ML081650181

Core Operating Limits Report, Cycle 18, Revision 2

ML081650181
Person / Time
Site:	Catawba
Issue date:	06/10/2008
From:	Morris J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNEI-0400-154, Rev 2
Download: ML081650181 (35)

Text

JAMES R. MORRIS, VICE PRESIDENT PDuke aEnergy Duke Energy Carolinas,LLC Catawba Nuclear Station Carolinas 4800 Concord Road / CNO1 VP York, SC 29745 803-701-4251 803-701-3221 fax June 10, 2008 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555-0001

Subject:

Duke Energy Carolinas, LLC.

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

Catawba Unit 1 Cycle 18, Revision 2 Attached, pursuant to Catawba Technical Specification 5.6.5, is an information copy of revision 2 of the Core Operating Limits Report for Catawba Unit 1 Cycle 18.

This letter and attached COLR do not contain any new commitments.

Please direct any questions or concerns to Marc Sawicki at (803) 701-5191.

Sincerely, James R. Morris Attachments A4ooI www. duke-energy.com

U. S. Nuclear Regulatory Commission June 10, 2008 Page 2 Xc: (w/att)

Luis A. Reyes, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 J. F. Stang, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8 G9A Rockville, MD 20852-2738 A. T. Sabisch Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station

U. S. Nuclear Regulatory Commission June 10, 2008 Page 3 bxc: (w/att)

RD Hart CN01RC MJ Sawicki CN01RC AR James EC08G BL Aldridge CNS01SA NCMPA-1 SREC PMPA NCEMC RGC Date File Master File CN-801.01 ELL ECO5O

CNEI-0400-154 Page 1"of32 Revision 2 Catawba Unit 1 Cycle 18 Core Operating. Limits Report Revision 2 June 2008 Duke Energy Company Date Prepared By: a Checked By:

Checked By:

Approved By: ew QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Techntical Specification 5.6.5.

N

CNEI-0400-154 Page 2 of 32 Revision 2 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: D ate:

(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) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor)  :: Inspected By/Date:

MOD Inspected By/Date:

Other ( -_Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other( Inspected By/Date:

CNEI-0400-154 Page 3 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Implementation Instructions for Revision 2 Revision Description and PIP Tracking A re-design of the Catawba Unit 1 Cycle 18 core design was required to remove the Mixed Oxide (MOX) fuel assemblies from the core due to excessive assembly growth as documented in PIP #C-08-02980. Revision 2 of the Catawba Unit I Cycle 18 COLR contains limits specific to the re-design reload core for all MODES of operation.

Implementation Schedule Revision 2 may become effective any time during No MODE between Cycles 17 and 18 but must become effective prior to entering MODE 4 of Cycle 18. The Catawba Unit I Cycle 18 COLR will cease to be effective during No MODE between Cycle 18 and 19.

Data files to be Implemented No data files are transmitted as part of this document.

CNEI-0400-154 Page 4 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR 0 April 2008 1-35, Appendix A* CIC18 COLR, Rev. 0 1 May 2008 1-32, Appendix A* CIC8 COLR, Rev. I 2 June 2008 1-32, Appendix A* C IC 18 COLR, Rev. 2 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is included only in the electronic COLR copy sent to the NRC.

CNEI-0400- 154 Page 5 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5:6.5. The Technical Specifications that reference this report are listed below:

TS COLR COLR Section Technical Specifications COLR Parameter - Section Page 2.1.1 Reactor Core Safety Limits RCS Temperature and Pressure -2.1 9 Safety Limits 3.1.1 Shutdown Margin Shutdown Margin 2.2 9 3.1.3 Moderator Temperature Coefficient MTC 2.3 11 3.1.4 Rod Group Alignment Limits Shutdown Margin 2.2 . 9 3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2,2 9 Rod Insertion Limits 2.4 11 3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 9 Rod Insertion Limits 2.5 11 3.1.8 Physics Tests Exceptions Shutdown Margin 2.2

• 9 3.2.1 Heat Flux Hot Channel Factor FQ 2.6 15 AFD 2.8 21 OTAT .2.9- 24 Penalty Factors 2.6 17 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH 2.7 20 Factor Penalty Factors 2.7 21 3.2.3 Axial Flux Difference AFD 2.8 21 3.3.1 Reactor Trip System Instrumentation OTAT " 2.9 '24 OPAT 2.9 25 3.3.9 Boron Dilution Mitigation System Reactor Makeup Water Flov) Rate 2.10 26 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, Temperature mnd 2.11 26 limits for DNB Flow 3.5.1 Accumulators Max and Min Boron Conc. 2.12 26 3.5.4 . Refueling Water Storage Tank Max and Min Boron Conc. ' 2-13 26 3.7.15 'Spent Fuel Pool Boron Concentration *Mm Boron Concentration 2.14 28 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 28 Concentration 5.6.5 Core Operating Limits Report (COLR) Analytical Methods " 1.1 6 The Selected License Commitments that reference this report are listed below:

SLC *"COLR COLR Section Selected Licensing Commitment COLR Parameter Section Page 16.7-9.3 Standby Shutdown System Standby Makeup Pump Water 2.16 29 Supply

.16.9-11 Boration Systems - Borated Water Borated Water Volume and Conc. 2.1P7 29 Source - Shutdown for BAT/RWST 16.9,12 Boration Systems-- Borated Water Borated Water Volume and Conc.* 2.18 30 Source - Operating for BAT/RWST

CNEI-0400-154.

Page 6 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC are as follows.

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

Revision 0 Report Date: July 1985 Not Used for CIC18

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

Revision 0 Report Date: August 1985

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

Revision 2 Report Date: March 1987 Not Used for C1C18

4. WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (W 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 I)ates: August 22, 1996 and November 26, 1996.

Revision 3 SER Date: June 15, 1994.

Not Used for CIC18

CNEI-0400-154 Page 7 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 3 SER Date: September 24, 2003

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

Revision 0 Report Date: November 15, 199 1, republished December 2000

8. DPC-NE-3002-A, "UFSAR Chapter 15 System Transient Analysis Methodology".

Revision 4 SER Date: April 6, 2001

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

Revision 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 Not Used for CiC18

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 26t 1996 Not Used for C1C18

CNEI-0400-154 Page 8 of 32 Re\ýision 2 Catawba 1 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 2 SER Date: June 24, 2003

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

Revision I SER Date: October 1, 2002

16. DPC-NE-1005-P-A, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX",

(DPC Proprietary).

Revision 0 SER Date: August 20, 2004

17. BAW-1023 IP-A, "COPERNIC Fuel Rod Design Computer Code" (Fralm-atorne ANP Proprietary)

Revision I SER Date: January 14, 2004 Not Used for C1C18

CNEI -0400-154 Page 9 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified in Section 1.1.

2.1 Reactor Core Safety Limits (TS 2.1.1)

The Reactor Core Safety Limits are shown in Figure 1.

2.2 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6, TS 3.1.8) 2.2.1 For TS 3.1.1, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 2 with Keff < 1.0 and in modes 3 and 4.

2.2.2 For TS 3.1. 1, shutdown margin shall be greater than or equal to 1,0% AK/K in mode 5.

2.2.3 For TS 3.1.4, shutdown margin shall be greater than or equal to 1.3% AK/K in mode 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-0400-154 Page 10 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 . .i.....

65 0 .. ... .... ......

2I 640 0 630 .. . .. . . ... ............. .

O 6 206 O*L

)*b 4 ....... '.... ....... .......... ...

610 -

610 600 590 .. ...

ACCEPTABLE 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power

CNEI-0400-154 Page 11 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:

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

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

2.3.2 The 300 ppm MTC Surveillance Limit is:

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

2.3.3 The60 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/ 0 F.

Where: BOC = Beginning of Cycle (burnup corresponding to most positive MTC)

EOC = End of Cycle ARO = All Rods Out HZP Hot Zero Thermal Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps. Shutdown banks are withdrawn in sequence and with no overlap.

2.5 Control Bank Insertion Limits (TS3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3. Specific control bank withdrawal and overlap limits as a function Of the fully withdrawn position are shown in Table 1.

CNEI-0400-154 Page 12 of 32 Revision 2 Catawba I Cycle 18 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation 0.8 Z

"L 0.7 0.6 0x 0 0.5 0.4 Acc.eptable Operation 0.3 0.2 0.1 '-

0.0 ---

I............... i.................... i ....

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 I ROD manual for details.

CNEI-0400-154 Page 13 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Wi lbdiawn (Maximum = 23 1) 231 220 200 I18 f 160

• . 140

= 120 1100 80 60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power The Rod Insertion Limits (RIL) for Control Bank D (CD), Control Bank C (CC), and Control Bank B (CB) can be calculated by:

Bank CD RIL = 2.3(P) - 69 {30 _<P <_1001 Bank CC RIL = 2.3(P) + 47 {0 _< P

• 80}

Bank CB RiL = 2.3(P) + 163 {0 < P _ 29.61 where P = %Rated Theermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to the Unit I ROD manual for details.

CNEI-0400-1 54 Page 14 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Fully Withdrawn at 223 Steps Control Conh'ol Control Control Control Control Control Control Bank A Bank B Bank C Bank I) Baitk A Bank It Bank C Baink 1) 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Start 0 223 116 0Start 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 Withdrawn at 224 Steps Fully Withdrawia at 225 Steps Control Control Conltrol Control Control Control Control Control Bank A Bank B Bank C Bank D Batnk A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 O Star 0 0 224 Stop 108 0 0 223 Slop 109 0 0 224 116 0 Start 0 225 116 0 Start 0 224 224 Stop 108 0 225 225 Stop 109 0 224 22 4 116 0 Start '25 2 25 116 0 Start 224 224 224 Stop 108 225 225 225 Stop 109 Fully Withdrawn at 226 Steps Full) Withdranwit at 227 Steps Control Control Control Control Control Control Control Control Bank A. Batik B Bank C Bank 1) Bank A Bank B Bank C Biaink 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 0Slarl 0 226 226 Stop 110 0 227 227 Stop III 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 Stop IIl Fully Withdrawn at 228 Steps FullyaWthlitawn at 229 Steps Control Control Control Control Control Control Control Control Bank A Bank B Batnk C Bank 1) Bank A Bank B Banik C Batik D 0 Start 0 0 0 0 Stalt 0 0 0 116 0 Start 0 0 116 0 Start 0 0 228Stop 112 0 0 229 Slot) 113 0 0 22M 116 0 Start 0 229 116 0 Start 0 2

228 28 Stop 112 . 0 229 229 Stop 113 0 229 228 116 0 Start 229 229 116 0 Start 228 228 228 Stop 112 229 229 229 Stop 113 Fullsy Withdrtawn at 230 Steps Fatly WVithdrawn at 231 Steps Cott trol Control Control Control Coil rol Conttrol Control Control Bank A Baank B Bank C Bank 1) Bank A Bank B Batnk C Batik 1) 0 Start 0 0 0 0 Star 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 t Start 0 23 2311 0 Stop . 114 0 231 231 Stop 115 0 "

230 230 116 0 Start 231 231. 116 0 Start 23(1 230 230 Stop 114 231 231 231 Stop 115

CNEI-0400-154 Page 15 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F R77T*K(Z)/P for P > 0.5 F TTP:*'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 3.0% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined below for COLR Sections 2.6.5 and 2.6.6.

2.. RTP 2..2 IFQ = 2.60 x K(BU) for RFA and NGF fuel 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height. K(Z) for Westinghouse RFA and NGF fuel is provided in Figure 4.

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

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

2.6.5 LY,Z)]o*' FQ(X,Y,Z) MQ(X,Y,Z) 6 -(X, UMT MT* TILT where:

[i- (X,Y,Z)]O '= 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. PQ (XY,Z) includes allowances for calculational and measurement uncertainties.

CNEI-0400-154 Page 16 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report D

vQ(,YZ Design power distribution for FQ. FIo(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial IQ (X,Y,Z) =

startup operation.

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

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

MT - Engineering Hot Channel Factor. (MT = 1.03). The manufacturing tolerances for RFA/NGF fuel is implicitly included in the FQ LOCA surveillance limits (Mq).

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 1)

FQ(X,Y,Z)

• Mc,(X,Y,Z)

L 2.6.6 IFQ(XIYIZ)l UMT

• MT *TILT where:

IF 1(X,Y,Z)J]Z)'s- Cycle dependent maximum allowable design peaking factor that Q) ensures that the FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR limits. [F L(X,Y,Z)]RPS includes allowances for calculational and measurement uncertainties.

FQ(X,Y,Z) = Design power distributions for FQ. FQ(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operations.

M(,(X,Y.,Z) = Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. M(.(X,Y,Z) is provided in Appendix Table A-2 for normal operating conditions and in

CNEI-0400-154 Page 17 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Appendix Table A-5 for power escalation testing during initial startup operations.

MT Engineering Hot Channel Factor. (MT = 1.03). The manufacturing tolerances for RFA/NGF fuel is implicitly included in the FQ RPS surveillance limits (Mc).

TILT Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.6.7 KSLOPE =0.0725 where:

KSLOPE the adjustment to the K1 value from OTAT trip setpoint required to compensate for each 1% that Fc7 (X,Y,Z) exceeds [L (X,Y,Z) 2.6.8 FQ(X,Y,Z) Penalty'Factors for Technical Specification Surveillances 3.2.1.2 and 3:2.1.3 are provided in Table 2.

CNEI-0400-154 Page 18 of 32 Revision 2 Catawba I Cycle 18 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA and NGF Fuel 1.200 (0.0, 1.00) (4.0, 1.00) 1.000 I.

T (12.0, 0.9615)

(4.0, 0.9615) 0.800 0.600 0.400 Core Height (ft) K(Z) 0.0 1.000 0.200 + <4 1.000

>4 0.9615 12.0 0.9615 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Heighl (ft)

CNEI-0400-154 Page 19 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAII(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(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.o0 375 2.00 2.00 400 2.00 2.00 425 2.00 2.00 450 2.00 2.00 465 2.00 2.00 481 2.00 2.00 506 2.00 2.00 521 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 F,1\ 1(X,Y) for compliance with the Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

CNEI-0400-154 Page 20 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)

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

2.7.1 [Flj (X,Y)]Lco= MARP (X,Y) [1.0 + RRH (1.0- P)]

where:

IJII (X, Y)]LL'o 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.

Thermal Power Rated Thermal Power RRI- =Thermal Power reduction required to compensate for each 1% that the.

measured radial peak, F£"i (X,Y), exceeds the limit.

(RRHl = 3.34, 0.0 < P < 1.0)

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

sui, v = Fa. 1 (X,Y)

• MA*l (X, Y) 2.7.2 [F,2,- (XY)]

UMR.* TILT where:

SI.RV

[FL-I (X,Y)] = Cycle dependent maximum allowable'design peaking factor that ensures that the Fa (X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

F,',(X,Y)suRv includes allowances for calculational and measurement uncertainty.

F) D FAl (X,Y) = Design power distribution for FAHFAH (X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix TFable A-6 for power escalation testing during initial startup operation.

CNEI-0400-154 Page 21 of 32 Revision 2 Catawba 1 Cycle18 Core Operating Limits Report 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 Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.

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

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratioof 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, F,"' (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 thermeasured radial peak, FH(X,Y) exceeds its limit.

.2.7.5 FAII(X,Y) Penalty Factors for Technical Spiecification 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 5.

CNEI-0400-154 Pge 22 of 32 Revision 2 Catawba I Cycle 18 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

RFA Fuel MARPs 100% Full Power Cori Hleighl Axial Peak (Al' 1.05 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.8092 1.8553 1.9489 1.9953 1.9741 2.1073 2.0498 2.009 1.9333 1.8625 1.778 1.3151 1.2461 1.2( 1.8102 1.854 1,9401 1,9953 1.9741 2,1073 2.0191 1.9775 1.9009 1.8306 1.7852 1.3007 1.2235 2.4( 1.8093 1.8525 1.9312 1.9779 1.9741 2.0735 1.9953 1.9519 1.876 1.8054 1,732 1.4633 1.4616 3.6C 1.8098 1.8514 1.9204 1.9641 1.9741 2.0495 1.9656 1.9258 1.8524 1.7855 1.6996 1.4675 1,3874 4.8C 1.8097 1.8514 1.9058 1,9449 1.9741 2.0059 1.9441 1.9233 1.8538 1.7836 1,6714 1.2987 1.2579 6.0( 1.8097 1.8514 1.8921 1.9212 1.9455 1.9336 1.8798 1.8625 1.8024 1.7472 1.6705 1.3293 1.2602 7T2C 1.807 1.8438 1.8716 1,893 1.8872 1.8723 1.8094 1.7866 1.7332 1.6812 - 1.5982 1.2871 1,2195 SAC 1.8073 1.8319 1.8452 1.8571 1 156 1.795 1.7359 1.7089 16544

• 1.601 1.5127 1.2182 1.1578 9.6c 1.8072 1.8102 1.8093 1.7913 1.7375 1.7182 1.6572 1.6347 1.5808 1.5301 1.4444 1.1431 1.0914 10.8C 1.798 1.7868 1.7611 1.7163 1.6538 1.6315 1,5743 1.5573 . 1.5081 1.4624 1,3832 1.1009 1.047 1 1.A 1.7892 1,7652 1.725 1.6645 1.6057 1.5826 1.5289 1.5098 1.4637 1.4218 1.3458 1.067 10142 NGF Fuel MARPs 100% Full Power Core Hleight Axial Peak (fit) 1.05 1.2 1.4 1.6 1.8 2.1 3.25 0.12 1,7339 1.8713 1.89045 2.0493 1.9307 1.7855 1.2661 2.40 1.7233 1.8528 1.8045 1.9933 1.8696 1.7244 1.4424 4.80 1.728 1.8237 1.8045 1.8844 1.8013 1.6471 I.2322 7.20 1.7247 1.7842 1.8045 1.7354 1.6587 1.5342 1,1715 9.60 1.724 1.7232 1.6517 1.566 1.4887 1.3575 1.0167 11.40 1.7066 1.6415 1.5241 1.4382 1.3737 1.2608 0,96

CNEI-0400-154 Page 23 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-20, 100) (+10,100)

Unacceptable Operation / Unacceptable Operation 90 80 70 E

Acceptable Operation 60 H

50

(-36, 50) (+21, 50) 0 40 I) 0-~ 30 .

20 +-

10

.........- 0

-50 -40 -30 -0 -10 0 to 20 30 40 50 Axial Flux Difference (% Delta I)

NOTE: Compliance with Technical Specification 3.2.1 may require mote restrictive AFD limits.

Refer to the Unit I ROD manual for operational AFD limits.

CNEI-0400-154 Page 24 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' < 585.1.'F Nominal RCS Operating Pressure F= 2235 psig Overtemperature AT reactor trip setpoint KI = 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.03340/°F penalty,,coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator TI = 8 sec.

for AT T) = 3 sec.

Time constant utilized in the lag compensator for AT 'E3 = 0 sec, Time constants utilized in the lead-lag compensator = 22 sec.

for T,,,, = 4 sec.

Time constant utilized in the measured T,,,, lag . 6 = 0 sec.

compensator fI (AI) "positive" breakpoint = 19.0 %AI f l (AI) "negative" breakpoint = N/A*

fl(A1) "positive" slope = 1.769 %AT 0 / %Al fl(AI) "negative" slope N/A*

The f1 (Al) negative breakpoints and slopes for OTAT are less restrictive than the OPAT f_(A1) negalive breakpoint and slope. Therefore, during a trahsient which challenges the negative imbalance limits the OPAT f2(AI) limits will result in a reactor trip before the OTAT f1 (AI) limits are reached. This makes implementation of an OTAT. f, (AI) negative breakpoint and slope unnecessary.

CNEI-0400-154 Page 25 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T"< 585.1 OF Overpower AT reactor trip setpoint K4= 1.0864 Overpower AT reactor trip penalty K5 = 0.02 / 'F for increasing Tavg K 5 = 0.00 / 'F for decreasing Tavg Overpower AT reactor trip heatup setpoint K6 = 0.001179/°F for T > T" penalty coefficient (for T>T'") K 6 = 0.0 /F for T < T" Time constants utilized in the lead-lag 'r, = 8 sec.

compensator for AT -c? = 3 sec.

Time constant utilized in the lag compensator u3 = 0 sec.

for AT Time constant utilized in the measured Tavg "6 = 0 sec.

lag compensator Time constant utilized in the rate-lag -17 = 10 sec.

controller for T,,,,g f 2(A1) "positive" breakpoint = 35.0 %AI f 2(AI) "negative" breakpoint = -35.0 %AI f 2 (AI) "positive" slope = 7.0 %AT/ %AI f 2(AI) "negative" slope = 7.0 %AT/ %AI

CN EI-0400-154 Page 26 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.10 Boron Dilution Mitigation System (TS 3.3.9) 2.10.1 Reactor Makeup Water Pump flow rate limits:

Applicable Mode Limit Mode 3 < 150 gpm Mode 4 or 5 < 70 gpm 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1)

The RCS pressure, temperature and flow limits for DNB are shown in Table 4.

2.12 .Accumulators (TS.3.5.1) 2.12.1 Boron concentratiori 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 - RWST (TS 315.4) 2.13.1 Boron concentration limits during modes 1, 2, 3, and 4:

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

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

CNEI-0400-154 Page 27 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable PARAMETER INDICATION CHANNELS LIMITS

1. Indicated RCS Average Temperature meter 4 < 587.2 TF meter 3 < 586.9 'F computer 4 < 587.7 'F computer 3 < 587.5 'F

2. Indicated Pressurizer Pressure meter 4 > 2219.8 psig meter 3 > 2222.1 psig computer 4 > 2215.8 psig computer 3 > 2217.5 psig

3. RCS Total Flow Rate > 388,000 gpm

CNEI-0400-154 Page 28 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.15) 2.14.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.

Parameter Limit Spent fuel pool minimum boron concentration. 2,700 ppm 2.15 Refueling Operations - Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keff < 0.95.

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

CNEI-0400-154 Page 29 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.16 Standby Shutdown System - Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.16.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes 1,2, and 3.

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

2.17 Borated Water Source - Shutdown (SLC 16.9-11) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Mode 4 with any RCS cold leg temperature < 2100F, 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 68°F Boric Acid Tank Mini mum Shutdown Volume 13,086 gallons (Includes the additional volumes listed in SLC 16.9- (14.9%)

11)

NOTE: When cycle burnup is > 480 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 "F Refueling Water Storage Tank Mini mum Shutdown 48,500 gallons Volume (Includes the additional volumes listed in (8.7%)

SLC 16.9-11)

CNEI-0400-154 Page 30 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report 2.18 Borated Water Source - Operating (SLC 16.9-12) 2.18.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during Modes 1, 2, and 3 and Mode 4 with all RCS cold leg temperatures > 210°F.

Parameter I Limit Boric Acid Tank mininunm boron concentration 7,000 ppm Volume of 7,000 ppm boric acid solution required 13,500 gallons to maintain SDM at 210'F 25,200 gallons Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC (45.8%)

16.9-12)

NOTE: When cycle burnup is > 480 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 210°"F Refueling Water Storage Tank Minimum 98,607 gallons Shutdown Volume (Includes the additional (22.0%)

volumes listed in.SLC 16.9-12)

CNEI-0400-154 Page 31 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is > 480 EFPD)

This figure includes additional volumes listed in SLC 16.9-11 and 16.9-12 50.0 ......

RCS Boron 45.0 Concentration BAT Level (ppm) (%level) 0 < 300 43.0 300<500 40.0 35.0 500 < 700 37.0 30.0 i 700<1000 30.0 1000<1300 14.9

-I 1300<2700 9.8

> 2700 9.8 w 25.0 Unacceptable

-J I.-

200 . Operation Acceptable Operation 15.0 10.0 0.0 t------- ".. .

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

CNEI-0400-154 Page 32 of 32 Revision 2 Catawba 1 Cycle 18 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke and is not included in the Duke internal copies of the COLR. The Catawba Reactor and Electrical Systems Engineering Section controls this information via computer files and should be contacted if there is a need to access this information.

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