ML101100461

Cycle 21, Revision 0, Core Operating Limits Report

ML101100461
Person / Time
Site:	McGuire
Issue date:	04/14/2010
From:	Repko R Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-232, Rev 0
Download: ML101100461 (34)

Text

Duke Energy.Vice REGISPresident T.REPKO Energy. McGuire Nuclear Station Duke Energy MG01 VP /12700 Hagers Ferry Rd.

Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko@duke-energy.corn April 14, 2010 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station Docket Nos. 50-369 Unit 1, Cycle 21, Revision 0 Core Operating Limits Report Pursuant to McGuire Technical Specification (TS) 5.6.5.d, please find enclosed Revision 0 of the McGuire Unit 1 Cycle 21 Core Operating Limits Report (COLR).

Revision 0 of the McGuire Unit 1 Cycle 21 COLR contains limits specific to the reload core.

Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Compliance at (980) 875-4306.

Regis T. Repko Attachment RcýD www. duke-energy. corn

U. S. Nuclear Regulatory Commission April 14, 2010 Page 2 cc: Mr. Jon H. Thompson, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Luis A. Reyes Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station

MCEI-0400-232

.Page 1 of 32 Revision 0 McGuire Unit 1 Cycle 21 Core Operating Limits Report Revision 0 March 2010 Calculation Number: MCC-1553.05-00-0519, Rev. 0 Duke Energy Date Pr red By:

Checked By:

Checked By: 3i/,o (Sections 2.2 and -18)

Approved By: 3 AI/

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

MCEI-0400-232 Page 2 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:

(Sponsor)

(cS pso) Date: 3 h/

/o t)

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

RES (Electrical Only) El Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD El Inspected By/Date:

Other( ) E] Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) El Inspected By/Date:

MOD El Inspected By/Date:

Other( ) Inspected By/Date:

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

RES (Electrical Only) El Inspected By/Date:

RES (Reactor) E] Inspected By/Date:

MOD Inspected By/Date:

Other ( ) Inspected By/Date:

MCEI-0400-232 Page 3 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and PIP Tracking Revision 0 of the McGuire Unit I Cycle 21 COLR contains limits specific to the reload core. There is no PIP associated with this revision.

Implementation Schedule Revision 0 may become effective any time during No MODE between cycles 20 and 21 but must become effective prior to entering MODE 6 which starts cycle 21. The McGuire Unit I Cycle 21 COLR will cease to be effective during No MODE between cycle 21 and 22.

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

MCEI-0400-232 Page 4 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR 0 March 2010 1-32, Appendix A* M1 C21 COLR, Rev. 0 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.

MCEI-0400-232 Page 5 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of the Technical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below.

TS COLR El Number Technical Specifications COLR Parameter Section Pag~e 1.1 Requirements for Operational Mode 6 Mode 6 Definition 2.1 9 2.1.1 Reactor Core Safety Limits RCS Temperature and 2.2 9 Pressure Safety Limits 3.1.1 Shutdown Margin Shutdown Margin 2.3 9 3.1.3 Moderator Temperature Coefficient MTC 2.4 11 3.1.4 Rod Group Alignment Limits Shutdown Margin 2.3 9 3.1.5. Shutdown Bank Insertion Limits Shutdown Margin 2.3 9 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion 2.5 11 Limit.

3.1.6 Control Bank Insertion Limits Shutdown.Margin 2.3 9 3.1.6 Control Bank Insertion Limits Control Bank Insertion 2.6 15 Limit 3.1.8 Physics Test Exceptions Shutdown Margin 2.3 9 3.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.7 15 Penalty Factors 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.8 20 Factor Penalty Factors 3.2.3 Axial Flux Difference AFD 2.9 21 3.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.10 24 Setpoint Constants 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, 2.11 26 limits for DNB Temperature and 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 3.7.14 Spent Fuel Pool Boron Concentration Min 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 Licensee Commitments that reference this report are listed below:

COLR El SLC Number Selected Licensing Commitment COLR Parameter Section 16.9.14 Borated Water Source - Shutdown Borated Water Volume and 2.16 29 Conc. for BAT/RWST 16.9.11 Borated Water Source - Operating Borated Water Volume and 2.17 30 Conc. for BAT/RWST 16.9.7 Standby Shutdown System Standby Makeup Pump 2.18 30 Water Supply

MCEI-0400-232 Page 6 of 32 Revision 0 McGuire I Cycle 21 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 as specified in Technical Specification 5.6.5 are as follows.

1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," (W Proprietary).

Revision 0 Report Date: July 1985 Not Used for M1C21

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 MlC21

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

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

Report Date: March 1998

5. BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for 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 M1C21

MCEI-0400-232 Page 7 of 32 Revision 0 McGuire 1 Cycle 21 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-300 1-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, "FSAR Chapter 15 System Transient Analysis Methodology".

Revision 4 SER Date: April 6, 2001

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

Revision 2a SER Date: December 2008

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

Revision 4a SER Date: December 2008

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

Revision 0 SER Date: April 3; 1995 Not Used for M1C21

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

Revision 2a SER Date: July 2009

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

Revision 1 SER Date: April 26, 1996 Not Used for M1C21

MCEI-0400-232 Page 8 of 32 Revision 0 McGuire 1 Cycle 21 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-2011 PA, "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 1 SER Date: November 12, 2008

MCEI-0400-232 Page 9 of 32 Revision 0 McGuire I Cycle 21 Core Operating Limits Report 2.0 Operating Limits The cycle-specific parameter limits for the specificitions 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 Requirements for Operational Mode 6 1

The following condition is required for operational mode 6.

2.1.1 The reactivity condition requirement for operational mode 6 is that klff must be less than, or equal to 0.95.

2.2 Reactor Core Safety Limits (TS.2.1.1) 2.2.1 The Reactor Core Safety Limits are shown in Figure 1.

2.3 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6 and TS 3.1.8) 2.3.1 ForTS 3.1.1, SDM shall be> 1.3% AK/K in MODE 2 with k-eff < 1.0 and in MODES 3 and4.

2.3.2 For TS 3.1.1, SDM shall be > 1.0% AK/K in MODE 5.

2.3.3 For TS 3.1.4, SDM shall be > 1.3% AK/K in MODES 1 and 2.

2.3.4 For TS 3.1.5, SDM shall be > 1.3% AK/K in MODE 1 and MODE 2 with any control bank not fully inserted.

2.3.5 ForTS 3.1.6, SDM shall be> 1.3% AK/K in MODE I and MODE 2 with K-eff> 1.0.

2.3.6 For TS 3.1.8, SDM shall be > 1.3% AK/K in MODE 2 during PHYSICS TESTS.

MCEI-0400-232 Page 10 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Figure 1 Reactor'Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 640 t4*oo sia: -. '

630 U 620 610 2100 psia" 6101%,.

S1945 psiia '

600 590 ACCEPTABLE 580 0.0 0.2 0.4 0.6 0.8 1.0 12 Fraction of Rated Thermal Power

MCEI-0400-232 Page 11 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.4 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.4.1 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/KI°F.

The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AKIK/ 0 F lower MTC limit.

2.4.2 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/ 0 F.

2.4.3 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/ 0 F.

Where, BOC = Beginning of Cycle (Bumup corresponding to the most positive MTC.)

EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.5 Shutdown Bank Insertion Limit (TS 3.1.5) 2.5.1 Each shutdown bank shall be withdrawn to at least 222 steps except under the conditions listed in Section 2.5.2. Shutdown banks are withdrawn in sequence and with no overlap.

2.5.2 Shutdown banks may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.

MCEI-0400-232 Page 12 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation S 0.8 S 0.7 U 0.6

• 0.5 OA Acceptable Operation F-o 0,4 0 0.3

. 0.2 0.1 0 10 20 30 40 50 60 70 80 90 10()

Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to OP/l/A/6100/22 Unit I Data Book for details.

MCEI-0400-232 Page 13 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 180 P0

. 160

., 140 120 0

"100 60 800 0

o*40 0

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 < 100)

Bank CCRIL = 2.3(P) +47 (0<P<76.1) for CCRIL = 222 (76.1 <P<100}

Bank CB RIL = 2.3(P) +163 (0 < P < 25.7} for CB RIL = 222 (25.7 < P < 100}

where P = %Rated Thermal Power NOTES; (1) Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to OP/l/A/6100/22 Unit 1 Data Book for details.

(2) Anytime any shutdown bank or control banks A, B, or C are inserted below 222 steps withdrawn, control bank D insertion is limited to > 200 steps withdrawn (see Sections 2.5.2 and 2.6.2)

MCEI-0400-232 Page 14 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Table 1 RCCA Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Fully Withdrawn at 223 Steps Control Control Control Control Control Control Control Control BankA Bank B Bank C BankD Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Start 0 223 116 0 Stat 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 Withdrawn at 225 Steps

.Control Control Control Control Control Control Control Control BankA BankB BankC BankD Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start . 0 0 0 116 0 Start 0 .0 116 0 Start 0. 0 224 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 BankB BankC BankD Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 226 Stop 110 0 0 227 Stop 111 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop III 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 Stop 111 Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps Control Control Control Control Control Control Control Control BankA BankB BankC BankD BankA Bank B Bank C BankD 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 0 Start 0 228 228 Stop 112 0 229 229 Stop 113 0 228 228 116 0 Start 229 229 116 0 Start 228 228 228 Stop 112 229 229 229 Stop 113 Fully Withdrawn at 230 Steps Fully Withdrawn at 231 Steps Control Control Control Control Control Control Control Control BankA BankB BankC Bank D BankA Bank B Bank C BankD 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 0 Start 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Start 230 230 230 Stop 114 231 231 23.1 Stop 115

MCEI-0400-232 Page 15 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.6 Control Bank Insertion Limits (TS 3.1.6) 2.6.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3 except under the conditions listed in Section 2.6.2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.

2.6.2 Control banks A, B, or C may be inserted to 219 steps withdrawn individually for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the plant was operated in steady state conditions near 100% FP prior to and during this exception.

2.7 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.7.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F:R *K(Z)/P for P > 0.5 F QRTP *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.7.5 and 2.7.6.

2.7.2 F-QITP = 2.60 x K(BU) 2.7.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height. The K(Z) function for Westinghouse RFA fuel is provided in Figure 4.

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

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

2.7.5 F z = FQ(X,Y,Z)

• MQ(X,Y,Z)

FQ(XYZ)

• UMT

• MT

• TILT

MCEI-0400-232 Page 16 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report where:

FoL (X,Y,Z)OP Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits. FL (X,Y,Z)°P includes allowances for calculational and measurement uncertainties.

EQ9 (X,Y,Z) Design power distribution for FQ. FQ9 (X,Y,Z) is provided in Appendix A-1 for normal operating conditions and in Appendix Table A-4 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 Appendix Table A-1 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)

TILT = Peaking penalty that accounts for the peaking increase from an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

FQ(X,Y,Z)

• Mc(X,Y,Z) 2.7.6 FQ(X,Y,Z)RPs-UMT

• MT

• TILT where:

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

D FQ(XYZ)- Design power distributions for FQ. FQ(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.

MCEI-0400-232 Page 17 of 32 Revision 0 MeGuire I Cycle 21 Core Operating Limits Report 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 operation.

UMT = Total Peak Measurement Uncertainty (UMT = 1.05)

MT = Engineering Hot Channel Factor (MT = 1.03)

TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.7.7 KSLOPE - 0.0725 where:

KSLOPE is the adjustment to the K1 value from OTAT trip setpoint required to L RPS compensate for each 1% that FQ" (X,Y,Z) exceeds Fd (X,Y,Z) .

2.7.8 FQ(X,Y,Z) penalty factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.

MCEI-0400-232 Page 18 of 32 Revision 0 McGuire I Cycle 21 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel 1.200 (0.0, 1.00) (4.0, 1.00) 1.000 (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 0.000 i i I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

MCEI-0400-232 Page 19 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAH(X,Y) Penalty Factors For Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup FQ(X,Y,Z) FAH(X,Y,Z)

(EFPD) Penalty Factor (%) Penalty Factor (%)

0 2.00 2.00 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 2.00 484 2.00 2.00 494 2.00 2.00 509 2.00 2.00 524 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle burnups. All cycle burnups outside of the range of the table shall use a 2% penalty factor for both FQ(X,Y,Z) and FAH(X,Y) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

MCEI-0400-232 Page 20 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.8 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 is defined by the following relationship.

2.8.(X, Y) = MARP (XY)

• 1.0 (10 P)]

where:

FkH (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.

. .Thermal Power Rated Thermal Power.

RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, FH (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.

2.8.2 FL(X,Y)SUgV F- (X,Y)xMm(X,Y)

UMR x TILT where:

L SUJRV FP (X,Y) = Cycle dependent maximum allowable design peaking factor that ensures that the FAH(XY) limit is not exceeded for operation within the AFD, RIL, and QPTR limits. FL (X,Y)SRV includes allowances for calculational and measurement uncertainty.

MCEI-0400-232 Page 21 of 32 Revision 0 McGuire I Cycle 21 Core Operating Limits Report D D FA (X,Y) = Design radial power distribution for F . FA (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.

MA(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 the peaking increase for an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035).

2.8.3 RRH 3.34 where:

RRH = Thermal power reduction required to compensate for each 1% that the measured radial peak, F1 (X,Y) exceeds its limit. (0 < P < 1.0) 2.8.4 TRH = 0.04 where:

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

2.8.5 FAH(XY) penalty factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.

2.9 Axial Flux Difference - AFD (TS 3.2.3) 2.9.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.

MCEI-0400-232 Page 22 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPs)

(Applicable for RFA Fuel)

Core Axial Peak Ht (ft.) LO0 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 1.809 1.855 1.949 1.995 1.974 2.107 2.050 2.009 1.933 1.863 1.778 1.315 1.246 1.2 1.810 1.854 1.940 1.995 1.974 2.107 2.019 1.978 1.901 1.831 1.785 1.301 1.224 2.4 1.809 1.853 1.931 1.978 1.974 2.074 1.995 1.952 1.876 1.805 1.732 1.463 1.462 3.6 1.810 1.851 1.920 1.964 1.974 2.050 1.966 1.926 1.852 1.786 1.700 1.468 1.387 4.8 1.810 1.851 1.906 1.945 1.974 2.006 1.944 1.923 1.854 1.784 1.671 1.299 1.258 6.0 1.810 1.851 1.892 1.921 1.946 1.934 1.880 1.863 1.802 1.747 1.671 1.329 1.260 7.2 1.807 1.844 1.872 1.893 1.887 1.872 1.809 1.787 1.733 1.681 L'598 1.287 1.220 8.4 1.807 1.832 1.845 1.857 1.816 1.795 1.736. 1.709 1.654 1.601 1.513 :1.218 1.158 9.6 1.807 1.810 1.809 1.791 1.738 1.718 1.657 1.635 1.581 1.530 1.444 1.143 1.091 10.8 1.798 1.787 1.761 1.716 1.654 1.632 1.574 1.557 1L509 1.462 1.383 1.101 1.047 11.4 1.789 1.765 1.725 1.665 1.606 1.583 1.529 1.510 1.464 1.422 1.346 1.067 1.014

MCEI-0400-232 Page 23 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits L.

4, 0

2 L.

4, 4,

4, 4,

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta 1)

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

Refer to OP/1/A/6100/22 Unit 1 Data Book for more details.

MCEI-0400-232 Page 24 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.10 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.10.1 Overtemperature AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T' < 585.1 0 F Nominal RCS Operating Pressure P' = 2235 psig Overtemperature AT reactor trip setpoint KI <1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.0334/°F penalty coefficient OvertemperatureAT reactor trip depressurization K3 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator c > 8 sec.

for AT T2 < 3 sec.

Time constant utilized in the lag compensator for AT r3 < 2 sec.

Time constants utilized in the lead-lag compensator T4 > 28 sec.

for Tayg r5 < 4 see.

Time constant utilized in the measured Tayg lag T6 < 2 sec.

compensator fl(Al) "positive" breakpoint = 19.0 %AI fl (AD "negative" breakpoint = N/A*

fl(AD) "positive" slope = 1.769 %AT0/ %Al

= N/A*

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

MCEI-0400-232 Page 25 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T" < 585.1 0 F Overpower AT reactor trip setpoint K4 < 1.0864 Overpower AT reactor trip Penalty K5 = 0.02/'F for increasing Tavg K5 = 0.0 for decreasing Tavg Overpower AT reactor trip heatup K6 = 0.001179/'F for T > T" setpoint penalty coefficient K6 = 0.0 for T<T" Time constants utilized in the lead- 1> 8 sec.

lag compensator for AT T2 < 3 sec.

Time constant utilized in the lag ¶3 <2 sec.

compensator for AT Time constant utilized in the r6 < 2 sec.

measured Tavg lag compensator Time constant utilized in the rate-lag t7 > 5 sec.

controller for Tayg f2(AI) "positive" breakpoint = 35.0%AI f2(AI) "negative" breakpoint = -35.0 %AI f2(AI) "positive" slope = 7.0 %ATo %/,1 f2(AI) "negative" slope = 7.0 %AT0/%AI

MCEI-0400-232 Page 26 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1) 2.11.1 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 Accumulator minimum boron concentration. 2,475 ppm Accumulator maximum boron concentration. 2,875 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 Limit RWST minimum boron concentration. 2,675 ppm RWST maximum boron concentration. 2,875 ppm

MCEI-0400-232 Page 27 of 32 Revision 0 McGuire 1 Cycle 21 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 OF meter 3 < 586.9 OF computer 4 < 587.7 OF computer 3 < 587.5 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*

• Note: The RCS minimum coolant flow rate assumed in the licensing analyses for the MIC21 core is 388,000 gpm. However, the flow is set at 390,000 gpm, which is conservative

MCEI-0400-232 Page 28 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.14) 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. 2,675 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 2,675 ppm System, the refueling canal, and the refueling cavity.

MCEI-0400-232 Page 29 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report 2.16 Borated Water Sources - Shutdown (SLC 16.9.14) 2.16.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during MODE 4 with any RCS cold leg temperature

< 300 'F and MODES 5 and 6.

Parameter Limit BAT minimum contained borated water volume 10,599 gallons 13.6% Level Note: When cycle burnup is > 455 EFPD, Figure 6 may be used to determine the required BAT minimum level.

BAT minimum boron concentration 7,000 ppm BAT minimum water volume required to 2,300 gallons maintain SDM at 7,000 ppm RWST minimum contained borated water 47,700 gallons volume 41 inches RWST minimum boron concentration 2,675 ppm RWST minimum water volume required to 8,200 gallons maintain SDM at 2,675 ppm

MCEI-0400-232 Page 30 of 32 Revision 0 McGuire I Cycle 21 Core Operating Limits Report 2.17 Borated Water Sources - Operating (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 MODES 1, 2, 3, and MODE 4 with all RCS cold leg temperatures > 300'F.

Parameter Limit BAT minimum contained borated water volume 22,049 gallons 38.0% Level Note: When cycle burnup is > 455 EFPD, Figure 6 may be used to determine the required BAT minimum level.

BAT minimum boron concentration 7,000 ppm BAT minimum water volume required to 13,750 gallons maintain SDM at 7,000 ppm RWST minimum contained borated water volume 96,607 gallons 103.6 inches RWST minimum boron concentration 2,675 ppm RWST maximum boron concentration (TS 3.5.4) 2875 ppm RWST minimum water volume required to 57,107 gallons maintain SDM at 2,675 ppm 2.18 Standby Shutdown System - (SLC-16.9.7) 2.18.1 Minimum boron concentration limit for the spent fuel pool required for Standby Makeup Pump Water Supply. Applicable for MODES 1, 2, and 3.

Parameter Limit Spent fuel pool minimum boron concentration for TR 2,675 ppm 16.9.7.2.

MCEI-0400-232 Page 31 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus RCS Boron Concentration (Valid When Cycle Burnup is > 455 EFPD)

This figure includes additional volumes listed in SLC 16.9.14 and 16.9.11 40.0 RCS Boron 35.0 -- Concentraton BAT Level (ppm) (%level) 0 < 300 , 37.0 300 <500 i 33.0

-0.0. 500 <700- 28.0 700<1000 23.0

.1000 <'1300 13.6

_ 25.0 1300 8.7 20.0

-- I Acceptable m 15.0 10.0 Unacceptable Operation ]

5.0 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 RCS Boron Concentration (ppmb)

MCEI-0400-232 Page 32 of 32 Revision 0 McGuire 1 Cycle 21 Core Operating Limits Report NOTE: Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire I Cycle 21 Maneuvering Analysis calculation file, MCC-1553.05-00-0512. 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 Plant Nuclear Engineering Section will control this information via computer file(s) 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.