ML13134A046
| ML13134A046 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/30/2013 |
| From: | Henderson K Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNEI-0400-248, Rev 0 CNC-1553.05-00-0582 | |
| Download: ML13134A046 (34) | |
Text
Kelvin Henderson DUKE ENERGY, Vice President Catawba Nuclear Station 803-701-4251 Duke Energy CNO1VP 1 4800 Concord Rd.
York, SC 29745 April 30, 2013 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station Unit 1 CNS Docket Nos. 50-413 Core Operating Limits Report (COLR)
Catawba Nuclear Station (CNS) Unit 1 Cycle 21, Revision 0 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy and electronic copy of the Core Operating Limits Report for Catawba Unit 1 Cycle 21. This COLR is being submitted to update the limits of the Cycle 21 reload core.
The electronic copy of this COLR is included with the letter. The electronic copy includes the power distribution monitoring factors.
This letter, attached COLR, and computer disk do not contain any new commitments.
Please direct any questions or concerns to Randy Hart at (803) 701-3622.
Sincerely, Kelvin Henderson Attachments www.duke-energy.com
U.S. Nuclear Regulatory Commission April 30, 2013 Page 2 xc w/Attachment only:
U.S. Nuclear Regulatory Commission V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. Kim, NRC Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 0-8 C2A Washington, D.C. 20555 Mr. G.A. Hutto, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station
CNEI-0400-248 Page 1 of 32 Revision 0 Catawba Unit I Cycle 21 Core Operating Limits Report Revision 0 October 2012 Calculation Number: CNC-1553.05-00-0582 Date Prepared By:
03 4-2 ,2 Checked By:
Checked By: ADZ39012..
(Sections 1.1, 2. 1, &M2.9 - 2.18)
Approved By:
0 QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.
CNEI-0400-248 Page 2 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: 9 (Sponsor)
(ý V&We'llC.) Date: 16__1Ai CATAWBA Inspection Waived MCE (Mechanical & Civil) _o, Inspected By/Date:
RES (Electrical Only) s Inspected By/Date:
RES (Reactor) 4;1" Inspected By/Date:
MOD Iii" Inspected By/Date:
Other ( ,) Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) [2 Inspected By/Date:
RES (Electrical Only) U Inspected By/Date:
RES (Reactor) i Inspected By/Date:
MOD Inspected By/Date:
Other ( ) L[ Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil) F- Inspected By/Date:
RES (Electrical Only) H Inspected By/Date:
RES (Reactor) F] Inspected By/Date:
MOD 7] Inspected By/Date:
Other ( ) U Inspected By/Date:
ii I' CNEI-0400-248 Page 3 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and PIP Tracking Revision 0 of the Catawba Unit I Cycle 21 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 20 and 21 but must become effective prior to entering MODE 6 which starts Cycle 21. The Catawba Unit I Cycle 21 COLR will cease to be effective during No MODE between Cycles 21 and 22.
Data files to be Implemented No data files are transmitted as part of this document.
CNEI-0400-248 Page 4 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR 0 October 2012 1-32, Appendix A* C I C21 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-0400-248 Page 5 of 32 Revision 0 Catawba 1 Cycle 21 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 Shutdown Margin SDM 2.2 9 3,1.3 Moderator Temperature Coefficient MTC 2.3 II 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 3A1.6 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 OTAT 2.9 24 Penalty Factors 2.6 19 3,2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 20 Factor Penalty Factors 2.6 19 3,2.3 Axial Flux Difference AFD 2.8 21 3.3.1 Reactor Trip System Instrumentation OTAT 2.9 24 OPAT 2.9 25 3.3.9 BoronDilution Mitigation System Reactor Makeup Water Flow Rate 2.10 26 3A4.] 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 26 315.4 Refueling Water Storage Tank Max and Min Boron Conc. 2.13 28 3.3.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 28 319.1 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 16.9-1 1 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-0400-248 Page 6 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 1.1 Analytical Methods Analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC, as specified in Technical Specification 5.6.5, are as follows.
I. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (W Proprietary).
Revision 0 Report Date: July 1985 Not Used
- 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
- 4. WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (W Proprietary).
Revision: Volume I (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
CNEI-0400-248 Page 7 of 32 Revision 0 Catawba I Cycle 21 Core Operating Limits Report 1.1 Analytical Methods (continued)
Revision 5a Report Date: October 2012
- 7. DPC-NE-3001 -PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision 0a Report Date: May 2009
Revision 4b Report Date: September 2010
- 9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-O I," (DPC Proprietary).
Revision 2a Report Date: December 2008
- 10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 4a Report Date: December 2008
- 11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision la Report Date: December 2008 Not Used
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 3a Report Date: September 2011
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."
Revision la Report Date: January 2009 Not Used
CNEI-0400-248 Page 8 of32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 14. DPC-NF-20 10-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."
Revision 2a Report Date: December 2009
- 15. DPC-NE-201 I-PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision I a Report Date: June 2009
- 16. DPC-NE- 1005-P-A, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX", (DPC Proprietary).
Revision I Report Date: November 12, 2008
- 17. BAW-10231P-A, "COPERNIC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)
Revision I SER Date: January 14, 2004 Not Used
CNEI-0400-248 Page 9 of 32 Revision 0 Catawba 1 Cycle 21 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% AK/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% AK/K in MODE 5.
2.2.3 For TS 3.1.4, SDM shall be greater than or equal to 1.3% AK/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% AK/K in MODE I 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% AK/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% AK/K in MODE 2 during PHYSICS TESTS.
CNEI-0400-248 Page 10 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THI-S AREA 660 650 640 oý 630 U 620 610 ___________,
600 590 ACCEPTABLE 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
CNEI-0400-248 Page II of 32 Revision 0 Catawba 1 Cycle 21 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 AK/K/0 F.
The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/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 AK/K/IF.
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 AK/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. Shutdown banks are withdrawn in sequence and with no overlap.
CNEI-0400-248 Page 12 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9
!0 11 0.8 U 0.7, 0.6 0.5 0.4 S 0.3 S 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 I ROD manual for details.
CNEI-0400-248 Page 13 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 180
- t 160 140 n 120
" 100
- 80
. 60 40 20 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 t25.7 < P<I00}
where P = %Rated Thermal Power NOTES: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to the Unit I ROD manual for details.
CNEI-0400-248 Page 14 of 32 Revision 0 Catawba 1 Cycle 21 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 BankA BankB BankC BankD 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 BankA BankB BankC BankD 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 BankA BankB BankC BankD 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 III 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop II1 0 226 226 116 0 Start 227 227 116 0 Start 226 -226 226 Stop 110 227 227 227 Stop III Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps Control Control Control Control Control Control Control Control BankA BankB BankC BankD 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 BankC 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 Slop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 0 Start 0 230 230 Slop 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-0400-248 Page 15 of 32 Revision 0 Catawba 1 Cycle 21 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. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table I.
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 RTP *K(Z)/P for P > 0.5 F RTP *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 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.
RTP 2.6.2 FQ = 2.70 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.
_RTP wt h 2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of bumup. FQ with the K(BU) penalty for Westinghouse RFA fuel is set to 1.0 at all burnups.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
D 2.6.5 [F L FQ(X,Y,Z)
- MQ(X,Y,Z)
. Q(XYZ)I UMT
- TILT where:
[FL (X,Y,Z)]oP = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
FM(X,Y,Z)°P includes allowances for calculational and measurement uncertainties.
CNEI-0400-248 Page 16 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report
> (X,Y,Z) = Design power distribution for FQ. Fj'(X,Y,Z).is provided in Appendix Table A-I 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-I for nonnal 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).
TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)
FQ(X,Y,Z)
- Mc(XY,Z) 2.6.6 [F LQ(X,Y,Z)]=RPS UMT
- TILT where:
[IFL(X,Y,Z)]RPS Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
[F'(XY,Z)]RPs includes allowances for calculational and measurement uncertainties.
D~XYZ Design power distributions for FQ. FQ(X,Y,Z) is provided in Appendix Table A-I for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial MQ(X,Y,Z) =
startup operations.
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.
CNEI-0400-248 Page 17 of 32 Revision 0 Catawba I Cycle 21 Core Operating Limits Report 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) 2.6.7 KSLOPE = 0.0725 where:
KSLOPE = Adjustment to K1 value from OTAT trip setpoint required to compensate for each 1% F,) (X,Y,Z) exceeds FQ (X,Y,Z)RPS 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-0400-248 Page 18 of 32 Revision 0 Catawba 1 Cycle 21 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 (12.0,0.9259)
(4.0, 0.9259) 0.800 0.600 0.400 Core Height (ft) K(Z) 0.0 1.000 0.200 <4 1.000
>4 0.9259 12.0 0.9259 0.000 i i i I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
CNEI-0400-248 Page 19 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAH(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup FQ(X,YZ) FAn(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 2.00 460 2.00 2.00 475 2.00 2.00 485 2.00 2.00 490 2.00 2.00 500 2.00 2.00 510 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 FAH(X,Y) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
CNEI-0400-248 Page 20 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)
FAH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.
2.7.1 [FkH (X, y)]LCO= MARP (X,Y)* [i.0 +- * (1.0- P)]
where:
FL y)Lco
[FAH (X, Y)] is 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.
Themrral Power Rated Thermal Power RRH =Thermal Power reduction required to compensate for each 1% measured radial peak, FA* (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.
L (X,Y)]sURV = FAH(X,Y)*MA,(X,Y)
UMR
- TILT where:
SURV F*H(X,Y)] Cycle dependent maximum allowable design peaking factor that ensures F AH(XY) limit is not exceeded for operation FAH(X,Y)SURV within the AFD, RIL, and QPTR limits.
includes allowances for calculational and measurement D uncertainty. D FAH (X,Y) is F H (X,Y) = Design radial power distribution for FAH provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.
CNEI-0400-248 Page 21 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report MAH(XY) = Margin remaining in core location X,Y relative to Operational DNB limits in the transient power distribution.
MAH(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 MAH(XY).
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, FA (X,Y) exceeds its limit. (0 < P < 1.0) 2.7.4 TRH = 0.04 where:
TRH = Reduction in OTAT K, setpoint required to compensate for each 1%
measured radial peak, F* (X,Y) exceeds its limit.
2.7.5 FAH(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 Axial Flux Difference (AFD) Limits are provided in Figure 5.
CNEI-0400-248 Page 22 of 32 Revision 0 Catawba 1 Cycle 21 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 2,0090 1.9333 1.8625 1.7780 1.3151 1.2461 1.20 1.8102 1.8540 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 1.8760 1.8054 1.7320 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 1.8070 1.8438 1.8716 1.8930 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 1.7950 1.7359 1.7089 1.6544 1.6010 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 1.7980 1.7868 1.7611 1.7163 1.6538 1.6315 1.5743 1.5573 1.5088 1.4624 1.3832 1.1009 1.0470 11.40 1.7892 1.7652 1.7250 1.6645 1.6057 1.5826 1.5289 1.5098 1.4637 1.4218 1.3458 1.0670 1.0142
CNEI-0400-248 Page 23 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits C
F-
~l) 0 0)
C.)
0)
-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta 1)
NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to the Unit I ROD manual for operational AFD limits.
CNEI-0400-248 Page 24 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T'< 585.1 OF Nominal RCS Operating Pressure P'= 2235 psig Overtemperature AT reactor trip setpoint K 1 = 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.03340/ 0 F penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator -c 8 sec.
for AT '2 = 3 sec.
Time constant utilized in the lag compensator for AT "E3 = 0 sec.
Time constants utilized in the lead-lag compensator -14 = 22 sec.
for Tavg _5 = 4 sec.
Time constant utilized in the measured Ta,,g lag T6 = 0 sec.
compensator f I(AI) "positive" breakpoint = 19.0 %AI f I(AI) "negative" breakpoint = N/A*
fl(Al) "positive" slope = 1.769 %AT0 / %At f I(AI) "negative" slope = N/A*
The fl(AI) negative breakpoints and slopes for OTAT are less restrictive than the OPAT f,(AI) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits the OPAT fl(AI) limits will result in a reactor trip before the OTAT fl(AI) limits are reached. This makes implementation of an OTAT fl(At) negative breakpoint and slope unnecessary.
CNEI-0400-248 Page 25 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T"< 585.1 OF Overpower AT reactor trip setpoint K4 = 1.0864 Overpower AT reactor trip penalty K5 = 0.02 / OF for increasing Tavg K5 = 0.00 / OF for decreasing Tavg Overpower AT reactor trip heatup setpoint K 6 = 0.00I1 179/'F for T > T" penalty coefficient (for T>T") K 6 = 0.0 /F for T < T" Time constants utilized in the lead-lag -'1 = 8 sec.
compensator for AT _[2 = 3 sec.
Time constant utilized in the lag -13 = 0 sec.
compensator for AT Time constant utilized in the measured Tavg _C6 = 0 sec.
lag compensator Time constant utilized in the rate-lag T7 = 10 sec.
controller for Tavg f2 (Al) "positive" breakpoint = 35.0 %AI f2 (Al) "negative" breakpoint = -35.0 %AI f2(AI) "positive" slope = 7.0 %ATo/ %AI f2(Al) "negative" slope = 7.0 %ATo/ %AI
CNEI-0400-248 Page 26 of 32 Revision 0 Catawba 1 Cycle 21 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 < 10 gpin MODE4or5 < 70gprn 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 Applicable Burnup Limit Accumulator minimum boron concentration. 0 - 200 EFPD 2,500 ppm Accumulator minimum boron concentration. 200.1 - 250 EFPD 2,400 ppm Accumulator minimum boron concentration. 250.1 - 300 EFPD 2,341 ppm Accumulator minimum boron concentration. 300.1 -350 EFPD 2,273 ppm Accumulator minimum boron concentration. 350.1 -400 EFPD 2,206 ppm Accumulator minimum boron concentration. 400.1 -450 EFPD 2,139 ppm Accumulator minimum boron concentration. 450.1 - 500 EFPD 2,073 ppm Accumulator minimum boron concentration. 500.1 -510 EFPD 2,007 ppm Accumulator maximum boron concentration. 0-510 EFPD 3,075 ppm
CNEI-0400-248 Page 27 of 32 Revision 0 Catawba 1 Cycle 21 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-0400-248 Page 28 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report 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 Limtit RWST minimum boron concentration. 23700 ppm RWST maximum boron concentration. 3,075 ppm 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 minimnumn boron concentration. 2,700 ppm 2.15 Refueling 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 MODE 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that core Keff remains 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-0400-248 Page 29 of 32 Revision 0 Catawba 1 Cycle 21 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 < 21 0°F, 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 68TF BAT Minimum Shutdown Volume (Includes the 13,086 gallons additional volumes listed in SLC 16.9-11) (14.9%)
NOTE: When cycle burnup is _ 471 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 °F RWST Minimum Shutdown Volume (Includes the 48,500 gallons additional volumes listed in SLC 16.9-11) (8.7%)
CNEI-0400-248 Page 30 of 32 Revision 0 Catawba 1 Cycle 21 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 > 210*F.
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 210°F BAT Minimum Shutdown Volume (Includes the 25,200 gallons additional volumes listed in SLC 16.9-12) (45.8%)
NOTE: When cycle burnup is >_471 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 21O0 EF RWST Minimum Shutdown Volume (Includes the 98,607 gallons additional volumes listed in SLC 16.9-12) (22.0%)
CNEI-0400-248 Page 31 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is ? 471 EFPD)
This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 50.0 45.0 RCS Boron Concentration BAT Level (ppm) (%level)
- 4. 0 < 300 43.0 300 < 500 40.0 35.0 500 < 700 37.0 700 < 1000 30.0
,*30.0 1000 < 1300 14.9 1300< 2700 9.8
-- 25.0
> 2700 9.8 Unacceptable 20.0 Operation Acceptable Operation 15.0 -
10.0 I 5.0 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)
CNEI-0400-248 Page 32 of 32 Revision 0 Catawba 1 Cycle 21 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the Catawba I Cycle 21 Maneuvering Analysis calculation file, CNC-1553.05-00-0579. 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.