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Duke Energy Corporation, Catawba Nuclear Station Unit 2, Core Operating Limits Report (COLR) Catawba Unit 2 Cycle 13, Revision 25
ML042020394
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 07/07/2004
From: Jamil D
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNEI-0400-25, Rev 25
Download: ML042020394 (36)
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V

^ Duke D.M. JAMIL hSPowere Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax July 7, 2004 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 (COLR)

Catawba Unit 2 Cycle 13, Revision 25 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of the Core Operating Limits Report for Catawba Unit 2 Cycle 13 Revision 25.

This letter and attachment do not contain any new commitments.

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

Sincerely,

,'g q,'A a D. M. Jamil Attachment Dbo www. duke-energy. corn

^ r U. S. Nuclear Regulatory Commission July 7, 2004 Page 2 xc w/att: W. D. Travers, Regional, Administrator USNRC, Region II S. E. Peters, NRR Project Manager (CNS)

USNRC, ONRR E. F. Guthrie Senior Resident Inspector (CNS)

Z V.

CNEI-0400-25 Page I of 34 Revision 25 Catawba Unit 2 Cycle 13 Core Operating Limits Report Revision 25 May 2004 Duke Power Company Date Prepared By: 1/2, Avy Checked By:

Checked By: eA~f A(,U-Approved By:

Wf- S12A0\ °4 QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

- r _

. x i CNEI-0400-25 Page 2 of 34 Revision 25 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: bw.4.-NL Date: '5\2.\ao 4 (Sponsor) '

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

RES (Electrical Only) Pe Inspected By/Date:

RES (Reactor) i Inspected By/Date:

MOD 15 Inspected By/Date:

Other ( ) X [ Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) 0 Inspected By/Date:

RES (Electrical Only) 0 Inspected By/Date:

RES (Reactor) Li Inspected By/Date:

MOD L] Inspected By/Date:

Other ( D)0 Inspected By/Date:

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

RES (Electrical Only) UI Inspected By/Date:

RES (Reactor) ,! Inspected By/Date:

MOD l! Inspected By/Date:

Other ( ,

I) Inspected By/Date:

CNEI-0400-25 Page 3 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 25 l Revision 25 of the Catawba Unit 2 COLR contains new end-of-cycle (EOC) moderator temperature coefficient (MTC) limits. These limits should be implemented prior to June 30, 2004.

CNEI-0400-25 Pagc 4 of 34 Revision 25 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 C2C1O COLR Revision 15 October 1998 N/A C2C 10 COLR rev I Revision 16 December 1998 N/A C2CIO COLR rev 2 Revision 17 February 2000 N/A C2CII COLR Revision 18 February 2001 N/A C2C II COLR rev I Revision 19 September 2001 N/A C2C12 COLR Revision 20 September 2001 N/A C2C12 COLR rev I Revision 21 July 2002 N/A C2C12 COLR rev 2 Revision 22 February 2003 N/A C2C13 COLR All Revision 23 January 2004 C2C13 COLR rev. I (except Appendix A)

All C2C13 COLR rev. 2 Revision 24 March 2004 (except Appendix A)

All Revision 25 May 2004 C2CI3 COLR rev. 3 (except Appendix A)

CNEI-0400-25 Page 5 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report INSERTION SHEET FOR REVISION 25 I Remove pages Insert Rev. 25 pages Pages 1-34 Pages 1-34

  • 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.

f 14 CNEI-0400-25 Page 6 of 34 Revision 25 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 Technical Specification 5.6.5. The Technical Specifications that reference this report are listed below:

TS COLR COL Section Tcchnical Specifications COLR Parameter Scction R Page 2.1.1 Reactor Core Safety Limits RCS Temperature and Pressure 2.1 10

__ ______ ___ _ Safety-Limits _______

3._.1 _ ShutdownMargin _ Shutdowvn Margin _h2.2 _ 10 3.1.3 _ Moderator Temperature Coefficient _ MTC 12 3.1.4 j Rod Group Alignment Limits IShutdown Margin 12.2 1 10 3.1.5 iShutdown Bank Insertion Limit f ShutdownMargin 2.2 10

__ __ __ I__

RodInsertionLimits 2.4 12 3.1.6 Control Bank insertion Limit Shutdown Margin 2.2 1 10

_ ___ __ __ _ _ _ l Rodnsertion Limits-___ _ 2.5 12 3.1.8 Physics Tests Exceptions __IShutdown Margin 2.2 10 3.2.1 Heat Flux Hot Channel Factor  ! FQ 2.6 16 AFD 2.8 23 OTAT 2.9 26 Penalty Factors 2.6 16 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 22 Factor Penalty Factors 2.7 22 3.2.3 Axial Flux Difference AFD 2.8 23 3.3.1 ReactorTrip System Instrumentation OTAT 2.9 26

_ __ _ OPAT 2.9 26 3.3.9 Boron Dilution MitigationSystemn Reactor Makeup Water Flow Rate 2.10 28_

3.4.1 RCS Pressure, Temperature and X RCS Pressure, Temperature and 2.11 28 Flow limits for DNB l Flow 3.5.1 l Accumulators _ _ ___ Max and Min Boron Conc. 2.12. 28 3.5.4 Refueling Water Storage Tank _ Max and Min Boron Conc. 2.13 i 28 3.7.15 _ ipent Fuel Pool Boron Concentration Min Boron Concentration 2.14 30 3.9.1 RefuelingOperations-Boron Min Boron Concentration 2.15 .30 3.9.2 Concentration Refueling Operations - Nuclear I Reactor Makeup Water Flow Rate 2.16, i

30 Instrumentation 5.6.5 Core Operating Limits Report Analytical Methods 1.1 7 (COLR) !_!

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

SLC [ j lCOLR [COLR Section Selected Licensing Commitment COLR Parameter Section Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.17 31

-I

__________ _____ uppjy _ _ _ _ _ _ ______

16.9-11 Boration Systems - Borated Water Borated Water Volume and Conc. 2.18 31

_Source - Shutdown _ for BAT/RWST ____

16.9-12 Boration Systems - Borated Water Borated Water Volume and Conc. l 2.19 r 32 Source - Operating for BAT/RWST l I

T.

CNEI-0400-25 Page 7 of 34 Revision 25 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," (W 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, " (A Proprietary).

Revision 0 Report Date: August 1985

3. XVCAP-10266-P-A, "THE 1981 'VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", (W 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," (AV Proprietary).

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

Report Date: March 1998

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

Revision 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 8 of 34 Revision 25 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 3 SER Datc: September 24,2003

7. DPC-NE-300 1PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).

Revision 0 Report Date: November, 1991, republished December 2000

8. DPC-NE-3002A, "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 I 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

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 9 of 34 Revision 25 Catawba 2 Cycle 13 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 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 10 of 34 Revision 25 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 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 I 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 I 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 I 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-0400-25 Pagc 11 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN TIllS AREA 660 1 640 240ps ia 0 630 <<

610 1 -<

600 . ________ -_ _ 1945 psi\

590 l ACCEPTABLE 580 0.2 0 0.6_.8_10_1.

0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power

CNEI-0400-25 Page 12 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:

- The MTC shall be less positive than the upper limits shown in Figure 2. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/ 0 F.

The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/K/IF lower MTC limit.

2.3.2 The 300 ppm MTC Surveillance Limit is:

The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/IF.

2.3.3 The 60 PPM MTC Surveillance Limit is:

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

-4.125E-04 AK/K/ 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 226 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-0400-25 Page 13 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 -

Unacceptable Operation C.' 0.8 -

C L, 0.7 -

0.6 -

Ed 0.5 -

0.4 - Acceptable Opera tion s- -

0 ~ 0.3 -

C.

0.2 -

0.1 -

I It _ I I, _

0.0 - _ -i- 1 I- 1 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 14 of 34 Revision 25 Catavba 2 Cycle 13 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum - 23 1) 231 220 200 0¢ 180

-5 160 c 140 e)

C 120

.2 o 100

°2 C) 80

- 60 0

W 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thernal 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'CCRIL = 2.3(P) +47 {0 *P

  • 80}

Bank CB RIL = 2.3(P) + 163 {0

  • P
  • 29.6}

it'here P = %Rated Thermal Powver NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit 2 ROD manual for details.

CNEJ-0400-25 Page 15 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Fully Vithdrawn at 223 Steps Control Control Control Control Control Control Control Control Bank A Bank B BankC BankD Bank A Bank B BankC BanklD O Start 0 0 *0 O Start 0 0 0 116 0 Start 0 0 116 OStart 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Stan 0 223 116 0 Start 0 222 222 Stop 106 0 223 223 Stop 107 0 222 222 116 0 Start 223 223 116 0 Start 222 222 222 Stop 106 223 223 223 Stop 107 Fully Withdraw n at 224 Steps Fully Withdrawn at 225 Steps Control Control Control Control Control Control Control Control Bank A Bank n Bank C Bank D Bank A Bank B BankC BankfD OStan 0 0 0 OStart 0 0 0 116 0 Start 0 0 116 OStart 0 0 224 Stop 108 0 0 225 Stop 109 0 0 224 116 0 Start 0 225 116 0 Start 0 224 224 Stop 108 0 225 225 Stop 109 0 224 224 116 0 Start 225 225 116 0 Start 224 224 224 Stop 108 225 225 225 Stop 109 Fully Withdrawn at 226 Steps Fully Withdrawn at 227 Steps Control Control Control Control Control Control Control Control BankA Bank B Bank C Bank D Bank A Bank B Bank C Bank D O Start 0 0 0 O Start 0 0 0 116 0 Start 0 0 116 OStan 0 0 226 Stop 110 0 0 227 Stop III 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop III 0 226 226 116 0 Start 227 227 116 OStart 226 226 226 Stop 110 227 227 227 Stop Ill Fully Withdrawn at 228 Steps Fully Withdrawn at 229 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 O Start 0 0 0 OStan 0 0 0 116 OStan 0 0 116 OStart 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 0 Stan 0 228 228 Stop 112 0 229 229 Stop 113 0 228 228 116 0 Start 229 229 116 0 Start 228 228 --228 Stop 112 229 229 229 Stop 113 Fully Withdrawn at 230 Steps Fully Withdrawn at 231 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D OStan 0 0 0 OStart 0 0 0 116 0 Start 0 0 116 OStart 0 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Stan 0 231 116 0 Start 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Stan 231 231 116 0 Start 230 230 230 Stop 114 231 231 231 Stop 115

CNEI-0400-25 Page 16 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor - FQ(XY,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F QRT *K(Z)/P for P > 0.5 F RTP *K(Z)10.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO 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 T = 2.50 x K(BU)

F rP 2.6.3 K(Z) is the normalized FQ(XYZ) as a function of core height. K(Z) for MkBW fuel is provided in Figure 4, and the K(Z) for Westinghouse RFA 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 MkBW, Westinghouse RFA and NGF 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,Y,Z)

  • MQ(X,Y,Z) 2.6.5 [FQ(XYZ)]JP = UMT
  • TILT where:

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

CNEI-0400-25 Page 17 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report FQ (X,Y,Z) = Design power distribution for FQ. FD (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.

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 startup operation.

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

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

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

FQ(XYZ)

  • MC(XYZ) 2.6.6 [FQ(XYZ)] =

UMT

  • TILT where:

[FQ(X,Y,Z)]RP= 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.

F (X,Y,Z) = Design power distributions 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 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 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)

i CNEI-0400-25 Page 18 of 34 Revision 25 Catawba 2 Cvcle 13 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) 2.6.7 KSLOPE = 0.0725 where:

KSLOPE = the adjustment to the K1 value from OTAT trip setpoint required to LRPS compensate for each 1% that FQ" (X,Y,Z) exceeds [FQ (X,Y,Z)]

2.6.8 FQ(X,Y,Z) Penalty Factors for Technical Specification Sunreillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

CNEI-0400-25 Page 19 of 34 Revision 25 Catawvba 2 Cycle 13 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,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 0.800 N 0.600 0.400 Core Height (ft) K(Z) 0.200 0.0 1.000 6.0 1.000 12.0 1.000 0.000 . ~I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

CNEI-0400-25 Page 20 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Figure 5 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) 1.000 *3 I 0.800 -

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

CNEI-0400-25 Page 21 of 34 Revision 25 Cataiba 2 Cycle 13 Core Operating Limits Report Table 2 FQ(X,Y,Z) and Fi,&(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2,3.2.1.3 and 3.2.2.2 Burnup FQ(X,Y,Z) FaII(XY)

(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 FAII(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 22 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAII(X,Y) (TS 3.2.2)

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

2.7.1 [FL (XY)JLC0= MARP (X,Y) [1.0 + (1.0- P]

where:

[FA.l (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, FiAl1 (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.

2.7.2 [ FA (XY)]SURV - F;1(XY)*MS,, 1 (XY)

UMR

  • TILT where:

[FAll (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.

FL1, (XY)SURV includes allowances for calculational and measurement uncertainty.

FDll (X,Y) = Design power distribution for Fail FAIlI (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.

- , I CNEI-0400-25 Page 23 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report MAII(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 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 MAII(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, Fr1 (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, FAI1 (X,Y) exceeds its limit.

2.7.5 F,6I1(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 6.

CNEI-0400-25 Page 24 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

MkBW Fuel MARPs 1l00% Full Power Core lleight 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 1.40 1.369 1.307 1.086 1.043 12.00 1.636 1.608 1.553 1.505 1A56 1.446 1.408 1.403 1.370 1.340 1.286 1.072 1.027 RFA Fuel MARPs 100% Full Power Core height Axial Peak (i) 1.05 1.1 1.2 1.3 I. 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.847 1.882 1.947 1.992 1.974 2.068 2.090 2.049 1.972 1.900 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 2.40 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 1.920 1.964 1.974 2.068 2.005 1.968 1.892 1.820 1.716 1.471 1.431 4.80 1.838 1.868 1.906 1.945 1.974 2.006 1.945 1.925 1.862 1.802 1.725 1.326 1.285 6.00 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 8.40 1.823 1.829 1.847 1.857 1.816 1.795 1.739 1.722 1.675 1.630 1.551 1.247 1.211 9.60 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 1.430 1.149 1.097 11.40 1.789 1.765 1.725 1.684 1.632 1.614 1.569 1.557 1.510 1.466 1.392 1.113 1.060

CNEI-0400-25 Page 25 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Figure 6 Percent of Rated Thermal Power Versuis Percent Axial Flux Difference Limits

(-18, 100) 1 (+10, 100)

Unacceptable Operation Unacceptable Operation 90-80- -

0 70 Acceptable Operation 60 50

(-36, 50) 1 (+21,50) o 40 0~ 30

-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 26 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' < 590.8 °F Nominal RCS Operating Pressure P' = 2235 psig Overtemperature AT reactor trip setpoint KI = 1.1953 Overtemperature AT reactor trip heatup setpoint K2 = 0.03163/ 0 F penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.00 l4l4/psi setpoint penalty coefficient Time constants utilized in the Icad-lag compensator Tl = 8 sec.

for AT 2 = 3 sec.

Time constant utilized in the lag compensator for AT T3 = 0 sec.

Time constants utilized in the lead-lag compensator T4 = 22 sec.

for T.,vg

= 4 sec.

Time constant utilized in the measured Tavg lag T6 = 0 sec.

compensator fj(Al) "positive" breakpoint =3.0%Al fl(Al) "negative" breakpoint = -39.9%AI fl(Al) "positive" slope = 1.525 %AT 0 / %Al f1 (Al) "negative" slope = 3.91 0%ATo/%Al

CNEI-0400-25 Page 27 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T" < 590.8 OF Overpower AT reactor trip setpoint K4= 1.0819 Overpower AT reactor trip penalty K5 = 0.02/ 0F for increasing Tavg K5 = 0.00/ IF for decreasing Tavg Overpower AT reactor trip heatup setpoint K6 = 0.001291/OF for T > T" penalty coefficient K6 = 0.0 /0 F for T < T" Time constants utilized in the lead-lag =8sec.

8l compensator for AT 2 = 3 sec.

Time constant utilized in the lag T3 = 0 sec.

compensator for AT Time constant utilized in the measured Tayg = °06sec.

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

controller for Tavg f2 (Al) "positive" breakpoint = 35.0 %Al f2(Al) "negative" breakpoint = -35.0 %Al f2 (Al) "positive" slope = 7.0 %ATd %Al f2(Al) "negative" slope = 7.0 %AT 0/ %Al

CNEI-0400-25 Page 28 of 34 Revision 25 Catawba 2 Cycle 13 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 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 2.13 Refueling Water Storage Tank - RWIIST (TS 3.5.4) 2.13.1 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.

1 17 i CNEI-0400-25 Page 29 of 34 Revision 25 Catavba 2 Cycle 13 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters

-No. Operable PARAMETER INDICATION CHANNELS LIMITS

1. Indicated RCS Average Temperature meter 4 < 592.9 'F meter 3 < 592.6 OF computer 4 < 593.4 OF computer 3 < 593.2 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-0400-25 Page 30 of 34 Revision 25 Catawba 2 Cycle 13 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 2,700 ppm System, the refueling canal, and the refueling cavity.

2.16 Refueling Operations - Instrumentation (TS 3.9.2) 2.16.1 Reactor Makeup Water Pump Flow rate Limit:

- - Applicable Mode Limit Mode6 < 70 gpm

.X o CNEI-0400-25 Page 31 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.17 Standby Shutdown System - Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.17.1 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.

2.18 Bo'rated WaterSource-Shutdown (SLC16.9-11)

.2.18.1 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 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 2000 gallons to maintain SDM at 680 F Boric Acid Tank Minimum Shutdown Volume- 13,086 gallons

'(Includes the additional volumes listed in SLC (14.9%)

16.9-11)

NOTE: When cycle burnup is > 450 EFPD, Figure 7 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 'F Refueling Water Storage Tank Minimum 48,500 gallons Shutdown Volume (Includes the additional (8.7%)

volumes listed in SLC 16.9-11)

. . 1.

CNEI-0400-25 Page 32 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report 2.19 Borated Water Source - Operating (SLC 16.9-12) 2.19.1 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 7,000 ppm Volume of 7,000 ppm boric acid solution required 13,500 gallons to maintain SDM at 210TF Boric Acid Tank Minimum Shutdown Volume 25,200 gallons (Includes the additional volumes listed in SLC (45.8%)

16.9-12)

NOTE: When cycle burnup is > 450 EFPD, Figure 7 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 dto maintain SDM at 210 F Refueling Water Storage Tank Minimum 98,607 gallons Shutdown Volume (Includes the additional - (22.0%)

volumes listed in SLC 16.9-12)

i -

CNEI-0400-25 Page 33 of 34 Revision 25 Catawba 2 Cycle 13 Core Operating Limits Report Figure 7 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 45.0 RCS Boron Concentration BAT Level 40.0 (ppm) (°/devel) 0 < 300 43.0 300 < 500 40.0 35.0 500 < 700 37.0 I ,'. -',  ;-t. .;L 1, 700 < 1000 30.0 C) 30.0 1000 < 1300 14.9 1300 < 2700 9.8

-j C) 25.0 > 2700 9.8

, Oprainacceptableh ......,,,,,,

CM 20.0 eOperation

.*,. Operation r~ V.,....... .. Actbl 15.0

,~ ~ ~ ~ ~~( - *- '~-_ , ;

10.0 5.0 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 Primary Coolant Boron Concentration (ppmb)

CNEI-0400-25 Page 34 of 34 Revision 25 Catawba 2 Cyclc 13 Core Operating Limits Report Appendix A Powver 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.

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