ML102850463
| ML102850463 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/29/2010 |
| From: | Morris J Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNC-1553.05-00-0535 CNEI-0400-203, Rev. 0 | |
| Download: ML102850463 (34) | |
Text
P Duke 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 September 29, 2010 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 Docket No. 50-413 Core Operating Limits Report (COLR)
Catawba Nuclear Station (CNS) Unit 2 Cycle 18, 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 2 Cycle 18. This COLR is being.submitted to update the limits of the Cycle 18 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 Toni K. Pasour at (803) 701-3566.
Sincerely, Ja R. Morris Attachments ADO(
www. duke-energy. com
N
'V U.S. Nuclear Regulatory Commission September 29, 2010 Page 2 xc w/attachment only:
U.S. Nuclear Regulatory Commission Mr. Luis A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. Jon H. Thompson, NRC Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 0-8 G9A Washington, D.C. 20555 Mr. G.A. Hutto, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station
f3 CNEI-0400-203 Page 1 Revision 0 Catawba Unit 2 Cycle 18 Core Operating Limits Report Revision 0 August 2010 Calculation Number: CNC-1553.05-00-0535 Duke Energy Prepared By:
Checked By:
Checked By:
Approved By:
(Secrions 2.1 and 2.9 -C4. 18)
Re Wzme.1 Date St/o
& /l ik 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-0400-203 Page 2 Revision 0 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived. By:
Date:
fL
/20 /6 (Sponsor)
-0 CATAWBA Inspection Waived MCE (Mechanical & Civil)
IV Inspected By/Date:
RES (Electrical Only)
[R-
.Inspected By/Date:
RES (Reactor)
[i-'
Inspected By/Date:
MOD P
Inspected By/Date:
Other (
)
[]
Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil)
El Inspected By/Date:
RES (Electrical Only)
[]
Inspected By/Date:
RES (Reactor)
.0 Inspected By/Date:
MOD 0]
Inspected By/Date:
Other ( _)
[
Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil)
[]
Inspected By/Date:
RES (Electrical Only)
LI Inspected By/Date:
RES (Reactor)
DI Inspected By/Date:
MOD.
[1 Inspected By/Date:
Other ( _)
L Inspected By/Date:
CNEI-0400-203 Page 3 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and PIP Tracking Revision 0 of the Catawba Unit 2 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 2.
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-0400-203 Page 4 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report REVISION LOG Revision 0
Effective Date August 2010 Pages Affected 1-32, Appendix A*
COLR C2C18 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.
'3
CNEI-0400-203 Page 5 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Technical Specifications that reference this report are listed below:
TS COLR COLR Section Technical Specifications COLR Parameter Section Page 2.1.1 Reactor Core Safety Limits I RCS Temperature and Pressure 2."1 9
__________________Safety Limits
_~
3.1.1 Shutdown Margin Shutdown Margi 2.2 9
3.1.3 Moderator Temperature Coefficient MTC
_2.3 11 3.1.4 Rod Group Alignment Limits 2
Shutdo9 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 1
9 Rod Insertion Limits 2.5 15 3.1.8 Physics Tests Exceptions Shutdown Margin 2.2 9
3.2.1 Heat Flux Hot Channel Factor FQ 2.6 15 AFD 2.8 1 21 OTAT 2.9 24
. Penalt Factors 2.6 1
17 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 j
20 Factor Penalty Factors 2.7 1 21 3.2.3 Axial Flux Difference AFD
-2.8 21 3.3.1 Reactor Trip System Instrumentation OTAT 2.9 24 I
{OPAT 2.9 25 3.3.9 Boron Dilution mitigationSysem Reactor Makeup Water Flow Rate 2.10 26 3.4.1 RCS Pressure, Temperature and RCS Pressure, Temperature and 2.11 26
.Flow limits for DNB Flow 3.5.1 Accumulators
_Max and Min Boron Conc.
2.12 26 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc.
6 2.13 1
26 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 28 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 28
_ Concentration 28 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 1
1 COLR COLR Section Selected Licensing Commitment COLR Parameter Section [ Page 16.7-9 Standby Shutdown System Standby Makeup Pump Water 2.16 29 Supp!Y 16.9-11 Boration Systems -Borated Water Borated Water Volume and Conc.
2.17 29 Source - Shutdown 1 for BAT/RWST 16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc.
2.18 30 Source - Operating for BAT/RWST
CNEI-0400-203 Page 6 Revision 0 Catawba 2 Cycle 18 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.
- 1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (& Proprietary).
Revision 0 Report Date: July 1985 Not Used for C2C18
- 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 C2C18
- 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 C2C18
CNEI-0400-203 Page 7 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)
Revision 4a Report Date: July 2009
- 7. DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision Oa Report Date: May 2009
Revision 4a Report Date: April 2009
- 9. DPC-NE-2004-PA, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-0 1," (DPC Proprietary).
Revision 2a Report Date: December 2008
- 10. DPC-NE-2005-P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 4a Report Date: December 2008
- 11. DPC-NE-2008-PA, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision la Report Date: December 2008 Not Used for C2C18
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 2a Report Date: July 2009
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."
Revision la Report Date: January 2009 Not Used for C2C18
CNEI-0400-203 Page 8 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 14. DPC-NF-201 O-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 1-P-A, "Duke Power Company Nuclear Design Methodology? for Core Operating Limits of Westinghouse Reactors," (DPC, Proprietary).
Revision Ia Report Date: June 2009
- 16. DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASMO-4 /
SIMULATE-3 MOX", (DPC Proprietary).
Revision 1 Report Date: November 12, 2008
Revision 1 SER Date: January 14, 2004 Not Used for C2C18
CNEI-0400-203 Page 9 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 2.0 Operating Limits Cycle-specific parameter limits for 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)
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 1 and MODE 2 with any control bank not fully inserted.
2.2.5 For TS 3.1.6, SDM shall be greater than or equal to 1.3% 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-0400-203 Page 10 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 640 630 2280 psia Ui 620 610.
600 590 ACCEPTABLE OPERATION 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
CNEI-0400-203 Page 11 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 Moderator Temperature Coefficient (MTC) Limits are:
MTC shall be less positive than the upper limits shown in Figure 2. BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/IF.
EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/K/°F lower MTC limit.
2.3.2 300 ppm MTC Surveillance Limit is:
Measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/°F.
2.3.3 60 PPM MTC Surveillance Limit is:
60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 AK/K/0 F.
Where:
BOC = Beginning of Cycle (burnup corresponding to most positive MTC)
EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Thermal Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps except under conditions listed in Section 2.4.2. Shutdown banks are withdrawn in sequence and with no overlap.
2.4.2 Shutdown banks may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.
CNEI-0400-203 Page 12 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 E.
U°!
o 0.8 0.7 0.6 0.5 0.4 0.3 0.2 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 2 ROD manual for details.
CNEI-0400-203 Page 13 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 180
'U 160 d140
- , 120
...* 100 80 60
- " 60
'U 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:
BankCDRJL=2.3(P)-69 {30<P<100}
Bank CCRIL = 2.3(P) +47 {0<P< 76.1) for CCRIL = 222 {76.1 <P<100)
Bank CBRIL =2.3(P) +163 {0 < P < 25.7} for CB RJL = 222 {25.7 < P < 1001 where P = %Rated Thermal Power NOTES: (1) Compliance with Technical Specification 3.1.3 may require rod withdrawal limits. Refer to the Unit 2 ROD manual for details.
(2) Anytime any shutdown bank or control banks A, B, or C are inserted below 222 steps withdrawn, control bank D insertion is limited to > 200 steps withdrawn (see Sections 2.4.2 and 2.5.2)
CNEI-0400-203 Page 14 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Control Control Control Control BankA BankB BankC BankD Fully Withdrawn at 223 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 222 Stop 106 0
0 222 116 0 Start 0
222 222 Stop 106 0
222 222 116 0 Start 222 222 222 Stop 106 Fully Withdrawn at 224 Steps Control Control Control Control BankA BankB BankC BankD 0 Start 0
0 0
116 0 Start 0
0 223 Stop 107 0
0 223 116 0 Start 0
223 223 Stop 107 0
223 223 116 0 Start 223 223 223 Stop 107 Fully Withdrawn at 225 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 225 Stop 109 0
0 225 116 0 Start 0
225 225 Stop 109 0
225 225 116 0 Start 225 225 225 Stop 109 Fully Withdrawn at 227 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 224 Stop 108 0
0 224 116 -,
OStart 0
224 224 Stop 108 0
224 224 116 0 Start 224 224 224 Stop 108 Fully Withdrawn at 226 Steps Control Control Control Control BankA Bank B Bank C BankD 0 Start 0
0 0
116 0 Start 0
0 226 Stop 110 0
0 226 116 0 Start 0
226 226 Stop 110 0
226 226 116 0 Start.
226 226 226 Stop 110 Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 228 Stop 112 0
0 228 116 0 Start 0
228 228 Stop 112 0
228 228 116 0 Start 228 228 228 Stop 112 Fully Withdrawn at 230 Steps Control Control Control Control BankA BankB BankC BankD 0 Start 0
0 0
116 0 Start 0
0 230 Stop 114 0
0 230 116 0 Start 0
230 230 Stop 114 0
230 230 116 0 Start 230 230 230 Stop 114 0 Start 0
'0 0
116 0 Start 0
0 227 Stop 111 0
0 227 116 0Start 0
227 227 Stop 111 0
227 227 116 0 Start 227 227 227 Stop 111 Fully Withdrawn at 229 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 229 Stop 113 0
0 229 116 0 Start 0
229 229 Stop 113 0
229 229 116 0 Start 229 229 229 Stop 113 Fully Withdrawn at 231 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 231 Stop 115 0
0 231 116 0 Start 0
231 231 Stop 115 0
231 231 116 0 Start 231 231 231 Stop 115
CNEI-0400-203 Page 15 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3 except under conditions listed in Section 2.5.2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.
2.5.2 Control banks A, B, or C may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.
2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:
F RTP *K(Z)iP for P > 0.5 FQR TP *K(Z)/0.5 for P < 0.5
- where, P
(Thermal Power)/(Rated Power)
Note:
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 limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.
2.6.2 F Rn = 2.60 x K(BU) 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height.
K(Z) for Westinghouse RFA fuel is provided in Figure 4.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. K(BU) for Westinghouse RFA fuel is 1.0 at all bumups.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
D 2.6.5
[FXLZ)]oP = FQ(X,Y,Z)
- MQ(X,Y,Z)
Q(XYZ UMT
- TILT
CNEI-0400-203 Page 16 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report where:
FQ (X,Y,Z)
=
MQ(X,Y,Z)
=
Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within AFD, RIL, and QPTR limits.
Fý (X,Y,Z) includes allowances for calculational and measurement uncertainties.
Design power distribution for FQ. Ff (X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
UMT =
Total Peak Measurement Uncertainty. (UMT = 1.05)
= Engineering Hot Channel Factor. (MT = 1.03).
TILT = Peaking penalty to account for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)
L RPS 2.6.6
[FQ(X,Y,Z)]
=
D FQ(X,Y,Z)
- MC(X,Y,Z)
UMT
- TILT where:
[FQ(X,Y,Z)]RP5
.Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within AFD, RIL, and QPTR limits.
[FQ(X,Y,Z)]RPs includes allowances for calculational and measurement uncertainties.
D Design power distributions for FQ. FQ(X,Y,Z) is provided in Appendix TableA-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operations.
D FQ(X,Y,Z)=
CNEI-0400-203 Page 17 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report 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.
UMT = Measurement Uncertainty (UMT = 1.05)
= Engineering Hot Channel Factor. (MT = 1.03).
TILT = Peaking penalty to account 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 [ F' (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-0400-203 Page 18 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA Fuel 1.200 1.000 0.800
. 0.600 0.400 0.200 0.000 (0.0, 1.00)
(4.0, 1.00)
(12.0,0.9615)
(4.0, 0.9615)
Core Height (ft)
K(Z) 0.0 1.0000
< 4.0 1.0000
> 4.0 0.9615 12.0 0.9615 2
2.0 0.0 4.0 1
6.0 Core Height (ft) 8 8.0 10.0 12.0
CNEI-0400-203 Page 19 Revision 0 Catawba 2 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 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 475 490 495 505 520 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 2.00 FA(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 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 Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
CNEI-0400-203 Page 20 Revision 0 Catawba 2 Cycle 18 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
[FALH (X, y)ILCO =MARP (X,Y)
- 1.
[.0 + RiI*(1. 0- P)]
where:
[F6H (X, y)]LCO 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.
Thermal 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 surveillance requirements of Technical Specification 3.2.2.
2.7.2
[ FH (X,Y)]sURv FI (X,Y)*MA.(X,Y)
UMR
- TILT where:
SURV
[FAH (X,Y)]
=
Cycle dependent maximum allowable design peaking factor that ensures FAH(XY) limit is not exceeded for operation within AFD, RIL, and QPTR limits. FALH (X,Y)sURv includes D
FAH MXY)=
allowances for calculational and measurement uncertainty.
D Design power distribution for FAH FAH (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-0400-203 Page 21 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report M A(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-61 for power escalation testing during initial startup operation.
UMR
=Uncertainty value for measured radial peaks (UMR= 1.0).
UMR is 1.0 since a factor of 1.04 is implicitly included in the variable MAH(X;Y).
TILT - Peaking penalty to account 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, FAH (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%
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 Axial Flux Difference (AFD) Limits are provided in Figure 5.
CNEI-0400-203 Page 22 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)
RFA Fuel MARPs 100% Full Power Core Height (ftl Axial Peak 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 1.20 2.40 3.60 4.80 6.00 7.20 8.40 9.60 10.80 11.40 1.8092 1.8102 1.8093 1.8098 1.8097 1.8097 1.807 1.8073 1Y8072 1.798 1.7892 1.8553 1.9489 1.9953 1.9741 1.854 1.9401 1.9953 1.9741 1.8525 1.9312 1.9779 1.9741 1.8514 1.9204 1.9641 1.9741 1.8514 1.9058 1.9449 1.9741 1.8514 1.8921 1.9212 1.9455 1.8438 1.8716 1.893 1.8872 1.8319 1.8452 1.8571 1.8156 1.8102 1.8093 1.7913 1.7375 1.7868 1.7611 1.7163 1.6538 1.7652 1.725 1.6645 1.6057 2.1073 2.1073 2.0735 2.0495 2.0059 1.9336 1.8723 1.795 1.7182 1.6315 1.5826 2.0498 2.009 2.0191 1.9775 1.9953 1.9519 1.9656 1.9258 1.9441 1.9233 1.8798 1.8625 1.8094 1.7866 1.7359 1.7089 1.6572 1.6347 1.5743 1.5573 1.5289 1.5098 1.9333 1.8625 1.9009 1.8306 1.876 1.8054 1.8524 1.7855 1.8538.
1.7836 1.8024 1.7472 1.7332 1.6812 1.6544 1.601 1.5808 1.5301 1.5088 1.4624 1.4637 1.4218 1.778 1.7852 1.732 1.6996 1.6714 1.6705 1.5982 1.5127 1.4444 1.3832 1.3458 1.3151 1.2461 1.3007 1.2235 1.4633 1.4616 1.4675 1.3874 1.2987 1.2579 1.3293 1.2602 1.2871 1.2195 1.2182 1.1578 1.1431 1.0914 1.1009 1.047 1.067 1.0142
CNEI-0400-203 Page 23 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-20, 100) 0 U
0 Unacceptable Operation
(-36, 50) 90 -
80 +
+10, 100)
Una cceptable Operation 70 +
60 Acceptable Operation 50 +
(+21,50) 40 +
30 +
20 +
10 +
[
l I
i UJ I i i
i v
-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 2 ROD manual for operational AFD limits.
CNEI-0400-203 Page 24 Revision 0 Catawba 2 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 Overteiperature AT reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constants utilized in the lead-lag compensator for Tavg Time constant utilized in the measured Tavg lag compensator fl(Al) "positive" breakpoint fl (Al) "negative" breakpoint fl (Al) "positive" slope fl (Al) "negative" slope T' < 590.8 OF P'= 2235 psig Kl = 1.1953 K2 = 0.03163/ 0F K3 = 0.001414/psi 1= 8 sec.
T2 = 3 sec.
'13 =0 sec.
'4 = 22 sec.
-5 = 4 sec.
-6 = 0 sec.
= 3.0 %AI
= N/A*
= 1.525 %AT 0 / %AI
= N/A*
flf(AI) negative breakpoints and slopes for OTAT are less restrictive than OPAT f2(AI) negative breakpoint and slope. Therefore, during a transient which challenges negative imbalance limits, OPAT f2(AI) limits will result in a reactor trip before OTATf 1 (Al) limits are reached. This makes implementation of an OTAT fl (Al) negative breakpoint and slope unnecessary.
CNEI-0400-203 Page 25 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Overpower AT Setpoint Parameter Values 2.9.2 Parameter Nominal Tavg at RTP Overpower AT reactor trip setpoint Overpower AT reactor trip penalty Overpower AT reactor trip heatup setpoint penalty coefficient 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 f2(AI) "positive" breakpoint f2(AI) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Nominal Value T" < 590.8 OF K4 =1.0819 K5 = 0.02 / 'F for increasing Tavg K5 =0.00 / 'F for decreasing Tavg K6 = 0.001291/OF for T > T" K6 0.0/oF for T < T"
-c1 8 sec.
'U2 3 sec.
13 0 sec.
6= 0 sec.
t7 = 10 sec.
= 35.0 %AI
= -35.0 %AI
= 7.0 %ATo/ %AI
= 7.0 %ATo/ %AI
CNEI-0400-203 Page 26 Revision 0 Catawba 2 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)
RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.12 Accumulators (TS 3.5.1) 2.12.1 Bor6n concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure >1000 psi:
Parameter Accumulator minimum boron concentration.
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 RWST minimum boron concentration.
RWST maximum boron concentration.
Limit 2,700 ppm 3,075 ppm
CNEI-0400-203 Page 27 Revision 0 Catawba 2 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
< 589.6 OF meter 3
<-589.3 OF computer 4
< 590.1 OF computer 3
< 589.9 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
>390,000 gpm
CNEI-0400-203 Page 28 Revision 0 Catawba 2 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 spei~t 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 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 MODE 6 reactivity requirement of Keffr< 0.95.
Parameter Limit Minimum boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.
2,700 ppm
CNEI-0400-203 Page 29 Revision 0 Catawba 2 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 TR 2,700 ppm 16.7-9.3.
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 < 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 2000 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 > 450 EFPD, Figure 6 may be used to determine 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 TF RWST Minimum Shutdown Volume (Includes the 48,500 gallons additional volumes listed in SLC 16.9-11)
(8.7%)
CNEI-0400-203 Page 30 Revision 0 Catawba 2 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 0F.
Parameter Limit BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 210°F BAT 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 > 450 EFPD, Figure 6 may be used to determine required BAT minimum level.
RWST minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210 TF RWST 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-0400-203 Page 31 Revision 0 Catawba 2 Cycle 18 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 450 EFPD)
This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 50.0 RCS Boron Concentration BAT Level (ppm)
(%level) 4 0.0 0 < 3 04
.0.......
0 0<300 43.0 300 < 500 40.0 35.0 500 < 700 37.0 700 < 1000 30.0 1000 < 1300 14.9 1300 <2700 9.8
> 2700 9.8 Unacceptable
- 20.0 O peration.
A cceptable O peration 1 5.0 10.0 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)
CNEI-0400-203 Page 32 Revision 0 Catawba 2 Cycle 18 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 2 Cycle 18 Maneuvering Analysis calculation file, CNC-1553.05-00-0529. Due to the size of monitoring factor data, Appendix A is controlled electronically within Duke and is not included in Duke internal copies of the COLR.
Catawba Reactor and Electrical Systems Engineering controls monitoring factor via computer files and should be contacted if questions concerning this information arise.
Appendix A is includedin the COLR transmitted to the NRC.