ML032250049

Core Operating Limits Report (COLR) Catawba Unit 1 Cycle 14, Revision 23

ML032250049
Person / Time
Site:	Catawba
Issue date:	08/04/2003
From:	Jamil D Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032250049 (30)

Text

f Duke rTPower.

A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN0I VP York, SC 29745-9635 803 831 4251 803 831 3221 fax August 4, 2003 U.S. Nuclear Regulatory Commission ATTENTION:

Document Control Desk Washington, D.C. 20555-0001

Subject:

Duke Energy Corporation Catawba Nuclear Station Unit 1 Docket No.: 50-413 Core Operating Limits Report (COLR)

Catawba Unit 1 Cycle 14, Revision 23 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of the Core Operating Limits Report for Catawba Unit 1 Cycle 14 revision 23.

This letter and attachment do not contain any new commitments.

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

Sincerely, D. M. Jamil Attachment A6D(

www. duke-energy. corn

U. S. Nuclear Regulatory Commission August 4, 2003 Page 2 xc w/att:

L. A. Reyes, Regional, Administrator USNRC, Region II R. E. Martin, NRC Senior Project Manager USNRC, ONRR E. F. Guthrie Senior Resident Inspector (Catawba)

CNEI-0400-24 Page 1 of 31 Revision 23 Catawba Unit 1 Cycle 14 Core Operating Limits Report Revision 23 July 2003 Duke Power Company Prepared By:

11-
.

--d&114 'It/ al f

- -I,?(= -I

Date Checked By:

Checked By:

g~o Tut4 3 Approved By:

Ip. J~ /~

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

CNEI-0400-24 Page laof31 Revision 23 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:

(Sponsor)

(Sponsor)

Date:

71:/301 A, CATAWBA Inspection Waived MCE (Mechanical & Civil) x Inspected By/Date:

RES (Electrical Only) 5 Inspected By/Date:

RES (Reactor) 11 Inspected By/Date:

MOD K

Inspected By/Date:

Other (

)

0 Inspected By/Date:

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

RES (Electrical Only)

Inspected By/Date:

RES (Reactor) 0 Inspected By/Date:

MOD Inspected By/Date:

Other (

)

0 Inspected By/Date:

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

RES (Electrical Only) 0 Inspected By/Date:

RES (Reactor)

C Inspected By/Date:

MOD 0

Insected BvyDate:

Other (

)

C Inspected By/Date:

CNEI-0400-24 Page 2 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 23 l

Revision 23 of the Catawba Unit 1 COLR contains new end-of-cycle Moderator Temperature Coefficient limits and should be implemented as soon as possible.

CNEI-0400-24 Page 3 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report REVISION LOG Revision 0-1 2-5 6-8 9-11 12-14 15-17 18 EI Date Superceded Superceded Superceded Superceded Superceded Superceded October 2000 February 2001 September 2001 September 2001 April 2002 July 2003 Paaes Affected N/A N/A N/A N/A N/A N/A 1 -26 Appendix A 1-4, 25, 26 1-4, 25, 26 1-4, 25, 26a, 26b ALL ALL COLR CIC07 C1C08 C1C09 Cicl0 Cicil ClC12 C1C13 (Orig. Issue)

CIC13 (Revision)

ClC13 (Revision)

CIC13 (Revision)

CIC14 CIC14 (Revision) 19 20 21 22 23

CNEI-0400-24 Page 4 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report I

INSERTION SHEET FOR REVISION 23 Remove pages Pages 1-31 Insert Rev. 23 pages Pages 1-31 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is only included in the COLR copy sent to the NRC.

CNEI-0400-24 Page 5 of 31 Revision 23 Catawba I Cycle 14 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Specifications that reference this report are listed below:

TS COLR COL Section Technical Specifications COLR Parameter Section R

Page 3.1.1 Shutdown Margin Shutdown Margin 2.1 1

9 3.1.3 Moderator Temperature Coefficient MTC 2.2 9

3.1.4 Rod Group Atigment Limits Shutdown Margin 2.1 I

9 3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.1 9

J Rod Insertion Limits

_2.3 10 3.1.6 Control Bank Insertion Limit Shutdown Margin l

2.1 I

9 Rod Insertion Limits 10 3.1.8 Physics Tests Exceptions Shutdown Margin 2.1 9

3.2.1 Heat Flux Hot Channel Factor FQ 2.5 14 lAFD 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 System Reactor Makeup Water Flow Rate 2.9 26

_ _.~~~~

~

3.5.1 Accumulators Max and Min Boron Conc.

2.10 26 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc..

2.11 26 3.7.15 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.12 1

27 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.13 27 Concentration 3.9.2 Refueling Operations - Nuclear Reactor Makeup Water Flow Rate 2.14 27 Instrumentation i

The Selected License Commnitments that reference this report are listed below:

SLC COLR COL Section Selected Licensing Commitment COLR Parameter Section R

Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.15 28

_orao Systems-

_e W

r Supply 16.9-11 Boration Systems - Borated Water Borated Water Volume and Conc.

2.16 28

! Source - Shutdown for BAT/RWST 16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc.

2.17 29 Source - Operating for BAT/RWST_

CNEI-0400-24 Page 6 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC are as follows.

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (

Proprietary).

Revision 0 Report Date: July 1985 Not Used for C1C14

2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, "(! Proprietary).

Revision 0 Report Date: August 1985 Note: Amendments to this report are included in Ref. 12.

3. WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", (! Proprietary).

Revision 2 Report Date: March 1987 Not Used for C1C14

4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (! Proprietary).

Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)

Report Date: March 1998

5. BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recalculating Steam Generator Plants," (B&W Proprietary).

Revision 1 SER Date: January 22, 1991 Revision 2 SER Dates: August 22, 1996 and November 26, 1996.

Revision 3 SER Date: June 15, 1994.

Not Used for C1C14

CNEI-0400-24 Page 7 of 31 Revision 23 Catawba 1 Cycle 14 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 3 SER Date: February 5, 1999

9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).

Revision I SER Date: February 20, 1997

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

Revision 1 SER Date: November 7, 1996

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

Revision 0 SER Date: April 3, 1995

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

Revision 0 SER Date: September 22, 1999

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

Revision I SER Date: April 26, 1996

CNEI-0400-24 Page 8 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision 0 Report Date: June 1985

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

Revision 0 Report Date: March 1990

CNEI-0400-24 Page 9 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified in Section 1.1.

2.1 Shutdown Margin - SDM (T S 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% AKIK 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 1 and mode 2 with any control bank not fully inserted.

2.1.5 For TS 3.1.6, shutdown margin shall be greater than or equal to 1.3% 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 (IES 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/0F.

The EOC, ARO, RTP MTC shall be less negative than the 4.3E-04 AK/K/0F 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 -3.65E-04 AK/K/0F.

CNEI-0400-24 Page 10 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.2.3 The 60 PPM MTC Surveillance Limit is:

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

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

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

CNEI-0400-24 Page 11 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 W

a-E c0 I..

0" 0

0.9 0.8 0.7 0.6 0.5 0.4 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 1 ROD manual for details.

CNEI-0400-24 Page 12 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 1 180

.- 160 i

140 c4 c 120

.2 0

100

.2 80 co c 60 a 40 20 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 1 ROD manual for details.

CNEI-0400-24 Page 13 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 226 Steps Control Control Control Control BankA BankB BankC BankD Fully Withdrawn at 227 Steps Control Control Control Control Bank A Bank B Bank C Bank D OStart 0

0 0

116 o Start 0

0 226Stop 110 0

0 226 116 0 Start 0

226 226Stop 110 0

226 226 116 o Start 226 226 226 Stop 110 0 Start 0

0 0

116 o Start 0

0 227Stop 111 0

0 227 116 o Start 0

227 227Stop 1I1 0

227 227 116 0 Start 227 227 227Stop 111 Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank B Bank C Bank D Fully Withdrawn at 229 Steps Control Control Control Control Bank A Bank B Bank C Bank D O Start 0

0 0

116 o Start 0

0 228Stop 112 0

0 228 116 OStart 0

228 228 Stop 112 0

228 228 116 OStart 228 228 228 Stop 112 O Start 0

0 0

116 o Start 0

0 229Stop 113 0

0 229 116 o Start 0

229 229Stop 113 0

229 229 116 OStart 229 229 229Stop 113 Fully Withdrawn at 230 Steps Control Control Control Control Bank A Bank B Bank C Bank D Fully Withdrawn at 231 Steps Control Control Control Control Bank A Bank B Bank C Bank D O Start 0

0 0

116 OStart 0

0 230 Stop 114 0

0 230 116 o Start 0

230 230 Stop 114 0

230 230 116 o Start 230 230 230 Stop 114 O Start 0

0 0

116 OStart 0

0 231 Stop 115 0

0 231 116 0 Start 0

231 231 Stop 115 0

231 231 116 OStart 231 231 231 Stop 115

CNEI-0400-24 Page 14 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.5 Heat Flux Hot Channel Factor - FQ(X,YZ) (rS 3.2.1) 2.5.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F RTP *K(Z)/P for P > 0.5 F RTP *K(Z)/0.5 for P < 0.5

where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,YZ) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the limits.

The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.5.5 and 2.5.6.

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

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

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:

L FQ(X,YZ)

• M0(XY,Z) 2.5.5

[FQ(XYZ)]OP =

UMT

• MT

• TILT where:

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

FQ (XY,Z)0 p includes allowances for calculational and measurement uncertainties.

CNEI-0400-24 Page 15 of31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report FD'(XYZ) =

MQ(X,Y,Z)

=

Design power distribution for FQ. F, (X,Y,Z) is provided in Table 4, Appendix A, for normal operating conditions and in Table 7, Appendix A for power escalation testing during initial startup operation.

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

UMT = Total Peak Measurement Uncertainty. (UMT = 1.05)

MT = Engineering Hot Channel Factor. (MT = 1.03)

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.5.6

[FQ(X,YZ)]

=

FQ(X,Y,Z)

• MC(X,Y,Z)

UMT

• MT

• TILT where:

[F(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. [FL(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.

D~XYZ Mc(X,Y,Z)

=

Design power distributions for FQ. FQ(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 startup operations.

Margin remaining to the CFM limit in core location X,YZ from the transient power distribution. MC(X,Y,Z) is provided in Table 5, Appendix A for normal operating conditions and in Table 8, Appendix A for power escalation testing during initial startup operations.

UMT = Measurement Uncertainty (UMT = 1.05)

CNEI-0400-24 Page 16 of31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report MT = Engineering Hot Channel Factor (MT = 1.03)

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

KSLOPE = the adjustment to the KI value from OTAT trip setpoint required to compensate for each 1% that FQ (X,Y,Z) exceeds FQ (X,Y,Z) 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-0400-24 Page 17 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(XY,Z) as a Function of Core Height for MkBW Fuel 1.200 1.000 0.800 N 0.600 0.400 0.200 0.000 (0.0, 1.00)

(6.0, 1.00)

(12.0, 1.00)

Core Height

00)

K(Z) 0.0 1.000 6.0 1.000 12.0 1.000 I

I I

I I

0.0 2.0 4.0 6.0 Core Height (ft) 8.0 10.0 12.0

CNEI-0400-24 Page 18 of31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA Fuel 1.200 -

(0.0, 1.00)

(6.0, 1.00)

(12.0, 1.00) 1.0004 0.800 -

2 0.600-0.400 Core Height 0.200 (ft)

K(Z) 0.0 1.000 6.0 1.000 12.0 1.000 0.000 i

I i

0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

CNEI-0400-24 Page 19 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Table 2 FQ(X,Y,Z) and Fm(XY) 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 75 100 125 150 175 200 225 250 275 300 400 500 530 FQ(XY,Z)

Penalty Factor(%)

2.00 2.21 2.08 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 FH(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 Note: Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of the table shall use a 2%

penalty factor for both FQ(X,Y,Z) and FAH(XY) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-24 Page 20 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(XY) (TS 3.2.2)

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

2.6.1

[FAH (X,Y)]LCo = MARP (X,Y) * [1.0 +

I

• (1.0 - P)]

where:

[FLH (X, y)]Lco is defined as the steady-state, maximum allowed radial peak.

[FL (XI Y)]

uncertainty.

includes allowances for calculation/measurement 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, F2mH (X,Y), exceeds the limit.

(RRH = 3.34, 0.O < P < 1.0)

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

2.6.2 [F (XY URV -

FAH(XY)x MAH(XY)

UMR x TILT where:

[ FL (X,Y)]

= Cycle dependent maximum allowable design peaking factor that ensures that the F.(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

FL, (Xy)suRv includes allowances for calculational and measurement uncertainty.

FAH (X,Y) = Design power distribution for FAH FD (X,Y) is provided in Table 6, Appendix A for normal operation and in Table 9,

CNEI-0400-24 Page 21 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Appendix A for power escalation testing during initial startup operation.

MaH(X,Y) = 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 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 M4H(XY).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

NOTE:

[F H(X,Y)]SURV is the parameter identified as [FAH(X,Y)]MAX in DPC-NE-201 1PA.

2.6.3 RRH= 3.34 where:

RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, Fm (X,Y) 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, Fm(X,Y) exceeds its limit.

2.6.5 FAH(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.

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

CNEI-0400-24 Page 22 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

MkBW and RFA Fuel MARPs 100% Full Power 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 1.678 1.708 1.772 1.829 1.878 1.922 1.852 1.798 1.714 1.636 1.535 1.211 1.147 1.20 1.675 1.706 1.766 1.821 1.867 1.886 1.829 1.806 1.731 1.655 1.540 1.182 1.117 2.40 1.679 1.708 1.763 1.815 1.853 1.841 1.786 1.769 1.711 1.655 1.557 1.168 1.106 3.60 1.682 1.709 1.760 1.804 1.812 1.797 1.743 1.722 1.669 1.619 1.556 1.202 1.131 4.80 1.684 1.708 1.754 1.792 1.766 1.750 1.699 1.681 1.630 1.581 1.516 1.232 1.186 6.00 1.686 1.708 1.745 1.761 1.715 1.703 1.654 1.638 1.590 1.544 1.476 1.206 1.156 7.20 1.686 1.704 1.733 1.714 1.666 1.649 1.603 1.587 1.542 1.503 1.438 1.177 1.127 8.40 1.681 1.692 1.702 1.660 1.612 1.595 1.549 1.537 1.494 1.454 1.387 1.145 1.100 9.60 1.673 1.677 1.651 1.601 1.558 1.544 1.502 1.491 1.450 1.413 1.350 1.121 1.076 10.80 1.662 1.649 1.603 1.550 1.503 1.491 1.448 1.441 1.404 1.369 1.307 1.086 1.043 12.00 1.636 1.608 1.553 1.505 1.456 1.446 1.408 1.403 1.370 1.340 1.286 1.072 1.027

CNEI-0400-24 Page 23 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-20,100)

We

(+10,100)

Unacceptable Operation Unacceptable Operation 90 80 0

70 Acceptable Operation 60 50

(-36, 50)

(+21, 50) o 40 0~ ~ ~ ~ ~ ~~~~~3

-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-0400-24 Page 24 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.8 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.8.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Overtemperature AT reactor trip setpoint Kl = 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.03340/OF penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator X l = 8 sec.

for AT TN =

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

'2 A *-.

T3 = 0 sec.

T4 = 22 sec.

T5 = 4 sec.

t6 = 0 sec.

= 19.0 %Al

= N/A*

= 1.769 %ATo/ %Al

= N/A*

The fl (Al) "negative" breakpoint and the fl (Al) "negative" slope are not applicable since the fl (Al) function is not required below the fl (Al) "positive" breakpoint of 19.0% Al.

CNEI-0400-24 Page 25 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report 2.8.2 Overpower AT Setpoint Parameter Values Parameter Overpower AT reactor trip setpoint 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 f2(AI) "positive" breakpoint f2(AI) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Nominal Value K4 = 1.0864 K6 = 0.001 179/OF T = 8 sec.

T2 = 3 sec.

T3 = 0 sec.

T6 = 0 sec.

T7 = 10 sec.

=35.0%AI

= -35.0 %AI

= 7.0 %AT0/ %AI

= 7.0 %ATO/ %AI

CNEI-0400-24 Page 26 of 31 Revision 23 Catawba I Cycle 14 Core Operating Limits Report 2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flow rate limits:

Applicable Mode Mode 3 Mode 4 or 5 Limit

< 150 gpm

<70 gpm 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure

>1000 psi:

Parameter Cold Leg Accumulator minimum boron concentration.

Cold Leg Accumulator maximum boron concentration.

Limit 2,500 ppm 2,975 ppm 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 Boron concentration limits during modes 1, 2, 3, and 4:

Parameter Refueling Water Storage Tank minimum boron concentration.

Refueling Water Storage Tank maximum boron concentration.

Limit 2,700 ppm 2,975 ppm

CNEI-0400-24 Page 31 of 31 Revision 23 Catawba 1 Cycle 14 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke and is not included in the Duke internal copies of the COLR. The Catawba Reactor and Electrical Systems Engineering Section controls this information via computer files and should be contacted if there is a need to access this information.

Appendix A is included in the COLR copy transmitted to the NRC.