ML11286A252

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Calculation MCC-1553.05-00-0549, Revision 1, Cycle 22 Core Operating Limits Report
ML11286A252
Person / Time
Site: Mcguire
Issue date: 09/29/2011
From: Repko R
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-261, Rev 1 MCC-1553.05-00-0549, Rev 1
Download: ML11286A252 (34)
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REGIS T. REPKO Duke Vice President 2Energye 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 September 29, 2011 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station Docket Nos. 50-370 Unit 1, Cycle 22, Revision 1 Core Operating Limits Report Pursuant to McGuire Technical Specification (TS) 5.6.5.d, please find enclosed Revision 1 of the McGuire Unit 1 Cycle 22 Core Operating Limits Report (COLR).

Revision 0 was not required to be submitted in accordance with TS 5.6.5.d because it was superseded prior to its effective date (No Mode).

Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Compliance at (704) 875-4306.

Regis T. Repko Attachment Ao0/

www. duke-energy.com

i U. S. Nuclear Regulatory Commission September 29, 2011 Page 2 cc: Mr. J.H. Thompson (addressee only)

NRC Senior Project Manager (McGuire)

U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, D.C. 20555-0001 Mr. V.M McCree, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. John Zeiler Senior Resident Inspector McGuire Nuclear Station

SA MCEI-0400-261 Page 1 of 32 Revision 1 McGuire Unit 1 Cycle 22 Core Operating Limits Report Revision 1 September 2011 Calculation Number: MCC-1553.05-00-0549, Rev. I Duke Energy Date Prepared By:

Checked By:

9Lý A0 Checked By:

(Sections 2.2 and 2.10 -1.18)

Approved By:

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

MCEI-0400-261 Page 2 of 32 Revision 1 McGuire 1 Cycle 22 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:.

(Sponsor) kC71Vi,LI Date: 2 CATAWBA Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:

RES (Electrical Only) El Inspected By/Date:

RES (Reactor) El Inspected By/Date:

MOD El Inspected By/Date:

Other( ) El Inspected By/Date:

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

RES (Electrical Only) El Inspected By/Date:

RES (Reactor) El Inspected By/Date:

MOD 11 Inspected By/Date:

Other( ) El 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( _ _ El Inspected By/Date:

MCEI-0400-261 Page 3 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report Implementation Instructions for Revision I Revision Description and PIP Tracking Revision I of the McGuire Unit I Cycle 22 COLR contains limits specific to the reload core and was revised to update an Analytical Method reference in Section 1.1. The PIP associated with this revision is: M-1 1-03805.

Implementation Schedule Revision I may become effective any time during No MODE between cycles 21 and 22 but must become effective prior to entering MODE 6 which starts cycle 22. The McGuire Unit 1 Cycle 22 COLR will cease to be effective during No MODE between cycle 22 and 23.

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

MCEI-0400-261 Page 4 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR 0 August 2011 1-32, Appendix A* M1C22 COLR, Rev. 0 I September 2011 1-32 M 1C22 COLR, Rev. I

  • 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 upon request.

MCEI-0400-261 Page 5 of 32 Revision I McGuire I Cycle 22 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 Pa ~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 Insertiorf 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, OTXT 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 1.16 The Selected Licensee Commitments that reference this report are listed below:

COLR El SLC Number Selected Licensing Commitment COLR Parameter Section Page 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-0400-261 Page 6 of 32 Revision 1 McGuire 1 Cycle 22 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.

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

Revision 0 Report Date: July 1985 Not Used for M1C22

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 M1C22

4. WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Quahfication 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 M1C22

MCEI-0400-261 Page 7 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 4a Report Date: July 2009

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

Revision Oa Report Date: May 2009

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

Revision 4b Report Date: September 2010

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

Revision 2a Report Date: December 2008

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

Revision 4a Report Date: December 2008

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

Revision la Report Date: December 2008 Not Used for M1C22

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

Revision 3a Report Date: September 2011

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

Revision la Report Date: January 2009 Not Used for M1C22

MCEI-0400-26 1 Page 8 of 32 Revision I McGuire 1 Cycle 22 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 2a Report Date: December 2009

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

Revision la Report Date: June 2009

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

Revision I Report Date: November 2008

MCEI-0400-261 Page 9 of 32 Revision I McGuire 1 Cycle 22 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 Requirements for Operational Mode 6 The following condition is required for operational mode 6.

2.1.1 The reactivity condition requirement for operational mode 6 is that kff 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 and 4.

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 I and 2.

2.3.4 For TS 3.1.5, SDM shall be > 1.3% AKJK in MODE I and MODE 2 with any control bank not fully inserted.

2.3.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in MODE 1 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-0400-261 Page 10 of 32 Revision I McGuire I Cycle 22 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 640 240pia 0 630

> 2280 psia C/1 (U 620 610 1 1945 psia* *.

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

MCEI-0400-261 Page 11 of 32 Revision I McGuire 1 Cycle 22 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 AKJK/°F.

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

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 (Burnup 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-0400-261 Page 12 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 0.8 Q

0.7 Q

0.6 S0.5 0

  • 0.4

- 0.3 0.2 0.1 0.0 0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

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

MCEI-0400-261 Page 13 of 32 Revision 1 McGuire 1 Cycle 22 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 180 160

, 140 S120 S100 80 0 60 S60

'N 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]

BankCCRIL =2.3(P) +47 (0<P<76.1) for CCRIL =222 (76.1 <P<1001 Bank CBRIL = 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/1/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)

MCE[-0400-261 Page 14 of 32 Revision I McGuire I Cycle 22 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 Bank A Bank B Bank C Bank D 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 Start 0 222 222 Stop l06 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 Bank A Bank B Bank C Bank D BankA 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 Wlthdraswn at 227 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 2 27 226 Stop 110 0 0 Stop 111 0 0 226 116 0 Start 0 227 116 0 Start 0 2 7 226 26 Stop 110 0 227 22 Stop 11I 0 226 226 116 0 Start 227 227 116 o Start 2 27 226 226 226 Slop 110 227 227 Stop IIl 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 Bank D 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 22 228 228 Stop 112 0 229 9 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 BanklB 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 0 230 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 114 231 231 231 Stop 115

MCEI-0400-261 Page 15 of 32 Revision I McGuire 1 Cycle 22 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 RTP *K(Z)/P for P > 0.5 F RTP *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured FQ(X,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'R = 2.70 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 bumups.

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

D 2.7.5 FQ(X,Y,Z)

  • MQ(XYZ) 25FQ(XYZ)o UMT
  • TILT

MCEI-0400-261 Page 16 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report where:

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

F D(X,Y,Z) = Design power distribution for FQ. F,D (X,Y,Z) is provided in Appendix A-I 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-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)

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

D L RPS FQ(X,Y,Z)

  • Mc(X,Y,Z) 2.7.6 FQ(X,Y,Z) =

UMT

  • TILT where:

L(X,Y,Z)RPS Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.

[F (X,Y,Z)]"S 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-I for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.

MCEI-0400-261 Page 17 of 32 Revision I McGuire 1 Cycle 22 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 to account for 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 fiom OTAT trip setpoint required to (X,Y,Z)RPS compensate for each 1% that F" (X,Y,Z) exceeds F, 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-0400-261 Page 18 of 32 Revision I McGuire I Cycle 22 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 1 (0.0, 1.00) (4.0, 1.00) 1.000 S(12.0, 0.9259)

(4.0, 0.9259) 0.800 +

0~..600-0.400-Core Height (fi) l Z) 0_0 1.000 0.200 + <4 1.000

>4 0-9259 12.0 0.9259 0.000 I I I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

MCEI-0400-261 Page 19 of 32 Revision 1 McGuire I Cycle 22 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FHM(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 3.30 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 2.00 465 2.00 2.00 489 2.00 2.00 499 2.00 2.00 514 2.00 2.00 524 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle bumups. 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-0400-26 I Page 20 of 32 Revision I McGuire 1 Cycle 22 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.

2.8.1 F6(X,Y)'-c 0 = MARP (X,Y)

  • where:

Fsi (X, Y) " is 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, Fm, (X,Y), exceeds its 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.

FL (X,Y)SURv FD,(X,Y)xM.(X,Y) 2.8.2 UMR x TILT where:

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

MCEI-0400-261 Page 21 of 32 Revision 1 McGuire 1 Cycle 22 Core Operating Limits Report D D F*H (X,Y) = Design radial power distribution for FlAH" FAH (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.

MAH(XY) = The margin remaining in core location X,Y relative to the Operational DNB limits in the transient power distribution.

MAH(X,Y) is provided in 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 = 1.0).

UMR is 1.0 since a factor of 1.04 is implicitly included in the variable MAH(XY).

TILT = Peaking penalty to account for 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, FaH (X,Y), exceeds its limit. (0 < P < 1.0) 2.8.4 TRH = 0.04 where:

TRI-1 = Reduction in OTAT K1 setpoint required to compensate for each 1% that the measured radial peak, F1, (X,Y), exceeds its limit.

2.8.5 F H(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-0400-261 Page 22 of 32 Revision I MeGuire I Cycle 22 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPs)

RFA Fuel Core Axial Peak Ht (ft.) 1.05 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.809 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 1.598 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 1.509 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-0400-261 Page 23 of 32 Revision 1 McGuire 1 Cycle 22 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 0

I-0 U

I-.

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

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

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

MCEI-0400-261 Page 24 of 32 Revision I McGuire 1 Cycle 22 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°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 Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator 1 > 8 sec.

for AT T2 < 3 sec.

Time constant utilized in the lag compensator for AT t3 < 2 sec.

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

for Tavg 15 < 4 sec.

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

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

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

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

MCEI-0400-261 Page 25 of 32 Revision I McGuire 1 Cycle 22 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter 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 = 0.0 for decreasing Tavg Overpower AT reactor trip heatup K 6 = 0.001179/°F forT > T-setpoint penalty coefficient K 6 = 0.0 for T<T" Time constants utilized in the lead- "*1 > 8 sec.

lag compensator for AT _C2 <3 sec.

Time constant utilized in the lag t3 < 2 sec.

compensator for AT Time constant utilized in the _r6 < 2 sec.

measured Tavg lag compensator Time constant utilized in the rate-lag _7 > 5 sec.

controller for Tavg f2(AI) "positive" breakpoint = 35.0 %AI f2(AI) "negative" breakpoint = -35.0 %A[

f2(AI) "positive" slope = 7.0 %ATo/%AI f2(AI) "negative" slope = 7.0 %ATo/ %AI

MCEI-0400-26 1 Page 26 of 32 Revision I McGuire I Cycle 22 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 Applicable Bumup Limit Accumulator minimum boron concentration. 0 - 200 EFPD 2,475 ppm Accumulator minimum boron concentration. 200.1 - 250 EFPD 2,407 ppm Accumulator minimum boron concentration. 250.1 - 300 EFPD 2,347 ppm Accumulator minimum boron concentration. 300.1 - 350 EFPD 2,279 ppm Accumulator minimum boron concentration. 350.1 - 400 EFPD 2,216 ppm Accumulator minimum boron concentration. 400.1 -450 EFPD 2,157 ppm Accumulator minimum boron concentration. 450.1 -500 EFPD 2,100 ppm Accumulator minimum boron concentration. 500.1 - 514 EFPD 2,034 ppm Accumulator minimum boron concentration. 514.1 -524 EFPD 2,016 ppm Accumulator maximum boron concentration. 0 - 524 EFPD 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-0400-261 Page 27 of 32 Revision I McGuire 1 Cycle 22 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 MIC22 core is 388,000 gpm. However, the flow is set at 390,000 gpm, which is conservative.

V" *1 MCEI-0400-261 Page 28 of 32 Revision 1 McGuire 1 Cycle 22 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.

t MCEI-0400-261 Page 29 of 32 Revision 1 McGuire 1 Cycle 22 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 bumup 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

v MCEI-0400-261 Page 30 of 32 Revision I McGuire I Cycle 22 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 bumup 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,

4 ~

MCEI-0400-261 Page 31 of 32 Revision I McGuire I Cycle 22 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 350 Concentration BAT Level (ppm) (%level) 0 < 300 37.0 300 < 500 33.0 30 - -500 <700 28.0 700 < 1000 23.0 1000 <1300 13.6

> 1300 8.7 (1 25.0

-J _______"

2 2 , .0 ............

-j I Acceptable Mo.0. .... .. ....................... .. ...

0.0 ___

0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 260o 28W0 RCS Boron Concentration (ppmb)

MCEI-0400-261 Page 32 of 32 Revision I McGuire 1 Cycle 22 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 22 Maneuvering Analysis calculation file, MCC-1553.05-00-0540. 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, upon request.

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