ML081510800
| ML081510800 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/27/2008 |
| From: | Morris J Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNEI-0400-154, Rev 0 | |
| Download: ML081510800 (38) | |
Text
PDuke EEnergy Carolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station / CNO1 VP 4800 Concord Road York, SC 29745 803-831-4251 803-831-3221 fax May 27, 2008 U.S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, D.C.
20555-0001
Subject:
Duke Energy Carolinas, LLC.
Catawba Nuclear Station Unit 1 Docket No.: 50-413 Core Operating Limits Report (COLR)
Catawba Unit 1 Cycle 18, Revision 0 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of the Core Operating Limits Report for Catawba Unit 1 Cycle 18.
This letter and attached COLR do not contain any new commitments.
Please direct any questions or concerns to Marc Sawicki at (803) 701-5191.
Sincerely, James R. Morris Attachments Aoo(~
www. duke-energy. corn
U.
S.
Nuclear Regulatory Commission May 27, 2008 Page 2 Xc:
(w/att)
Luis A.
Reyes, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St.,
SW Atlanta, GA 30303-8931 J.
F.
Stang, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8 G9A Rockville, MD 20852-2738 A.
T. Sabisch Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station
U.
S.
Nuclear Regulatory Commission May 27, 2008 Page 3 bxc: (w/att)
RD Hart MJ Sawicki AR James BL Aldridge NCMPA-1 SREC PMPA NCEMC RGC Master File ELL CN01RC CNO1RC EC08G CNS01SA Date File CN-801. 01 EC050
CNEI-0400- 154 Page 1 of 35 Revision 0 Catawba Unit 1 Cycle 18 Core Operating Limits Report Revision 0 April 2008 Duke Energy Company Prepared By:
Checked By:
Checked By:
Approved By:
p Date La/0 eo QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.
CNEI-0400-154 Page 2 of 35 Revision 0 INSPECTION OF ENGINEERING INSTRUCTIONS ie 'A' Inspection Waived By:
Date:
(Sponsor) 0 CATAWBA Inspection Waived MCE (Mechanical & Civil)
Inspected By/Date:
RES (Electrical Only)
[I Inspected By/Date:
RES (Reactor) w Inspected By/Date:
MOD Inspected By/Date:
Other (
)
Li Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) r, Inspected By/Date:
RES (Electrical Only) 0 Inspected By/Date:
RES (Reactor)
- 0.
Inspected By/Date:
MOD 0
Inspected By/Date:
Other (.....
_)
Li Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil)
Li Inspected By/Date:
RES (Electrical Only)
L Inspected By/Date:
RES (Reactor)
Li Inspected By/Date:
[]
Inspected By/Date:
Other (
- 0)
[
Inspected By/Date:
CNEI-0400-154 Page 3 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and PIP Tracking Revision 0 of the Catawba Unit 1 Cycle 18 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 17 and 18 but must become effective prior to entering MODE 6 which starts Cycle 18. The Catawba Unit 1 Cycle 18 COLR will cease to be effective during No MODE between Cycle 18 and 19.
Data files to be Implemented No data files are transmitted as part of this document.
CNEI-0400-154 Page 4 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report REVISION LOG Revision 0
Effective Date April 2008 Pages Affected 1-35, Appendix A*
- 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-0400-154 Page 5 of 35 Revision 0 Catawba 1 Cycle 18 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 COLR1 COLR Section Technical Specifications COLR Parameter Section Page 2.1.1 Reactor Core Safety Limits RCS Temperature and Pressure 2.1 9
i Safety Limits 3.1.1 Shutdown Mar1gint
_imts Shutdown Marg2in
-2.2 9
3.1.3 Moderator Temperature Coefficient MTC23 1
3.1.4 RAimts Shutdown Margin 2.2 9
3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.2 9
Rod Insertion Limits 2.4 11 3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 9
Rod Insertion Limits 2.5.
11 3.1.8 Physics Tests Excep-tions Shutdown Mar&gin.
2.2 9
3.2.1 Heat Flux Hot Channel Factor FQ 2.6 15 AFD 2.8 24 OTAT 2.9 27 i Penalty Factors 2.6 17 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 23 Factor Penalty Factors 2.7 24 3.2.3 Axial Flux Difference 2.AFD
_.8 24 3.3.1 Reactor Trip System Instrumentation OTAT I
2.9 27 n Se OPAT 2.9 28 3.3.9 MBoronDilution-M-ittig n S-stem i Reactor Makeup Water Flow Rate 2.10 29 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, Temperature and 2.11 29 limits for DNB Flow 3.5.1 Accumulators Max and Min Boron Conc.
2.12 29 3.5.4 Refueling Water Storage Tank Max and Mi Boron Conc.
2.13 29 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 31 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 31
__ Concentration 5.6.5 Core Operating Limits Report
.Analytical Methods I
- 1.
6 I (COLR)
The Selected License Commitments that reference this report are listed below:
SLC 1
1 1 COLR COLR Section Selected Licensing Commitment COLR Parameter Section Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.16 32 16.9-11 Boration Systems-Borated Water Borated Water Volume and Conc.
2.17 32 Source - Shutdown.
for BAT/RWSTC 16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc.
2.18 33 Source - Operating for BAT/RWST
CNEI-0400-154 Page 6 of 35 Revision 0 Catawba 1 Cycle 18 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 C1C18
- 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 C1C18
- 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 C1C18
CNEI-0400-154 Page 7 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)
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 C1C18
- 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 C1C18
CNEI-0400-154 Page 8 of 35 Revision 0 Catawba 1 Cycle 18 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-201 1PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision 1 SER Date: October 1, 2002
Revision 0 SER Date: August 20, 2004
- 17. BAW-10231P-A, "COPERNIC Fuel Rod Design Computer Code" (Framatome ANP Proprietary)
Revision 1 SER Date: January 14, 2004
CNEI-0400-154 Page 9 of 35 Revision 0 Catawba 1 Cycle 18 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, shutdown margin 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, shutdown margin shall be greater than or equal to 1.0% AK/K in mode 5.
2.2.3 For TS 3.1.4, shutdown margin 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, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 1 and mode 2 with any control bank not fully inserted.
2.2.5 For TS 3.1.6, shutdown margin 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, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 during Physics Testing.
CNEI-0400-154 Page 10 of 35 Revision 0 Catawba 1 Cycle 18 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 o
630
~2280 Zpsia H
U 620_____
610210 600 590 ACCEPTABLE 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
CNEI-0400-154 Page 11 of 35 Revision 0 Catawba 1 Cycle 18 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/°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/°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 AK/K/0F.
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.
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 1.
CNEI-0400- 154 0
E 0
Page 12 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level, 1.0-0.9 Unacceptable Operation 0.8 0.7 0.6 0.5 0.4 Acceptable Operation 0.3 0.2 0.1 0.0-0 10 20 30 40 50 60 70 80 90 100 Il 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-0400-154 Page 13 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231)
(29.6%, 231)
(80.0%, 231) 231 220 200 180 E 160
- . 140
= 120 0 100 80 S60 0
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*< P5
<80}
Bank CB RIL = 2.3(P) + 163 {0 < P < 29.6}
where P = %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- 154 Page 14 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 222 Stop 106 0
0 222 116 0OStart 0
222 222 Stop 106.
0 222 222 116 0OStart 222 222 222 Stop 106 Fully Withdrawn at 223 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 223 Stop 107 0
0 223 116 0OStart 0
223 223 Stop 107 0
223 223 116 0OStart 223 223 223 Stop 107 Fully Withdrawn at 224 Steps Control Control Control Control Bank A Bank B Bank C Bank D Fully Withdrawn at 225 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 224 Stop 108 0
0 224 116 0OStart 0
224 224 Stop 108 0
224 224 116 0OStart 224 224 224 Stop 108 Fully Withdrawn at 226 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 225 Stop 109 0
0 225 116 0OStart 0
225 225 Stop 109 0
225 225 116 0OStart 225 225 225 Stop 109 Fully Withdrawn at 227 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 2 26 Stop 110 0
0 226 116 0OStart 0
226 226 Stop 110 0
226 226 116 0OStart 226 226 226 Stop 110 Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank B Bank C BankD-0OStart 0
0 0
116 0OStart 0
0 228 Stop 112 0
0 228 116 0OStart 0 228 228 Stop 112 0
228 228 116 0OStart 228 228 228 Stop 112 0OStart 0
0 0
116 0OStart 0
0 227 Stop 111 0
0 227 116 0OStart 0
227 227 Stop 111 0
227 227 116 0OStart 227 227 -227 Stop III Fully Withdrawn at 229 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 O
0Start 0
0 229 Stop 113 0
0 229 116 0OStart 0
229 229 Stop 113 0
229 229 116 0OStart 229 229 229 Stop 113 Fully Withdrawn at 230 Steps Control Control Control Control Bank A Bank B Bank C BankD-0OStar-t 0
0 0
116 0OStart 0
0 230OStop 114 0
0 230 116 0OStart 0
230 230OStop 114 0
230 230 116 0OStart 230 1230 230OStop 114 Fully Withdrawn at 231 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0OStart 0
0 0
116 0OStart 0
0 231 Stop 115 0
0 231 116 0OStart 0
231 231 Stop 115 0
231 231 116 0OStart 231 231
'231 Stop 115
CNEI-0400-154 Page 15 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 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 Q
F RTP *K(Z)/0.5 for P < 0.5 Q
- where, P = (Thermal Power)/(Rated Power)
Note: The measured FQ(X,Y,Z) shall be increased by 3.1% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limit. The more conservative of the manufacturing tolerances for RFA/NGF fuel (3%) or MOX fuel (3.1%) is used when comparing against the LCO limit due to input limitations in monitoring software. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined below for COLR Sections 2.6.5 and 2.6.6.
2.6.2 FRTP 2.60 x K(BU) for RFA and NGF fuel FýRTP 2.40 x K(BU) for MOX fuel 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height.
K(Z) for Westinghouse RFA and NGF fuel is provided in Figure 4, and the K(Z) for MOX fuel is provided in Figure 5.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. K(BU) for Westinghouse RFA and NGF fuel is provided in Figure 6, and the K(BU) for MOX fuel is provided in Figure 7.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
CNEI-0400-154 Page 16 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.6.5
[FQ(X,Y,Z)]oP = F(X,Y,Z)
- MQ(X,Y,Z) 2 UMT'* MT
- TILT where:
[F* (X,Y,Z)IOP = 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.
F* (X,Y,Z)0 P includes allowances for calculational and measurement uncertainties.
FQ D(X,Y,Z) =
MQ(X,Y,Z) =
Design power distribution for FQ. F D (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.
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 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)
= Engineering Hot Channel Factor. (MT = 1.03 1). The more conservative of the manufacturing tolerances for RFA/NGF fuel (3%) or MOX fuel (3.1%) is used when comparing against the FQ LOCA surveillance limit due to input limitations in monitoring software. The manufacturing tolerances for RFA/NGF fuel and MOX 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)
L RPS 2.6.6
[FQ(X,Y,Z)].
=
FQ(X,Y,Z)
- Mc(X,Y,Z)
UMT
- TILT where:
CNEI-0400-154 Page 17 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report
[FQ(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 QPTR limits. [FL$(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.
Ft(X,Y,Z) =
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 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.
= Engineering Hot Channel Factor. (MT = 1.03 1). The more conservative of the manufacturing tolerances for RFA/NGF fuel (3%) or MOX fuel (3.1%) is used when comparing against the FQ RPS surveillance limit due to input limitations in monitoring software. The manufacturing tolerances for RFA/NGF fuel and MOX 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 OTAT trip setpoint required to compensate for each 1% that F j (X,Y,Z) exceeds FL (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-0400-154 Page 18 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA and NGF Fuel 1.200 1.000 (0.0,1.00)
(4.0, 1.00)
I (0.0, 1.00)
(4.0, 1.00)
I (12.0, 0.9615)
(4.0, 0.9615) 0.800 N 0.600
ý4 0.400 +
Core Height (ft)
K(Z) 0.0 1.000
<4 1.000
>4 0.9615 12.0 0.9615 0.200 +
0.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
CNEI-0400-154 Page 19 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 5 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MOX Fuel 1.200 1.000 0.800 -
,, 0.600 -
I(0.0, 1.00)
(8.0, 1.00)
(12.0,0.95)
(0.0, 1.00) 0.400 +
Core Height (ft)
K(Z) 0.0 1.000 8.0 1.000 12.0 0.950 0.200+
0.000 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
CNEI-0400-154 Page 20 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 6 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for RFA and NGF Fuel 1.200 1.000 (0.0, 1.00)
(30.0, 1.00)
(60.0, 1.00) i 0.800 +
0.600 +
0.400 +
0.200 +
Core Burnup (GWD/MTU)
K(BU) 0.0 1.000 30.0 1.000 60.0 1.000 0.000 i
i 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Burnup (GWD/MTU)
CNEI-0400-154 Page 21 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 7 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MOX Fuel 1.200 (0.0, 1.00)
(30.0, 1.00) 1.000 0.800 (60.0, 0.80 m 0.600 0.400 Core Burnup (GWD/MTU)
K(BU) 0.200 0.0 1.000 30.0 1.000 60.0 0.800 0.000 I
I I
0.0 10.0 20.0 30.0 40.0 50.0 60.0 Burnup (GWD/MTU)
CNEI-0400-154 Page 22 of 35 Revision 0 Catawba 1 Cycle 18 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 (EFPD) 4 12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 465 481 506 521 FQ(X,Y,Z)
Penalty Factor(%)
2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 FAH(X,Y)
Penalty Factor (%)
2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle bumups.
All cycle bumups 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-0400-154 Page 23 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)
The FAH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.
2.7.1
[FL (X, Y)] Lo = MARP (X,Y) 1.0+ RRH * (1.0- P)]
where:
[FWL (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.
P Thermal Power Rated Thermal Power RRH =Thermal Power reduction required to compensate for each 1% that the measured radial peak, Fm (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 SURV 2.7.2
[ FL (X,Y)I FL (XY) *MA (XY)
UMR
- TILT where:
[ FL (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.
FL (,YSURV includes allowances for calculational and D
FAH (X,Y)=
measurement uncertainty.
Design power distribution for F,,. FA (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-0400-154 Page 24 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report M A(XY)
= The margin remaining in core location X,Y relative to the 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 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% that the measured radial peak, FL (X,Y) exceeds its limit. (0 < P < 1.0) 2.7.4 TRH = 0.04 where:
TRH = Reduction in OTAT K1 setpoint required to compensate for each 1% that the measured radial peak, Fm(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 The Axial Flux Difference (AFD) Limits are provided in Figure 8.
CNEI-0400- 154 Page 25 of 35 Revision 0 Catawba 1 Cycle 18 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 MOX Fuel M4ARPs 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 1.711 1.742 1.798 1.847 1.887 1.913 1.823 1.768 1.685 1.611 1.537 1.231 1.171 1.20 1.711 1.739 1.790 1.836 1.874 1.893 1.813 1.771 1.690 1.616 1.515 1.183 1.122 2.40 1.709 1.734 1.780 1.818 1.852 1.868 1.791 1.755 1.685 1.620 1.508 1.148 1.095 3.60 1.706 1.728 1.766 1.800 1.823 1.813 1.761 1.742 1.685 1.620 1.528 1.159 1.086 4.80 1.702 1.720 1.752 1.780 1.767 1.758 1.707 1.690 1.642 1.591 1.543 1.180 1.128 6.00 1.697 1.712 1.735 1.757 1.716 1.703 1.655 1.639 1.592 1.547 1.496 1.261 1.224 7.20 1.693 1.704 1.717 1.707 1.663 1.649 1.602 1.586 1.543 1.501 1.448 1.220 1.182 8.40 1.689 1.691 1.696 1.657 1.609 1.595 1.549 1.536 1.495 1.455 1.400 1.183 1.144 9.60 1.679 1.675 1.651 1.605 1.557 1.543 1.499 1.490 1.452 1.414 1.359 1.147 1.107 10.80 1.667 1.654 1.608 1.558 1.509 1.494 1.453 1.443 1.407 1.373 1.318 1.124 1.087 11.40 1.661 1.637 1.587 1.538 1.488 1.476 1.433 1.424 1.389 1.359 1.307 1.113 1.074 NGF Fuel MARPs 100% Full Power Core Height Axial Peak (ft) 1.05 1.2 1.4 1.6 1.8 2.1 3.25 0.12 1.7339 1.8713 1.8045 2.0493 1.9307 1.7855 1.2661 2.40 1.7237 1.8528 1.8045 1.9933 1.8696 1.7244 1.4424 4.80 1.728 1.8237 1.8045 1.8844 1.8013 1.6471 1.2322 17.201 1.7247 1.7842 1.8045 1.7354 1.6587 1.5342 1.1715 9.60 1.724 1.7232 1.6517 1.566 1.4887 1.3575 1.0167 11.40 1.7066 1.6415 1.5241 1.4382 1.3737 1.2608 0.96
CNEI-0400-154 Page 26 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 8 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-20, 100)
(+10, 100)
Unacceptable Operation Unacceptable Operation 90 80 07
- p.
70 Acceptable Operation 60 50o
(-36, 50)
(+21, 50) 40
- p.
30 20 10 I
I I
0
[
I
-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-0400-154 Page 27 of 35 Revision 0 Catawba 1 Cycle 18 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 Nominal RCS Operating Pressure Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip heatup setpoint penalty coefficient Overtemperature AT reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for AT T'< 585.1 OF P' = 2235 psig KI = 1.1978 K2 = 0.03340/0 F K3 = 0.001601/psi Til = 8 sec.
,r2 = 3 sec.
Time constant utilized in the lag compensator for AT r3 = 0 sec.
Time constants utilized in the lead-lag compensator r4 = 22 sec.
for Tavg "r5 = 4 sec.
Time constant utilized in the measured Tavg lag t6 = 0 sec.
compensator fl(AI) "positive" breakpoint
= 19.0 %AI fl(AI) "negative" breakpoint
= N/A*
fl(AI) "positive" slope
= 1.769 %AT 0 / %AI fI(AI) "negative" slope
= N/A*
The fI (Al) negative breakpoints and slopes for OTAT are less restrictive than the OPAT f2(AI) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits the OPAT f2(AI) limits will result in a reactor trip before the OTAT fl(Al) limits are reached. This makes implementation of an OTAT fl (Al) negative breakpoint and slope unnecessary.
CNEI-0400-154 Page 28 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower AT reactor trip setpoint Overpower AT reactor trip penalty Overpower AT reactor trip heatup setpoint penalty coefficient (for T>T")
Time constants utilized in the lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constant utilized in the measured Tavg lag compensator Time constant utilized in the rate-lag controller for Tavg f 2(AI) "positive" breakpoint f2(AI) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Nominal Value T" < 585.1 °F K4 = 1.0864 K5 = 0.02 / °F for increasing Tavg K5 = 0.00 / °F for decreasing Tavg K6 = 0.00 1179/ 0F for T > T" K6 = 0.0 /OF for T < T" "11 = 8 sec.
'12 = 3 sec.
"U3 = 0 sec.
"16 = 0 sec.
"17 = 10 sec.
= 35.0 %AI
-35.0 %AI
= 7.0 %AT0/
= 7.0 %ATo/
%AI
%AI
CNEI-0400-154 Page 29 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.10 Boron Dilution Mitigation System (TS 3.3.9) 2.10.1 Reactor Makeup Water Pump flow rate limits:
Applicable Mode Limit Mode 3
< 150 gpm Mode 4 or 5
< 70 gpm 2.11 RCS Pressure, Temperature and Flow Limits for DNB (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 Cold Leg Accumulator minimum boron concentration.
Cold Leg Accumulator maximum boron concentration.
Limit 2,500 ppm 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 Refueling Water Storage Tank minimum boron concentration.
Refueling Water Storage Tank maximum boron concentration.
Limit 2,700 ppm 3,075 ppm
CNEI-0400-154 Page 30 of 35 Revision 0 Catawba 1 Cycle 18 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 °F meter 3
< 586.9 'F computer 4
< 587.7 'F computer 3
< 587.5 'F
- 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-0400-154 Page 31 of 35 Revision 0 Catawba 1 Cycle 18 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 System, the refueling canal, and the refueling cavity.
2,700 ppm
CNEI-0400-154 Page 32 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.16 Standby Shutdown System - Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.16.1 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 2.17 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 < 210°F, and Modes 5 and 6.
Parameter Limit Boric Acid Tank minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 680F Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 7,000 ppm 2000 gallons 13,086 gallons (14.9%)
NOTE: When cycle burnup is > 480 EFPD, Figure 9 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 68 OF Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 2,700 ppm 7,000 gallons 48,500 gallons (8.7%)
CNEI-0400-154 Page 33 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report 2.18 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 0 F.
Parameter Limit Boric Acid Tank minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 210°F Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 7,000 ppm 13,500 gallons 25,200 gallons (45.8%)
NOTE: When cycle burnup is > 480 EFPD, Figure 9 may be used to determine the required Boric Acid Tank Minimum Level.
Refueling Water Storage Tank minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210TF Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 2,700 ppm 57,107 gallons 98,607 gallons (22.0%)
CNEI-0400-154 Page 34 of 35 Revision 0 Catawba 1 Cycle 18 Core Operating Limits Report Figure 9 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 16.9-11 and 16.9-12 50.0 45:0 RCS Boron Concentration BAT Level 400.(ppm)
(%level) 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 A0
> 2700 9.8
- *25.0 Unacceptable 20.0 Operation Acceptable Operation 15.0 i
10.0 5.0 0.0 4 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)
CNEI-0400-154 Page 35 of 35 Revision 0 Catawba 1 Cycle 18 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.