ML031220324

Transmittal of Core Operating Limits Report for Catawba Unit 2 Cycle 13, Revision 22

ML031220324
Person / Time
Site:	Catawba
Issue date:	03/27/2003
From:	Gordon Peterson Duke Energy Corp, Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNEI-0400-25, Rev 22
Download: ML031220324 (34)

Text

_ Duke GARY R. PETERSON OrPowere Vice President Catawba Nuclear Station A Duke Energy Company Duke Power CN01 VP / 4800 Concord Rd York, SC 29745 803 831 4251 803 831 3221 fax March 27, 2003 grpeters@duke-energy corn U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Duke Energy Corporation Catawba Nuclear Station Unit 2 Docket No.: 50-414 Core Operating Limits Report for Catawba Unit 2 Cycle 13 Revision 22 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of the Core Operating Limits Report (COLR) for Catawba Unit 2 Cycle 13. The COLR Appendix A is included with the letter to the NRC Document Control Desk as an electronic file.

The attachment and electronic file do not contain any new commitments.

Please direct any questions or concerns to George Strickland at (803) 831-3585.

G. R. Peterson Attachment i) 4ool1 www duke-energy.com

U. S. Nuclear Regulatory Commission March 27, 2003 Page 2 xc w/att: L. A. Reyes, Regional Administrator Region II R. E. Martin, NRR Senior Project Manager E. F. Guthrie, Catawba NRC Senior Resident

CNEI-0400-25 Page I of 30 Revision 22 Catawba Unit 2 Cycle 13 Core Operating Limits Report Revision 22 February 2003 Duke Power Company Date Prepared By: _XA/_ ;2/2-e/o13 Checked By:

-' /19 iz16 Checked By:

Approved By:

QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

CNEI-0400-25 Page la of 30 Revision 22 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date: Z/26/2 vo3 (Sponsor)

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( l) Inspected By/Date:

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

RES (Electrical Only) D Inspected By/Date:

RES (Reactor) Li Inspected By/Date:

MOD Inspected By/Date:

Other ( _ _ ) U Inspected By/Date:

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

RES (Electrical Only) a Inspected By/Date:

RES (Reactor) U Inspected By/Date:

MOD L Inspected By/Date:

Other ( l) Inspected By/Date:

CNEI-0400-25 Page 2 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 22 Revision 22 of the Catawba Unit 2 COLR contains limits specific to the Catawba 2 Cycle 13 reload core and may become effective any time during NO MODE between Cycles 12 and 13.

This revision must become effective prior to entering MODE 6 which starts Cycle 13.

CNEI-0400-25 Page 3 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR Revisions 1-13 N/A N/A C2C06- C2C09 Revision 14 August 1998 N/A C2CIO COLR Revision 15 October 1998 N/A C2CIO COLR rev 1 Revision 16 December 1998 N/A C2C1O COLR rev 2 Revision 17 February 2000 N/A C2CI ICOLR Revision 18 February 2001 N/A C2CI 1 COLR rev 1 Revision 19 September 2001 ALL C2C12 COLR Revision 20 September 2001 1,2,3,4,25,26,27 C2C12 COLR rev 1 Revision 21 July 2002 1-4, 5a, 5b, Sc C2C12 COLR rev 2 Revision 22 February 2003 All C2C13 COLR

CNEI-0400-25 Page 4 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report INSERTION SHEET FOR REVISION 22 Remove pages Insert Rev. 22 pages All 1-30 Appendix A*, 1-3 12 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is only included on CD with the COLR copy sent to the NRC.

CNEI-0400-25 Page 5 of 30 Revision 22 Catawba 2 Cycle 13 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 the Technical Specification 5.6.5.

The Technical Specifications that reference this report are listed below:

Tech Spec COLR COLR Section Technical Specifications COLR Parameter Section Page 3.1.1 Shutdown Margin __ Shutdown Margin 2.1 9 3.1.3 Moderator Temperature Coefficient _MTC 2.2 9 3.1.4 Rod GroupAlignment Limits Shutdown Margin _ 2.1 9 3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.1 9 Rod Insertion Limits ___ 2.3 10 3.1.6 Control Bank Insertion Limit Shutdown Margin 2.1 9 Rod Insertion Limits _ 2.4 10 3.1.8 Physics Tests Exceptions Shutdown Margin 2.1 9 3.2.1 Heat Flux Hot Channel Factor FQ 2.5 14 AFD 2.7 21 OTAT 2.8 24 Penalty Factors 2.5 16 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.6 20 Factor Penalty Factors 2.6 21 3.2.3 Axial Flux Difference__ ___ AFD 2.7 21 3.3.1 Reactor Trip System Instrumentation OTAT 2.8 24 OPAT _ 2.8 25 3.3.9 Boron Dilution Mitigation Sysster Reactor Makeup Water Flow Rate 2.9 26-3.5.1 Accumulators Max and Min Boron Conc. 2.10 26 3.5.4 Refueling Water Storage Tank _ Max and Min Boron Conc.. 2.11 26 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.12 27 3.9.1 Refueling Operations - Boron i Min Boron Concentration 2.13 27 Concentration 3.9.2 Refiuxelmg Operations - Nuclear Reactor Makeup Water Flow Rate 2.14 27 Instrumentation _

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 lCOLR Section Selected Licensing Commitment COLR Parameter Section Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.15 28

_ _ _ ___Supply -

16 9-11 Boration Systems - Borated Water Borated Water Volume and Conc. 2.16 28 Source - Shutdown for BATIRWST 16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc. 2.17 29 Source - Operating for BATIRWST

CNEI-0400-25 Page 6 of 30 Revision 22 Catawba 2 Cycle 13 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," fE Proprietary).

Revision 0 Report Date: July 1985 Not Used for C2C13

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", (_ Proprietary).

Revision 2 Report Date: March 1987 Not Used for C2C13

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

Revision: Volume I (Revision 2) and Volumes 2-5 (Revision I)

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 I 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 C2C13

CNEI-0400-25 Page 7 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 2 SER Date: October 14, 1998

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

Revision 0 Report Date: November 1991

8. DPC-NE-3002A, "FSAR 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-0 I," (DPC Proprietary).

Revision 1 SER Date: February 20, 1997

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

Revision I SER Date: November 7,1996

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

Revision 0 SER Date: April 3, 1995

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

Revision 2 SER Date: December 18, 2002

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

Revision I SER Date: April 26, 1996

CNEI-0400-25 Page 8 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-201 OA, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision I SER Date: October 1, 2002

15. DPC-NE-201 IPA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).

Revision I SER Date: October 1, 2002

CNEI-0400-25 Page 9 of 30 Revision 22 Catawba 2 Cycle 13 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 Technical Specification 5.6.5.

2.1 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.1.1 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 with Keff< 1.0 and in modes 3 and 4.

2.1.2 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.0% AK/K in mode 5.

2.1.3 For TS 3.1.4, shutdown margin shall be greater than or equal to 1.3% AK!K in mode 1 and mode 2.

2.1.4 For TS 3.1.5, shutdown margin shall be greater than or equal to 1.3% AK/K in mode I and mode 2 with any control bank not fully inserted.

2.1.5 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.

2.1.6 For TS 3.1.8, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 during Physics Testing.

2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The Moderator Temperature Coefficient (MTC) Limits are:

The MTC shall be less positive than the upper limits shown in Figure 1. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/0 F.

The EOC, ARO, RTP MTC shall be less negative than the -4.1 E-04 AK/K/0 F lower MTC limit.

2.2.2 The 300 ppm MTC Surveillance Limit is:

The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.2E-04 AK/K/0 F.

CNEI-0400-25 Page 10 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.2.3 The 60 PPM MTC Surveillance Limit is:

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

-3.85E-04 AK!KI 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) 2.3 Shutdown Bank Insertion Limit (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 226 steps. Shutdown banks are withdrawn in sequence and with no overlap.

2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.

CNEI-0400-25 Page 11 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 0.8 0 0.7 0--

0.6 U

0.5 3-0 0.4 0

E-4 0.3 0.2 0.1 0.0 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 2 ROD manual for details.

CNEI-0400-25 Page 12 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn 231 220 200 2 180 e

10

- 160 m 140 2

120

.2 0 100

°0 80

' 60 0

40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thernal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 2 ROD manual for details.

CNEI-0400-25 Page 13 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 226 Steps Fully Withdrawn at 227 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 226 Stop 110 0 0 227 Stop 111 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop 111 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 Stop 111 Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps Control Control Control Control Control Control Control Control BankA BankB BankC BankD BankA BankB BankC BankD 0 Start 0 0 0 0 Start 0 0 0 116 OStart 0 0 116 0 Start 0 0 228 Stop 112 0 0 229Stop 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 BankA BankB BankC BankD Bank A Bank B BankC BankD 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 OStart 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Start 230 230 230 Stop 114 231 231 231 Stop 115

CNEI-0400-25 Page 14 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.5 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.5.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

FQRTP *K(Z)JP for P > 0.5 F 'rP *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.5.5 and 2.5.6.

2.5.2 FQ RTP = 2.50 x K(BU) 2.5.3 K(Z) is the normalized FQ(XY,Z) as a function of core height. K(Z) for MkBW fuel is provided in Figure 3, and the K(Z) for Westinghouse RFA fuel is provided in Figure 4.

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

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2. 1:

L( FQ(XYZ)

• MQ(X,Y,Z) 2.5.5 [F1(XYZ)]OP = UMT

• MT

• TILT where:

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

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

CNEI-0400-25 Page 15 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report F~(X,YZ) = Design power distribution for FQ. FrD(X,YZ) is provided in Table 4, Appendix A, for normal operating conditions and in Table 7, Appendix A for power escalation testing during initial I startup operation.

MQ(X,Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is provided in Table 4, Appendix A for normal operating conditions and in Table 7, Appendix A for power escalation testing during initial I 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)

FD(X,Y,Z)

• MC(X,Y,Z) 2.5.6 [F'(X,Y,Z)] RPS= UMT

• MT

• TILT where:

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

FD(XY,Z) = Design power distributions for FQ. F (X,Y,Z) is provided in Table 5, Appendix A for normal operating conditions and in Table 8, Appendix A for power escalation testing during initial startup operations.

CNEI-0400-25 Page 16of30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report MC(X,Y,Z) = Margin remaining to the CFM limit in core location XY,Z from the transient power distribution. MC(X,Y,Z) is provided in Table 5, Appendix A for normal operating conditions and in Table 8, Appendix A for power escalation testing during initial startup operations.

UMT = Measurement Uncertainty (UMT = 1.05)

MT = Engineering Hot Channel Factor (MT = 1.03)

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.5.7 KSLOPE = 0.0725 where:

KSLOPE = the adjustment to the K1 value from OTAT trip setpoint required to t, L RPS compensate for each 1% that FQ (XY,Z) exceeds FQ (X,YZ) 2.5.8 FQ(XY,Z) Penalty Factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

CNEI-0400-25 Page 17 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(XY,Z) as a Function of Core Height for MkBW Fuel 1.200 -

(0 0,1.00) (6.0, 1.00) (12.0,1.00) 1.000 1 0.800

- 0.600-0.400 t Core Height (0) K(Z) 0.200 - 00 1.000 6.0 1.000 1 12.0 1.000 0 000 I l I I I 0.0 2.0 4.0 6.0 80 10.0 12.0 Core Height (ft)

CNEI-0400-25 Page 18 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(XY,Z) as a Function of Core Height for RFA Fuel 1.200 -

(0.0, 1.00) (6.0, 1.00) (12.0, 1.00) 1.000 1 I 0.800

"' 0.600 0.400 Core Height 0.200 - (ft) 14Z) 0.0 1.00 60 1.00 12.0 1.00 0.000- I I I I I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

CNEI-0400-25 Page 19 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FA&H(XY) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup FQ(X,Y,Z) FAH(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 2.00 475 2.00 2.00 500 2.00 2.00 509 2.00 2.00 524 2.00 2.00 534 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 FAE1(X,Y) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-25 Page 20 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(XY) (TS 3.2.2)

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

2.6.1 [F5SH (XY)]Lc = MARP (X,Y) * [1.0 + RH * (1.0 - P)]

where:

[F.'H (X,Y)]Lco is defined as the steady-state, maximum allowed radial peak.

[FAH(X'Y)]LC0 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% that the measured radial peak, F^m, (X,Y), exceeds the limit.

(RRH = 3.34, 0.0 < P < 1.0)

The following parameters are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.

2.6.2 [FL (XY)]SURV = FAH(XY) x MAH(XY)

UMR x TILT where:

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

FkL (XY)suRV includes allowances for calculational and measurement uncertainty.

D D F (X,Y) = Design power distribution for FAN. FAH (XY) is provided in Table 6, Appendix A for normal operation and in Table 9,

CNEI-0400-25 Page 21 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Appendix A for power escalation testing during initial startup operation.

MAH(XY) = The margin remaining in core location XY relative to the Operational DNB limits in the transient power distribution.

MAIH(X,Y) is provided in Table 6, Appendix A for normal operation and in Table 9, Appendix A for power escalation testing during initial startup operation.

UMR = Uncertainty value for measured radial peaks. UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable MAH(X,Y).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.3 RRH = 3.34 where:

RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, FkL (XY) exceeds its limit. (0 < P < 1.0) 2.6.4 TRH = 0.04 where:

TRH = Reduction in OTAT K1 setpoint required to compensate for each 1% that the measured radial peak, FAHI(XY) exceeds its limit.

2.6.5 FAII(XY) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.

2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.

CNEI-0400-25 Page 22 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

MkBW Fuel MARPs 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 1678 1.708 1.772 1 829 1 878 1.922 1.852 1.798 1.714 1.636 1.535 1.211 1147 120 1 675 1.706 1.766 1.821 1.867 1886 1.829 1 806 1.731 1.655 1.540 1.182 1.117 2 40 1 679 1.708 1.763 1.815 1.853 1.841 1786 1.769 1711 1.655 1.557 1.168 1.106 3 60 1682 1.709 1.760 1.804 1.812 1.797 1.743 1 722 1 669 1.619 1.556 1.202 1.131 4 80 1 684 1 708 1.754 1.792 1.766 1.750 1 699 1.681 1.630 1.581 1.516 1.232 1.186 6.00 1.686 1.708 1 745 1.761 1.715 1.703 1 654 1 638 1.590 1.544 1.476 1 206 1.156 7.20 1.686 1 704 1 733 1 714 1 666 1.649 1603 1 587 1.542 1 503 1 438 1.177 1.127 8 40 1 681 1 692 1 702 1 660 1.612 1.595 1.549 1.537 1.494 1 454 1.387 1.145 1.100 9 60 1 673 1 677 1 651 1 601 1.558 1.544 1 502 1.A91 1 450 1413 1.350 1.121 1 076 10 80 1 662 1.649 1 603 1 550 1.503 1.491 1.A48 1.441 1.404 1 369 1.307 1.086 1.043 12 00 1.636 1.608 1.553 1 505 1 456 1.446 1.408 1.403 1.370 1.340 1.286 1.072 1.027 RFA Fuel MARPs 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 3.25 0 12 1 847 1.882 1 947 1.992 1.974 2 068 2.09 2.049 1.972 1.9 1.778 1.315 1.246 1.20 1.843 1 879 1.938 1.992 1.974 2.068 2.054 2 012 1.935 1 862 1 785 1 301 1.224 240 1 846 1 876 1.931 1.981 1.974 2.068 2.025 1.981 1.903 1.832 1.757 1.468 1.456 3 60 1.843 1 869 1.92 1.964 1.974 2.068 2.005 1.968 1.892 1.82 1.716 1.471 1.431 480 1 838 1.868 1.906 1 945 1.974 2006 1.945 1.925 1.862 1 802 1.725 1.326 1.285 600 1 834 1.856 1.891 1.921 1.946 1.934 1.878 1.863 1.802 1.747 1.673 1.384 1 317 7.20 1.828 1.845 1.871 1.893 1.887 1.872 1.809 1.787 1.732 1.681 1 618 1.316 1 277 840 1.823 1.829 1.847 1.857 1.816 1.795 1.739 1.722 1 675 1.63 1.551 1.247 1.211 960 1.814 1.812 1.809 1.792 1.738 1.724 1 678 1.665 1.621 1.578 1.492 1.191 1.137 10 80 1.798 1.784 1.761 1.738 1.697 1 682 1 626 1.605 1.558 1.512 1.43 1.149 1.097 11.40 1 789 1 765 1.725 1.684 1.632 1.614 1.569 1.557 1.51 1.466 1.392 1.113 1.06

CNEI-0400-25 Page 23 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-18, 100) i RA (+10, 100)

Unacceptable Operation I Jnacceptable Operation 90 a) 80 0

1o 70 C-Acceptable Operation 60 50 0P

-S (-36, 50) (+21, 50)

C4 I.. 40 +

C)e 0..

30 +

20 +

10 -

I I I O iI 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 2 ROD manual for operational AFD limits.

CNEI-0400-25 Page 24 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.8 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.8.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Overtemperature AT reactor trip setpoint KI = 1.1953 Overtemperature AT reactor trip heatup setpoint K2 = 0.031 63/OF penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001414/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator TI = 8 sec.

for AT av = 3 sec.

t3 0.= s Time constant utilized in the lag compensator for AT = 0 sec.

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

for Tavg x5 = 4 sec.

Time constant utilized in the measured Tag lag x16 = ° sec.

compensator f1 (AI) "positive" breakpoint =3.0%Al fl(Al) "negative" breakpoint = -39.9 %AI fl(Al) "positive" slope = 1.525 %ATO/ %AI fl (Al) "negative" slope = 3.910 %ATO/ %AI

CNEI-0400-25 Page 25 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.8.2 Overpower AT Setpoint Parameter Values Parameter Nominal Value Overpower AT reactor trip setpoint K4 = 1.0819 Overpower AT reactor trip heatup setpoint K6 = 0.001291/OF penalty coefficient (for T>T")

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

compensator for AT n2 = 3 sec.

Time constant utilized in the lag ¶3 = 0 sec.

compensator for AT Time constant utilized in the measured Tavg T6 = 0 sec.

lag compensator Time constant utilized in the rate-lag T7 = 10 sec.

controller for Tavg f2(AI) "positive" breakpoint = 35.0 %AI f2 (AI) "negative" breakpoint = -35.0 %AI f2 (AI) "positive" slope = 7.0 %ATO/ %AI f2 (AI) "negative" slope = 7.0 %ATW %AI

CNEI-0400-25 Page 26 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flow rate limits:

Applicable Mode Limit Mode 3 <150 gpm Mode 4 or 5 < 70 gpm 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes I and 2, and mode 3 with RCS pressure

>1000 psi:

Parameter Limit Cold Leg Accumulator minimum boron concentration. 2,500 ppm Cold Leg Accumulator maximum boron concentration. 3,075 ppm 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 Boron concentration limits during modes 1, 2, 3, and 4:

Parameter Limit Refueling Water Storage Tank minimum boron 2,700 ppm concentration.

Refueling Water Storage Tank maximum boron 3,075 ppm concentration.

CNEI-0400-25 Page 27 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.12 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.12.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.

Parameter Limit Spent fuel pool minimum boron concentration. 2,700 ppm 2.13 Refueling Operations - Boron Concentration (TS 3.9.1) 2.13.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keff <

0.95.

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

2.14 Refueling Operations - Nuclear Instrumentation (TS 3.9.2) 2.14.1 Reactor Makeup Water Pump Flow rate Limit:

Applicable Mode Limit Mode 6 < 70 gpm

CNEI-0400-25 Page 28 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.15 Standby Makeup Pump Water Supply - Boron Concentration (SLC-16.7-9.3) 2.15.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes 1, 2, and 3.

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

2.16 Borated Water Source- Shutdown (SLC 16.9-11) 2.16.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Mode 4 with any RCS cold leg temperature < 285 0 F, and Modes 5 and 6.

Parameter Limit Boric Acid Tank minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required 2,000 gallons to maintain SDM at 680 F Boric Acid Tank Minimum Contained Shutdown 13,086 gallons Volume (Includes the additional volumes listed in (14.9%)

SLC 16.9-11)

NOTE: When cycle burnup is > 450 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.

Refueling Water Storage Tank minimum boron 2,700 ppm concentration Volume of 2,700 ppm boric acid solution required 7,000 gallons to maintain SDM at 68 OF Refuieling Water Storage Tank Minimum 48,500 gallons Contained Shutdown Volume (Includes the (8.7%)

additional volumes listed in SLC 16.9-1 1)

CNEI-0400-25 Page 29 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report 2.17 Borated Water Source - Operating (SLC 16.9-12) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Modes 1, 2, and 3 and Mode 4 with all RCS cold leg temperatures > 285°F.

Parameter Limit Boric Acid Tank minimum boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required 13,500 gallons to maintain SDM at 2850 F Boric Acid Tank Minimum Contained Shutdown 25,200 gallons Volume (Includes the additional volumes listed in (45.8%)

SLC 16.9-12)

NOTE: When cycle burnup is > 450 EFPD, Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.

Refueling Water Storage Tank minimum boron 2,700 ppm concentration Volume of 2,700 ppm boric acid solution required 57,107 gallons to maintain SDM at 285 TF Refueling Water Storage Tank Minimum 98,607 gallons Contained Shutdown Volume (Includes the (22.0%)

additional volumes listed in SLC 16.9-12)

CNEI-0400-25 Page 30 of 30 Revision 22 Catawba 2 Cycle 13 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid when the cycle burnup is greater than 450 EFPD)

This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 500 .

RCS Boron 450 - Concentration BAT Level 7i j (ppm) (0/cievel) 400 *1t -< 300 1 43.0 300 < 500 40.0 350 500< 700 37.0 O j, il.,!illl'1000 < 1300 14.9

) 300 ' (.  : 1300 <2700 9.8 c0!-1L~. "ijIfiH >2700 9.8

- 250-IUnacceptable iibI Uncepal Acceptable Operation j, 200 Operation ,il, 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)

CNEI-0400-25 Appendix A, Rev. 22 Catawba 2 Cycle 13 Core Operating Limits Report Appendix A Catawba 2 Cycle 13 Monitoring Factors NOTE: Data contained in Appendix A was generated in the Catawba 2 Cycle 13 Maneuvering Analysis calculation file, CNC-1 553.05-00-0372. The Plant Nuclear Engineering I Section will control this information via computer file(s) and should be contacted if there is a need to access this information.