ML081550653

Core Operating Limits Report (COLR) Catawba Unit 1 Cycle 18, Revision 1

ML081550653
Person / Time
Site:	Catawba
Issue date:	05/28/2008
From:	Morris J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNEI-0400-154, Rev 1
Download: ML081550653 (35)

Text

PDuke WEnergy.

Carolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station / CN01 VP 4800 Concord Road York, SC 29745 803-831-4251 803-831-3221 fax May 28, 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 1 Attached, pursuant to Catawba Technical Specification 526.5, is an information copy of revision 1 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 IQI~A~

www. duke-energy, com

U.

S.

Nuclear Regulatory Commission May 28, 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 May 28, 2008 Page 3 bxc:

(w/att)

RD Hart MJ Sawicki AR James BL Aldridge NCMPA-1 SREC PMPA NCEMC RGC Master File ELL CN01RC CN01RC EC08G CNS01SA Date File CN-801.01 EC050

CNEI-0400-154 Page I of 32 Revision I Catawba Unit 1 Cycle 18 Core Operating Limits Report Revision 1 May 2008 Duke Energy Company

<114a~

Prepared By:

Checked By:

Checked By:

Approved By:

A 2I4 Z;A Date eZOb3~s

-: 1 ::-3O/Sc?-2ý QA Condition 1 The information presented in this report has been prepared and issued in accordance with Catawba Technical Specification 5.6.5.

(

CNEI-0400-154 Page 2 of 32 Revision I INSPECTION OF ENGINEERING INSTRUCTIONS R

C Va4v,4, Date:

6-Inspection Waived 13y:

(Sponsor)

UI CATAWBA Inspection Waived MCE (Mechanical & Civil)

Insiected By/Date:

RES (Electical Only)

I nspected By/Date:

RES (Reactor)

Inspected By/Date:

MOD Inspected By/Date:

Other (

)___i._)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)

K Inspected By/Date:

RES (Reactor)

K Inspected By/Date:

MOD I. Inspected By/Date:

Other

)

I2 Inspected By/Date:

CNEI-0400-154 Page 3 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Implementation Instructions for Revision I Revision Description and PIP Tracking A re-design of the Catawba Unit I Cycle 18 core design was recluired to remove the Mixed Oxide (MOX) fuel assemnblies friom the core due to excessive assembly growth as docurmentcd in PIP #CO08-02980. Revision I of the Catawba Unit 1 Cycle 18 COLR contains limits specific to the re-design reload core. This revision of the Catawba Unit I Cycle 18 COLR is only valid for MODE 5 and MODE 6 in order to reload the core. A second revision will be issned that will address all MODES of operation.

Implementation Schedule Revision I may become effective any time during No MODE between Cycles 17 and 18 butt must become effective prior to entering MODE 6 which starts 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 1 Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Mode's 5 & 6 only)

REVISION LOG Revision Effective Date 0

1 April 2008 May 2008 Pages Affected 1-35, Appendix A*

1-32, Appendix A" COLR CIC18 COLR, Rev. 0 CIC18 COLR, Rev. I Appendix A will contain power distribution monitoring factors used in Technical Specification Surveillance.

Appendix A is included only in the electronic COLR copy sent to the NRC. Presently Appendix A is blank since this revision of the COLR is only valid for MODES 5 and 6. This Appendix will be updated in a future revision.

CNEI-0400-154 Page 5 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 Paralneter Section Page 2.1.1 311.1 3.1.3 3.1.4 3.1.5 Reactor Core Safety Limits Shutdown Margin Moderator Temperature Coefficient Rod Group Alignment Limits Shutdown Bank Insertion Limit 3.1.6 Control Bank Insertion Limit 3.1.8 3.2.1 3.2,2 3.2.3 3.3A1 3.3,9 3.4A1 3.5,1 3.5,4 3.7,15 3.9.1 5.6.5 Physics Tests Exceptions Heat Flux 1-lot Channel Factor Nuclear Enthalpy Rise 1-lot Channel Factor Axial Flux Difference Reactor Trip System Instrumcntat ion Boron Dilution Mitigation System RCS Pressure, Temperature and Flow limits for DNB Accumulators Refueling Water Storage Tank Spent Fuel Pool Boron Concentration Refueling Operations - Boron Concentration Core Operating Limits Report (COL.R)

RCS Temperature and Pressure Safety Limits Shutdown Margin MTC Shutdown Margin Shutdown Margin Rod Insertion Limits Shutdown Margin Rod Insertion Limits Shutdown Margin FQ AFD OTAT Penalty Factors FAH Penalty Factors AFD OTAT OPAT Reactor Makeup Water Flow Rate RCS Pressure, Temperature and Flow Max and Min Boron Cone.

Max and Min Boron Cone.

Min Boron Concentration Min Boron Concentration Analytical Methods.

2.1 9

2.2 2.3 2.2 2.2 2.4 2.2 2.5 2.2 2.6 2.8 2.9 2.6 2.7 2.7 2.8 2.9 2.9 2,10 2.11 2.12 2.13 2.14 2.15 9

11 9

9 11 9

is9 15 21 24 17 20 21 21 24 25 26 26 26 26 28 28 1.16 The Selected License Commitments that reference this report are listed below:

SLC Section Selected Licensine Commitment COLR COLR Section Page COLR Paramieter 16.7-9.3 Standby Shutdown System 16.9-1 1 Boration Systems - Borated Water Source - Shutdown 16.9-12 Boration Systems -- Borated Water Source - Operating Standby Makeup Pump Water Supply Borated Water Volume and Cone.

for BAT/RWST Borated Water Volume and Conc.

for BAT/RWST 2.16 2.17 29 29 2.18 30

CNEI-0400-154 Page 6 of 32 Revision I Catawba 1 Cycle 18,Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 METHOI)OLOGY," (W Proprietary).

Revision 0 Report Date: July 1985 Not Used for C1C18

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.

B AW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (13&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 CIC18

CNEI-0400-154 Page 7 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 1.1 Analytical Methods (continued)

6.

D1PC-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. 1991, 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. I)PC-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. I)1PC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."

Revision I SER Date: April 26, 1996 Not Used for C1C18

CNEI-0400-154 Page 8 of 32 Revision 1 Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 Coie 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 I SIMULATE-3 MOX", (DPC Proprietary).

Revision 0 SER Date: August 20, 2004

17. BAW-1023 IP-.A, "COPERNIC Fuel Rod Design Computer Code" (Framatome AN 1 Proprietary)

Revision I SER Date: January 14, 2004 Not Used for CIC18

CNEI-0400-154 Page 9 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 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 mode 5.

2.2.3 For TS 3.1.4, shutdown margin shall be greater than or equal mode I and mode 2.

2.2.4 For TS 3.1.5, shutdown margin shall be greater than or equal mode 1 and mode 2 with any control bank not fully in'serted.

2.2.5 For TS 3.1.6, shutdown margin shall be greater than or equal 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 mode 2 during Physics Testing.

to 1.3% AK/K in to 1.0% AK/K in to 1.3% AK/K in to 1.3% AKIK ini to 1.3% AK/K in to 1.3% AK/K in

CNEI-0400-154 Page 10 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 660 650 640 o

630 U

620 610 600 590 580 0.0 0.2 0.4 0.6 0.8 Fraction of Rated Thermal Power 1.0 1.2

CNEI-0400-154 Page 11 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 AKJK/KF 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/°F.

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 222 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-0400-154 Page 12 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0.

W C

I-0.9 0.8 Unacceptable Operation 0.7 04 0.6 0.5 0.4 0.3, Acceptable Operation 0.2 0.1 0.0

..... 1.........................

1.......

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 foi details.

(NEI-0400-1.54 Page 13 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawu (Maximum 231)

(29.6%, 23 1)

(80.0%. 231 )

2203 1......

Fully WVithdrawnu 200 f......

Mi 222)

Control Bank 1 S180-160 (0%,. 163) 1l40 410.............

a.~~ ~~~~~

• 4 4........

Conro Bankro Ban (C)cDbaluae y

Bank, CRI 2(P 7 OP 20.4 0

to 20o 30 40 50 60 70 so 90 100 Pei-cent of Rated Thermal Power The Rod Inser-tion Ilimits (RIL) for-Contr-ol Bank D (CD), Contr-ol Bank C (CC), and Contr-ol Bank B (CB) can be calculated by:

tBank CD RIL = 2.3(P) - 69 {30 _< P <_<

100}

Bank CC RIL = 2.3(P) + 47 {0 _<_

P _<80}

Bank CB RIL = 2.3(P) + 163 {0) < P 29.6}

wthere P = %Rated Thermal Pot.'er 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 14 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Table I Control Bank Withdrawal Steps and Sequence Fully Withdrawn' at 222 Steps Cool rot Control Control Control Bank A Bank B Book C Bank D) 0 Start 0

0 0

I6 0 Start 0

0 222 Stop 106 0

0 222 116 0 Start 0

222 222 Slop 106 0

222 222 116 0 Siart 222-------2 Stop 106 Fully Withrhtawn at 224 Steps Control Control Control Cont rol Bank A Bank B Bank C Bank t) 0 Starl 0

0 116 0 Starl 0

0 224 Stop 108 0

0 224 116 0 Start 0

22-4 224 Stop 108 0

224 224 116 0 Stal 224 224 224 Stop 108 Ftully \\Vithdchr'aiw at 223 Steps Control Control Control Control Bank A Bllank B Blank C Bank D)

OStart 0

0 0

116 0 Start 0

0 223 Stop 107 0

0 223 116 0 Start 0

223 223 Stop 107 0

223 223 116 0 Starl 223 223 223 Stop 107 Fully \\Vithdrrain at 225 Steps Corntrot Control Control Control Baik A IBank B Balnk C Bank I) 0 Start 0

0 0

116 0 Start 0

0 225 Stop 109 0

0 225 116 0 Start 0

225 225 Stop 109 0

225 225 116 0 Starr 225 225 225 Stop 109 Fully Withdr aw at 226 Steps Control Con0trol Control Con1trol Bank A Bank B Bank C BMnk 1) 0 Start 0

0 0

116 0 Start 0

0 226 Stop It0 0

0 226 116 0 Start (I

226 226 Stop 110 0

226 226 116 0 Slarr 226 226 226 Stop 110 Fill,V WithdItrawn at 227 Steps Control Control Control Control BIank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start

(

0 227 Stop 111 0

0 227 116 0 Stur 0

227 227 Stop 11I 0

227 227 116

4) Stall 227 227 227 Stop III Fully Withdrawn at 229 Steps Conrtrol Corn oto Control Control Bank A Bank B Bank C Bank 1)

Fully Withdrawn at 228 Steps Control Control Control Control Bank A Bank It Bank C Bank 1) 0 Starr 0

0 0

116 0 Start 0

0 228 Stop 112 0

0 228 116 0 Slar 1 0

228 228Stop 1 12

()

22M 228 116 0 Starr 228 228 228 Stop 112 0 Start 0

0 0

116 0 Starr 0

0 229 Stop 113 0

0 229 116 0 Start I) 229 229 Stop 113 0

229 229 116 0 Start 229 229 229 Stop 113 Fultly Willthdrawin at 231 Steps Control Control ControlContirot Bank A BanlIk B 1

Bank (C

]ank I)

Fully Witlhdrawn at 230 Steps Controt Cortrol Ctonl rot Control Bankl A Bank B Ba1,ik C BaIltt I) 0 Strtl 0

0 0

116 0 Stil 0

230 Stop 114 0

0 230 H16 0 Start 0

230 230 Stop 114 0

230 230 116

( Start 230 230 230 Stop 114 0 Stmar 0

0 0

116 0 Start 0

)

231 Stop 1H5

)

0 231 116 0 Stiru 0

231 231 Stop 115 0

231 231 1It 1

Slarr 231 231 231 Stop 115

CNEI-0400-154 Page 15 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 arc defined by the following relalionships:

F '?'P %:K(Z)/P for P > 0.5 Q

F RrTP *K(Z)/0 5 for P < 0.5

where, P

(Thermal Power)/(Rated Power)

Note: The measuured 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.

2.6.2

= 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 pei the Surveillance Requirements of Technical Specification 3.2.1:

L..

FFQ(X,Y,Z)]

F(XYZ MQ(X,Y,Z) 2..5 IQ(XYZ)

=

UMT MT TILT where:

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

CNEI-0400-154 Page 16 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

/F1 (X,Y,Z)01 includes allowances for calculational and measurement uncertainties.

z(X,Y,Z)=

MQ(XYZ) =

Design power distribtition for FQ. F': (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 operatilon.

Margin remaining in core location X,Y,Z t0 the LOCA limit in the transient power distribution. MQ(XY,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) 2.6.6

[FQ(X,Y,Z)] RPS F.(X,Y,Z)

• MQ(X,Y,Z)

UMT

• MT

• TILT where:

[F6(X,Y,Z)11Rl's-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. [FQ(X,Y,Z)m1'Rs includes allowances for c alc u l at ional and measurement uncertainties.

Desian 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.

FQ(X,Y,Z)

CNEI-0400-154 Page 17 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Mc(X,Y,Z)

Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. MC(X,Y,Z) is provided in Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operations.

MT Engineering Hot Channiel 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 RPS compensate for each 1% that F/S (XY,Z) exceeds F." (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 I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for RFA and NGF Fuel 11 1.200 (0.0, 1.00)

(4.0, 1.00) 1.000 0-I (12.0, 0.9615)

(4.0, 0.9615) 0.800 0.600 0.400 0.200 0.000 Core Height (nt)

K(Z) 0.0 1.000

<4 1.000

>4 0.9615 12.0 0.9615

....0.

I..

8.0 0.0 4.0 6.0 Core Height (Jt) t0.0 12.0

CNEI-0400-154 Page 19 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

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 BurnUJ)

(EFPD))

4 12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400

.425 450 465 481 506 521 FQ(X,Y,Z)

Penalty Factor(%)

2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 FAI1 (X,Y)

Penalty Factor (%)

2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 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-0400-154 Page 20 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAHI(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

([FY,](X, ("'

MARP (XY) 1.0 + RRH (1.0 - P)]

wherc:

[FAH (X, y)]L(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.

P Thermal Power Rated Theimal Power RRH =Thermal Power reduction requnirecd to compensate for each I% that the measured radial peak, Fý,, (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.

SIJRV Fl 1 (X, I Y) 1 (X, Y) 2.7.2

[FA(ik(X,Y)]

=

UMR *TILT where:

S11 RV F*]* (X,Y)] s Cycle dependent maximum allowable design peaking factor that ensures that the Flll 1(X,Y) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

Bk., (X,Y) includes allowances for calculational and measurement uncertainty.

-H (X,Y) = Design power distribution for F A FAI. (Xy) is provided in Appendix Table A-3 for normal operation and in Appendix

CNEI-0400-154 Page 21 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Table A-6 for power escalation testing during initial startup operation.

M\\J$(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 foor normal opleration and in Appendix Table A-6 for power escalation testing during initial startup operation.

UMR Uncertainty Value for measured radial peaks. UJMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable MAli(XY).

TILT =Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02. (TILT = t.035) 2.7.3 RRH 3.34 wheire:

RRH = Theirmal Power redIuction required to compensate for each I t% 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 setpoini required to compensate for each 1% that the measured radial peak, FAj.(X,Y) exceeds its limit.

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

2.8 Axial Flux l)ifference - AFD (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.

CNEI-0400-154 Page 22 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Table 3 Maximum Allowable Radial Peaks (MARPS)

RFA Fuel MARPs 100% Full Power SAxia Pea k Core lleight

('ft I 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

%lbl 0.12 1.20 2.40 3.60 4.80 6.00 7.20 8.40 9.60 10.80 S1.40 I.8092 1.8553 1.9489 1.9953 1.9741 1.8102 1.854 1.9401 1.9953 1.9741 1.8093 1.8525 1.9312 1.9779 1.9741 1.8098 1.8514 1.9204 1.9641 1.9741 1.8097 I.8514 1.9058 1.9449 1.9741 1.8097

(.8514 1.8921 1.9212 1.9455 1.807 1.8438 1,8716 1.893 1.8872 1.8073 1.8319 1.8452 1.8571 1.8156 1.8072 1.8102 1.8093 1.7913 1.7375 1.798 1.7868 1.7611 1.7)63 1.6538 1.7892 1.7652 1.725 1.6645

,(6057 2.1073 2.1073 2.01735 2.0495 2.0(159 1.9336 1.8723 1.795 1.7182 1.6315 1.5826 2.0498 2.009 1.9333 1.8625 1.778 1.3151 2.11(91 1.9775

(.9009

.1S306 1.7852 1.3007 1.9953 1.9519 1.876 1,8054 1.732 1.4633 1.9656 1.9258 1.524 1.7185 1.6996 1.4(675 1.9441 1.9233 1.8538 1.7836 1.6714 1.2987 1.8798 1.8625 1.9024 1.7,472 1.6705 1.3293 1.80194 1.7866 1,7332 1.6812 1.5982 1.2871 1.7359 1.7089 1,6544 1.601 1.5127 1.2182 1.6572 1,6347 1.5808 1.5301 1.4444 1.1431 1.5743

(.5573 1.5088 1.4624 1.3832

.1009 1.5289 1.5098 1.4637 1.421(

1.3458 1.067 1(2461 1,2235 1.;1(,]6 1.3874 1.2579 1.2602 1.2(95 1.1578 1,0914

(,647 1,0142 NGF Fuel MARPs 100% Full Power Core Ileight (fl)

Axial Iea'c;lk 1.05 1.2 1.4 1.6 1.8 2.1 3.25 0.12 2.40 4.80 7.20 9.60 11.40 1.7339 1.8713 1.1045 2.0493 1.9307 1.7855 1.2661 1.7237 1.8528 1.8045 1.9933 1 8696 1.7244 1.4424 1.728 1.8237 1.8045 1(8844 18013 1.647 1.2322 1.7247 1.7842 1.8045 1.7354 1.6517 1.5342 1.1715 1.724 1.7232 1.6517 1.566

(.4887 1,3575 1.0167 1,7066 1.6415 1.5241 1.4382 1.3737 1.2608 0.96

CNE1-0400-154 Page 23 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux D)ifference Limits H

-ci 4) 4-U Unacceptable Operation Accer 90-Uinacceptable Oj:

70 (table Operation 60 50

(-36, 50) 40 30 20

(+21,50) 20 30 Jeration 40 50 10

-50

-40

-30

-20

-10 0

10 Axial Fllux Difference (% Delta I)

NOTE: Compliance with Technical Specification 3.2.1 may require more restrictive AFD limits. Refer to the Unit I ROD manual for operational AFD limits.

CNEl-0400- t 54 Page 24 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 Tavg at RTPI Nominal RCS Opera ting Pressure Overtemperature -AT reactor trip setpoint Overtemperature AT reactor trip heatup setpoint penalty coefficient Overtemperatu re AT reamlor trip depressurization setpoint penalty coefficient Time constants utilized in the lea.d-lag compensator for AT Time constant utilized in the lag compensator for AT Time constants Utilized in the lead-lag comPensator for Tavg Time constant utilized in the measured T,,,.g lag compellsator fl(AI) "positive" breakpoint Nominal Value T'<585.1 'F P'= 2235 psig K1I = 1.1978 K2 = 0.03340/OF K3 = 0.001601 /psi 1= 8 sec.

T2 = 3 sec.

U3 = 0 sec.

"r4 = 22 sec.

T5 = 4 sec.

"16 = 0 sec.

= 19.0 %AI fl(AI) "negative" breakpoint

= N/A*

fl (AI) "positive" slope

= 1.769 %AT0 %AI fl(A1) "negative" slope

= N/A*

The f1 (AI) negative breakpoints and slopes for OTAT are less restrictive than the OPAT f2(Al) negative breakpoint and slope. Thectfore, during a transient which challenges the negative imbalance limits the OP.AT f2(AI) limits will result in a reactor trip before the OTA'I' f (Al) limits arc reached. This makes implementation of an OT AT fI (AI) negative breakpoint and slope unnecessary.

CNEI-0400-154 Page 25 of 32 Revision 1 Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 2.9.2 Overpower AT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower AT reactor trip setpoint Overpower AT reactor tiip penalty Overpower AT reactor trip heatup setpoint penalty coefficient (for T>T")

Time constants utilized in the lead-lag compensatlor for AT Time constant utilized in the lag compensator for AT Time constant utilized in the measured T,,,..

lag compensator Time constant utilized in the rate-lag controller for.Tg f2(AI) "positive" breakpoint f2(AJ) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Nominal Value T"< 585.1 OF K4 = 1.0864 K 5 = 0.02 / OF for increasing Tavg K5 = 0.00 / °F for decreasing Tavg K 6 = 0.001 179/°F for T > T" K6 = 0.0 /F for T < T" 1= 8 sec.

-C2 3 sec.

'C3 = 0 sec.

"6 = 0 sec.

C7 10 sec.

= 35.0 %AI

= -35.0 %AI

= 7.0 %ATo/%AI

= 7.0 %ATo/ %Al

CNEI-0400-154 Page 26 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 1 and 2, and mode 3 with RCS pressure

>1000 psi:

Parameter Limit Cold Leg Accumulator minimum boron concentration.

2,500 ppm Cold Leg Accuirnulator maximum boron concentration.

3,075 ppm 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 Boron concentration limits during modes 1, 2, 3, and 4:

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

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

CNEI-0400-154 Page 27 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Table 4 Reactor Coolant System DNB Parameters No. Operable PARAMETER INI)ICATION CHANNELS LIMITS

1. Indicated RCS Average Temperature meter 4

< 587.,2 'F 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 I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 1)rocedures 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 System, the refueling canal, and the refueling cavity.

2,700 ppm

CNEI-0400-154 Page 29 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 2.16 Standby Shutdown System-Standby Makeup Pump Water Supply - (SLC-16.7-9.3) 2.16.1 Minimum boron concentration limit foi-the spent fuel pool. Applicable for modes 1, 2, and 3.

Parameter Spent fuel po061 minimumn boron concentration for surveillance SLC-16.7-9.3.

Limit 2,700 ppmn 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 < 210°F, and Modes 5 and 6.

Parameter Limit Boric Acid Tank mninimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 68°F Boric Acid Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-11) 7,000 ppmn 2000 gallons 13,086 gallons (14.9%)

NOTE: When cycle burnup is > 480 EFPI), Figure 6 may be used to determine the required Boric Acid Tank Minimum Level.

Refueling Water Storage Tank minimum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 68 'F Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volurnes listed in SLC 16.9-11) 2,700 ppm 7,000 gallons 48,500 gallons (8.7%)

CNEI-0400-154 Page 30 of 32 Revision I Catawba I Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only) 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 > 2 10°F.

Parameter Li n it Boric Acid Tank minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 210°F Boric Acid Tank Minimum Shutdown Volulme (Includes the additional volumes listed in SLC 16.9-12) 7,000 ppmn 13,500 gallons 25,200 gallons (45.8%)

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 mini mum boron concentration Volume of 2,700 ppm boric acid solution required to maintain SDM at 210OF Refueling Water Storage Tank Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9-12) 2,700 ppfln 57,107 gallons 98,607 gallons (22.0%)

CNEI-0400-154 Page 31 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

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 5 0.0 504 0

45,0

> 30.0 25.0 Unacceptable S20.0 Oprto 15.0 10.0 50.

0.0 10 2200 RCS Bo Concentr*

(ppm 300 <5 500 <7 700 < I1 1000 <1 1300 <

• > 270

)ron ation BAT Level (p

(%level) 0 0 43.0 3 00 40.0 5 00 37.0 000 30.0 1 300 14.9 2700 9.8 0

9.8 2000 2200 2400 2600 Acceptable Operation 1200 1400 t600 1800 Primary Coolant Boron Concentration (ppmb)

CNEI-0400-154 Page 32 of 32 Revision I Catawba 1 Cycle 18 Core Operating Limits Report (Applicable to Modes 5 & 6 only)

Appendix A Power Distribution Monitoring Factors Appendix A will contain power dlistributi on monitoring factors used in Technical Specification Surveillance. In this revision Appendix A is intentionally blank sinice it is only valid for MODES 5 and 6. This Appendix will be updated in a future revision.