ALL C1C14
CNEI-0400-24 Page 4 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report INSERTION SHEET FOR REVISION 22 Remove pages Insert Rev. 22 pages Pages 1-26b Appendix A*, 1-268 Pages 1-31 Appendix A*, 1-275
- Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is only included in the COLR copy sent to the NRC.
CNEI-0400-24 Page 5 of 31 Revision 22 Catawba 1 Cycle 14 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 Section Technical Specifications COLR Parameter COLR Section COL R
Page 3.1.1 Shutdown Margin Shutdown Margin 2.1 9
3.1.3 Moderator Temperature Coefficient MTC 2.2 9
3.1.4 Rod Group Alignment Limits Shutdown Margin 2.1 9
3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.1 9
Rod Insertion Limits 2.3 10 3.1.6 Control Bank Insertion Limit Shutdown Margin 2.1 9
Rod Insertion Limits 2.4 10 3.1.8 Physics Tests Exceptions Shutdown Margin 2.1 9
3.2.1 Heat Flux Hot Channel Factor FQ 2.5 14 AFD 2.7 21 OTT 2.8 24 Penalty Factors 2.5 16 3.2.2 Nuclear Enthalpy Rise Hot Channel FH 2.6 20 Factor Penalty Factors 2.6 21 3.2.3 Axial Flux Difference AFD 2.7 21 3.3.1 Reactor Trip System Instrumentation OTT 2.8 24 OPT 2.8 25 3.3.9 Boron Dilution Mitigation System Reactor Makeup Water Flow Rate 2.9 26 3.5.1 Accumulators Max and Min Boron Conc.
2.10 26 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc..
2.11 26 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.12 27 3.9.1 Refueling Operations - Boron Concentration Min Boron Concentration 2.13 27 3.9.2 Refueling Operations - Nuclear Instrumentation Reactor Makeup Water Flow Rate 2.14 27 The Selected License Commitments that reference this report are listed below:
SLC Section Selected Licensing Commitment COLR Parameter COLR Section COL R
Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water Supply 2.15 28 16.9-11 Boration Systems - Borated Water Source - Shutdown Borated Water Volume and Conc.
for BAT/RWST 2.16 28 16.9-12 Boration Systems - Borated Water Source - Operating Borated Water Volume and Conc.
for BAT/RWST 2.17 29
CNEI-0400-24 Page 6 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC are as follows.
- 1. WCAP-9272-P-A, WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY, (W Proprietary).
Revision 0 Report Date: July 1985 Not Used for C1C14
- 2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, " (W Proprietary).
Revision 0 Report Date: August 1985 Note: Amendments to this report are included in Ref. 12.
- 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 C1C14
- 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 Recalculating 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 C1C14
CNEI-0400-24 Page 7 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 1.1 Analytical Methods (continued)
Revision 2 SER Date: October 14, 1998
- 7. DPC-NE-3001PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision 0 Report Date: November 1991
Revision 3 SER Date: February 5, 1999
- 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 1 SER Date: November 7, 1996
- 11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision 0 SER Date: April 3, 1995
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report, (DPC Proprietary).
Revision 0 SER Date: September 22, 1999
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."
Revision 1 SER Date: April 26, 1996
CNEI-0400-24 Page 8 of 31 Revision 22 Catawba 1 Cycle 14 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 0 Report Date: June 1985
- 15. DPC-NE-2011PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision 0 Report Date: March 1990
CNEI-0400-24 Page 9 of 31 Revision 22 Catawba 1 Cycle 14 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 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.1.1 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.3% K/K in mode 2 with Keff < 1.0 and in modes 3 and 4.
2.1.2 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.0% K/K in mode 5.
2.1.3 For TS 3.1.4, shutdown margin shall be greater than or equal to 1.3% K/K in mode 1 and mode 2.
2.1.4 For TS 3.1.5, shutdown margin shall be greater than or equal to 1.3% K/K in mode 1 and mode 2 with any control bank not fully inserted.
2.1.5 For TS 3.1.6, shutdown margin shall be greater than or equal to 1.3% K/K in mode 1 and mode 2 with Keff > 1.0.
2.1.6 For TS 3.1.8, shutdown margin shall be greater than or equal to 1.3% K/K in mode 2 during Physics Testing.
2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the upper limits shown in Figure 1. 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 -4.1E-04 K/K/°F lower MTC limit.
2.2.2 The 300 ppm MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.2E-04 K/K/°F.
CNEI-0400-24 Page 10 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.2.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-3.85E-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) 2.3 Shutdown Bank Insertion Limit (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 226 steps. Shutdown banks are withdrawn in sequence and with no overlap.
2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.
CNEI-0400-24 Page 11 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Moderator Temperature Coefficient (1.0E-04 DK/K/F)
Unacceptable Operation Acceptable Operation NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 1 ROD manual for details.
CNEI-0400-24 Page 12 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power 0
20 40 60 80 100 120 140 160 180 200 220 0
10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power Rod Insertion Position (Steps Withdrawn)
(29.6%, 231)
(80.0%, 231)
Fully Withdrawn (Maximum = 231) 231 (Control Bank B)
(Control Bank C)
(Control Bank D)
(0%, 163)
(0%, 47)
(30%, 0)
(100%, 161)
Fully Withdrawn (Minimum = 226)
NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit 1 ROD manual for details.
CNEI-0400-24 Page 13 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence 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 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 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 Fully Withdrawn at 226 Steps Fully Withdrawn at 227 Steps Fully Withdrawn at 230 Steps Fully Withdrawn at 231 Steps Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps
CNEI-0400-24 Page 14 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.5 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.5.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:
F RTP Q
- K(Z)/P for P > 0.5 F RTP 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% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.5.5 and 2.5.6.
2.5.2 F RTP Q
= 2.50 x K(BU) 2.5.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height. K(Z) for MkBW fuel is provided in Figure 3, and the K(Z) for Westinghouse RFA fuel is provided in Figure 4.
2.5.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. K(BU) for both MkBW fuel and 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:
2.5.5 [F L
Q(X,Y,Z)]OP =
F D
Q(X,Y,Z)
- MQ(X,Y,Z)
UMT
- TILT where:
[
L Q
F (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.
L Q
F (X,Y,Z)
OP includes allowances for calculational and measurement uncertainties.
CNEI-0400-24 Page 15 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report D
Q F (X,Y,Z) = Design power distribution for FQ.
D Q
F (X,Y,Z) is provided in Table 4, Appendix A, for normal operating conditions and in Table 7, Appendix A 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 Table 4, Appendix A for normal operating conditions and in Table 7, Appendix A for 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) 2.5.6 [F L
Q(X,Y,Z)]
RPS =
F D
Q(X,Y,Z)
- MC(X,Y,Z)
UMT
- TILT where:
[F L
Q(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPRT limits. [F L
Q(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.
F D
Q(X,Y,Z) = Design power distributions for FQ. F D
Q(X,Y,Z) is provided in Table 4, Appendix A for normal operating conditions and in Table 7, Appendix A 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 Table 5, Appendix A for normal operating conditions and in Table 8, Appendix A for power escalation testing during initial startup operations.
UMT = Measurement Uncertainty (UMT = 1.05)
CNEI-0400-24 Page 16 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 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) 2.5.7 KSLOPE = 0.0725 where:
KSLOPE = the adjustment to the K1 value from OTT trip setpoint required to compensate for each 1% that M
Q F
(X,Y,Z) exceeds L
Q F (X,Y,Z)
RPS.
2.5.8 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-0400-24 Page 17 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MkBW Fuel 0.000 0.200 0.400 0.600 0.800 1.000 1.200 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
K(Z)
(0.0, 1.00)
(6.0, 1.00)
(12.0, 1.00)
Core Height (ft)
K(Z) 0.0 1.000 6.0 1.000 12.0 1.000
CNEI-0400-24 Page 18 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA Fuel 0.000 0.200 0.400 0.600 0.800 1.000 1.200 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
K(Z)
(0.0, 1.00)
(6.0, 1.00)
(12.0, 1.00)
Core Height (ft)
K(Z) 0.0 1.000 6.0 1.000 12.0 1.000
CNEI-0400-24 Page 19 of 31 Revision 22 Catawba 1 Cycle 14 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 2.21 2.00 25 2.08 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 2.00 400 2.00 2.00 500 2.00 2.00 530 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-0400-24 Page 20 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.6 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 is defined by the following relationship.
2.6.1 LCO L
H Y)]
(X,
[F
= MARP (X,Y)
- 1.0 + 1 RRH * (1.0 - P) where:
LCO L
H Y)]
(X,
[F is defined as the steady-state, maximum allowed radial peak.
LCO L
H Y)]
(X,
[F 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 Power Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% that the 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.
2.6.2 [
L H
F(X,Y)]
SURV = F (X,Y)
M (X,Y)
UMR TILT H
D H
x x
where:
[
L H
F(X,Y)]
SURV = 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.
L H
F(X,Y)
SURV includes allowances for calculational and measurement uncertainty.
F D
H (X,Y) = Design power distribution for FH. F D
H (X,Y) is provided in Table 6, Appendix A for normal operation and in Table 9,
CNEI-0400-24 Page 21 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Appendix A for power escalation testing during initial startup operation.
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 Table 6, Appendix A for normal operation and in Table 9, Appendix A for power escalation testing during initial startup operation.
UMR = Uncertainty value for measured radial peaks. 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)
NOTE:
[F L
H(X,Y)]SURV is the parameter identified as [FH(X,Y)]MAX in DPC-NE-2011PA.
2.6.3 RRH = 3.34 where:
RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, M
H F(X,Y) exceeds its limit. (0 < P < 1.0) 2.6.4 TRH = 0.04 where:
TRH = Reduction in OTT K1 setpoint required to compensate for each 1% that the measured radial peak, FH(X,Y) exceeds its limit.
2.6.5 FH(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.
2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
CNEI-0400-24 Page 22 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)
MkBW and RFA Fuel MARPs 100% Full Power Height (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 1.678 1.708 1.772 1.829 1.878 1.922 1.852 1.798 1.714 1.636 1.535 1.211 1.147 1.20 1.675 1.706 1.766 1.821 1.867 1.886 1.829 1.806 1.731 1.655 1.540 1.182 1.117 2.40 1.679 1.708 1.763 1.815 1.853 1.841 1.786 1.769 1.711 1.655 1.557 1.168 1.106 3.60 1.682 1.709 1.760 1.804 1.812 1.797 1.743 1.722 1.669 1.619 1.556 1.202 1.131 4.80 1.684 1.708 1.754 1.792 1.766 1.750 1.699 1.681 1.630 1.581 1.516 1.232 1.186 6.00 1.686 1.708 1.745 1.761 1.715 1.703 1.654 1.638 1.590 1.544 1.476 1.206 1.156 7.20 1.686 1.704 1.733 1.714 1.666 1.649 1.603 1.587 1.542 1.503 1.438 1.177 1.127 8.40 1.681 1.692 1.702 1.660 1.612 1.595 1.549 1.537 1.494 1.454 1.387 1.145 1.100 9.60 1.673 1.677 1.651 1.601 1.558 1.544 1.502 1.491 1.450 1.413 1.350 1.121 1.076 10.80 1.662 1.649 1.603 1.550 1.503 1.491 1.448 1.441 1.404 1.369 1.307 1.086 1.043 12.00 1.636 1.608 1.553 1.505 1.456 1.446 1.408 1.403 1.370 1.340 1.286 1.072 1.027 Axial Peak
CNEI-0400-24 Page 23 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 0
10 20 30 40 50 60 70 80 90 100
-50
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I)
Percent of Rated Thermal Power
(+10, 100)
(-20, 100)
(-36, 50)
(+21, 50)
Acceptable Operation Unacceptable Operation Unacceptable Operation 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-0400-24 Page 24 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.8 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.8.1 Overtemperature T Setpoint Parameter Values Parameter Nominal Value Overtemperature T reactor trip setpoint K1 = 1.1978 Overtemperature T reactor trip heatup setpoint penalty coefficient K2 = 0.03340/oF Overtemperature T reactor trip depressurization setpoint penalty coefficient K3 = 0.001601/psi Time 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 Tavg lag compensator 6 = 0 sec.
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" breakpoint and the f1(I) "negative" slope are not applicable since the f1(I) function is not required below the f1(I) "positive" breakpoint of 19.0% I.
CNEI-0400-24 Page 25 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.8.2 Overpower T Setpoint Parameter Values Parameter Nominal Value Overpower T reactor trip setpoint K4 = 1.0864 Overpower T reactor trip heatup setpoint penalty coefficient (for T>T)
K6 = 0.001179/oF Time 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 Tavg lag compensator 6 = 0 sec.
Time constant utilized in the rate-lag controller for Tavg 7 = 10 sec.
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-0400-24 Page 26 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flow rate limits:
Applicable Mode Limit Mode 3
< 150 gpm Mode 4 or 5
< 70 gpm 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure
>1000 psi:
Parameter Limit Cold Leg Accumulator minimum boron concentration.
2,500 ppm Cold Leg Accumulator maximum boron concentration.
2,975 ppm 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 Boron concentration limits during modes 1, 2, 3, and 4:
Parameter Limit Refueling Water Storage Tank minimum boron concentration.
2,700 ppm Refueling Water Storage Tank maximum boron concentration.
2,975 ppm
CNEI-0400-24 Page 27 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.12 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.12.1 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 2.13 Refueling Operations - Boron Concentration (TS 3.9.1) 2.13.1 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 System, the refueling canal, and the refueling cavity.
2,700 ppm 2.14 Refueling Operations - Instrumentation (TS 3.9.2) 2.14.1 Reactor Makeup Water Pump Flow rate Limit:
Applicable Mode Limit Mode 6
< 70 gpm
CNEI-0400-24 Page 28 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.15 Standby Shutdown System - Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.15.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes 1, 2, and 3.
Parameter Limit Spent fuel pool minimum boron concentration for surveillance SLC-16.7-9.3.
2,700 ppm 2.16 Borated Water Source - Shutdown (SLC 16.9-11) 2.16.1 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 < 285OF, and Modes 5 and 6.
Parameter Limit Boric Acid Tank minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required to maintain SDM at 68oF 2000 gallons Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 13,086 gallons (14.9%)
NOTE: When cycle burnup is > 470 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration 2,700 ppm Volume of 2,700 ppm boric acid solution required to maintain SDM of 68 oF 7,000 gallons Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 48,500 gallons (8.7%)
CNEI-0400-24 Page 29 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report 2.17 Borated Water Source - Operating (SLC 16.9-12) 2.17.1 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 > 285OF.
Parameter Limit Boric Acid Tank minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required to maintain SDM at 285oF 13,500 gallons Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 25,200 gallons (45.8%)
NOTE: When cycle burnup is > 470 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration 2,700 ppm Volume of 2,700 ppm boric acid solution required to maintain SDM of 68 oF 57,107 gallons Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 98,607 gallons (22.0%)
CNEI-0400-24 Page 30 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 470 EFPD)
This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)
BAT Level (% Level)
Acceptable Operation Unacceptable Operation RCS Boron Concentration BAT Level (ppm)
(%level) 0 < 300 43.0 300 < 500 40.0 500 < 700 37.0 700 < 1000 30.0 1000 < 1300 14.9 1300 < 2700 9.8
> 2700 9.8
CNEI-0400-24 Page 31 of 31 Revision 22 Catawba 1 Cycle 14 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.
CNEI-0400-24 Page 32 of 31 Revision 22 Catawba 1 Cycle 14 Core Operating Limits Report Appendix A Tables Table 4 FqD Normal Operation Table 5 Mc(X,Y,Z)
Normal Operation Table 6 FDH Normal Operation Table 7 FqD Power Escalation Table 8 Mc(X,Y,Z)
Power Escalation Table 9 FDH Power Escalation