ML070940684

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Cycle 19, Revision 30 Core Operating Limits Report (COLR)
ML070940684
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 03/27/2007
From: Gordon Peterson
Duke Energy Carolinas, Duke Power Co
To:
Document Control Desk, NRC/NRR/ADRO
References
MCEI-0400-46 Rev 30
Download: ML070940684 (35)
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Text

A-Duke a-Powero GARY R. PETERSON Vice President A Duke Energy Company McGuire Nuclear Station Duke Power MG01VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.corn March 27, 2007 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station Docket Nos. 50-369 Unit 1, Cycle 19, Revision 30 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification (TS) 5.6.5.d, please find enclosed Revision 30 to the McGuire Unit 1 Cycle 19 Core Operating Limits Report (COLR).

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

Gary 7eterson Attachment www. dukepower. corn AODI

. . k" U. S. Nuclear Regulatory Commission March 27, 2007 Page 2 cc: Mr. John Stang, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30323 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station

U.S. Nuclear Regulatory Commission March 27, 2007 Page 3 bxc: RGC File ECO50-ELL Master File

MCEI-0400-46 Page 1 of 32 Revision 30 McGuire Unit 1 Cycle 19 Core Operating Limits Report March 2007 Calculation Number: MCC-1553.05-00-0463, Rev. 0 Duke Energy Date Prepared By:

Checked By:

Checked By:

6Qct22-

/* fg/k/ 7" Approved By:

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

MCEI-0400-46 Page 2 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:

(Sponsor)

Re h" p Date: 3 CATAWBA CATAWiBA Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:

RES (Electrical Only) El Inspected By/Date:

RES (Reactor) El Inspected By/Date:

MOD LI Inspected By/Date:

Other( ) El Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) El El Inspected By/Date:

El Inspected By/Date:

MOD El Other ( ) Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( ) El Inspected By/Date:

MCEI-0400-46 Page 3 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Implementation Instructions for Revision 30 Revision Description and PIP Tracking This revision of the McGuire Unit 1 COLR contains limits specific to the McGuire 1 Cycle 19 reload core. There is no PIP.associated with this revision.

Implementation Schedule This revision may become effective at any time during No Mode between Cycles 18 and 19 but must become effectiveprior to entering Mode 6, which starts Cycle 19.

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

Insertion/Deletion Instructions Remove Insert pages 1-.32 of rev 29 pages 1- 32 of rev 30 (including Appendix A*) (including Appendix A*)

  • 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-0400-46 Page 4 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Pages COLR Revisions 0-3 Superseded N/A M1C09 Mi~

Revisions 4-8 Superseded N/A M1C10 Revisions 9-11 Superseded N/A MICH2 Revisions 12415 Superseded N/A MIC12 Revisions 16-17 Superseded N/A M1C13 Superseded N/A MIC14 Revision 18-20 Revision 21-23 Superseded N/A MIC15 Revision 24-26 Superseded N/A M1C16 Revision 27 Superseded N/A M1C17 Revision 28-29 May 2006 1-32 M1C18 Revision 30 March 2007 1-32 M1C19 (Original Issue)

MCEI10400-46 Page 5 of 32 Revision 30 McGuire 1 Cycle 19 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 Page 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 11 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 Cone. 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 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

MCEI-0400-46 Page 6 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Conc. for BAT/RWST 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," Q Proprietary).

Revision 0 Report Date: July 1985 Not Used for M1C19

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 M1C19

4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," & 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 1 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 M1C19

MCEI-0400-46 Page 7 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 3 SER Date: September 24, 2003

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

Revision 0 Report Date: November 1991 (Republished December 2000)

8. DPC-NE-3002A, "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-01," (DPC Proprietary).

Revision 1 SER Date: February 20, 1997

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

Revision 3 SER Date: September 16, 2002

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

Revision 0 SER Date: April 3, 1995 Not Used for M1C19

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

Revision 2 SER Date: December 18, 2002

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

Revision 1 SER Date: April 26, 1996 Not Used for M1C19

MCEI-0400-46 Page 8 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 1.1 Analytical Methods (continued)

14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station.

Nuclear Physics Methodology for Reload Design."

Revision 2 SER Date: June 24, 2003

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

Revision 1 SER Date: October 1, 2002

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

(DPC Proprietary).

Revision 0 SER Date: August 20, 2004

MCEI-0400-46 Page 9 of 32 Revision 30 McGuire 1 Cycle 19 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 kIff 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 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 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 Testing.

MCEI-0400-46 Page 10 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 ______

640 A0220 p~sia 630 Ui 620 _____

61 0_____ _

600 ______

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

MCEI-0400-46 Page 11 of 32 Revision 30 McGuire 1 Cycle 19 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/K/°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/°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. Shutdown banks are withdrawn in sequence and with no overlap.

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. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.

MCEI-0400-46 Page 12 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation 0.8 E

0.7 0.6 0.5 0? Acceptable Operation 0.4 0.3 0

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/1/A/6100/22 Unit 1 Data Book for details.

MCEI-0400-46 Page 13 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231) 231 220 200 180 160

  • 140

' 120 o 100

.280

. 60 0 40 20 0

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

Bank CD RIL = 2.3(P)- 69 {30 < P < 100}

Bank CC R/L = 2.3(P) + 47 {0*< P*<580}

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

where P = %Rated Thermal Power NOTE: 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.

MCEI-0400-46 Page 14 of 32, Revision 30 McGuire 1 Cycle 19 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 0OStart 0 0 0 116 0OStart 0 0 116 0OStart 0 0 222 stop 106 0 0 223 Stop 107 0 0.

222 116 0 Start 0 223 116 0OStart 0 222 222 Stop 106 0 223 223 Stop 107 0 222 222 116 0 Start 223 223 116 0OStart 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 Bank A Bank B Bank C Bank D 0OStart 0 0 0 0OStart 0 0 0-116 0OStart 0 0 116 0OStart 0 0 224 Stop 108 0 0 225 Stop 109 0 0 224 116 0 Start 0 225 116 0OStart 0 224 224 Stop 108 0 225 225 Stop 109 0 224 224 116 OSt=r 225 225 116 0OStart

  • 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 Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0OStart 0 0 0 0OStart 0 0 0 116 0 Start 0 0 116 0OStart 0 0 226 Stop 110 0 0 227 Stop 111 0 0 226. 116 0OStart 0 227 116 0 Start 0 226 226 Stop 110 .0 227 227 Stop ill .0
  • 226 226 116 0OStart 227 227 116 . 0OStart 226 226 .226 Stop 110 227 227 227 Stop . Ill Fully Withdrawn at 228 Steps Fully Withdrawn at 229 Steps Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C .Bank D 0OStart 0 0 0 0OStart 0 0 0 116 0OStart 0 0 116 0OStart 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0OStart 0 229 116 0OStart 0 228 228 Stop 112 0 229 229 Stop 113, 0
  • 228 228 116 0OStart 229 229 116 0OStart 228 228 228 Stop 112 229 229 229 Stop 113 Fully. Withdrawn at 230 Steps Fully Withdrawn at 231 Steps Control Control Control Control Control Control Control Control Bank A B ank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0OStant 0 0 0 116 0OStant 0 0 116 0OStart 0 0 230OStop 114 0 0 231 Stop 115 0 0 230 116 0OStart 0 231 116 0OStart 0 230 230OStop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0OStart 230 230 230 Stop 114 231 231 , 231IStop 115

MCEI-0400-46 Page 15 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 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 thefollowing relationships:

F QRTP *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 =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 bumup. 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:

2.7.5 I= ~Q(XY,Z)

  • MQ(X,Y,Z) 5Q(XYZ) UMT
  • MT* TILT where:

FQ (X,Y,Z)OP = Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) LOCA limit will be preserved for operation within the LCO limits. F* (X,Y,Z)OP includes allowances for calculation and measurement uncertainties.

Fjf (X,Y,Z) = Design power distribution for FQ. Fcf (X,Y,Z) is provided in Appendix A-1 for normal operating conditions and in

MCEI-0400-46 Page 16 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 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.

UNIT = Total Peak Measurement Uncertainty. (UNIT = 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)

Ft*(X,Y,Z)

  • Mc(X,Y,Z) 2.7.6 F'Q(X,Y,Z) =

UNIT

  • TILT where:

FL$(X,Y,Z)RPS = Cycle dependent maximum allowable design peaking factor that ensures that the FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit will be preserved for operation within the LCO limits.

FLQ(X,Y,Z)RPS includes allowances for calculation and measurement uncertainties.

D~XYZ Design power distributions for FQ. FtQ(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 Mc(X,Y,Z) =

startup operation.

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.

MCEI-0400-46 Page 17 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 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 M L,( y ZRPS.

compensate for each 1% that FQ (X,Y,Z) exceeds FL (X,Y,Z)s 2.7.8 FQ(X,YZ) penalty factors for Technical Specification Surveillance's 3.2.1.2 and 3.2.1.3 are provided in Table 2.

MCEI-0400-46 Page 18 of 32

. Revision 30 McGuire 1 Cycle 19 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 ((12,00099615)

(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 4 8 I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)-

MCEI-0400-46 Page 19 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAH(X,Y) Penalty Factors For Technical Specification Surveillance's 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup FQ(X,Y,Z) FtA(X,Y,Z)

OEFPD) 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 2.51 2.00 75 2.54 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 2.00 479 2.00 2.00 489 2.00 2.00 504 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle burnups. All cycle bumups 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-0400-46 Page 20 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 2.8 Nuclear Enthalpy Rise Hot Channel Factor - FAJH(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 FL (X, Y)Lc= MARP (X,Y)

  • 1.0 + * (1.0- P)]

where:

FL (X, Y)LCo is defined as. the steady-state, maximum allowed radial peak.

FL (X, Y)L 0 includes allowances for calculation-measurement uncertainty.

MARP(X,Y) = Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in Table 3.

P Thermal Power Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1%that the measured radial peak, F, (X,Y), exceeds the limit. RRH also is used to scale the MARP limits as a function of power per the FL (X, Y)LCO equation. (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 (XY"SURV F- (X, Y) x M,, (X, Y)

UMR x TILT where:

FLH (X,Y)sURv = Cycle dependent maximum allowable design peaking factor that ensures that the F.(X,Y) limit willLbe preserved URV-for operation within the LCO limits. FL (X,Y) includes allowances for chlculation-measurement uncertainty.

MCEI-0400-46 Page 21 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report F,', (X,Y) = Design radial power distribution for F.. F (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.

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

M&H(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.

JvUMR = 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, FH (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, Fý (X,Y) exceeds its limit.

2.8.5 FAH(X,Y) 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-0400-46 Page 22 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPs)

(Applicable for RFA Fuel)

Core Axial Peak Ht (ft.) 01.05 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-0400-46 Page 23 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits I...

0 0

.0

  • 0 0

0 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/l/A/6100/22 Unit 1 Data Book of more details.

MCEI-0400-46 Page 24 of 32 Revision 30 McGuire 1 Cycle 19 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. IF Nominal RCS Operating Pressure = 2235 psig Overtemperature AT reactor trip setpoint KI < 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.0334/ 0 F penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator ,r1 > 8 sec.

for AT U2 < 3 sec.

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

Time constants utilized in the lead-lag compensator r4 > 28 sec.

for Tavg T5 < 4 sec.

Time constant utilized in the measured Tavg lag "E6 < 2 sec.

compensator fl(Al) "positive" breakpoint = 19.0 %AI fl(A1) "negative" breakpoint - N/A*

fl(AI) "positive" slope - 1.769 %AT0/ %AI fl(AI) "negative" slope = N/A*

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 f 2(AI) limits will result in a reactor trip before the OTAT fl(Al) limits are reached. This makes implementation of an OTAT fl(AT) negative breakpoint and slope unnecessary.

MCEI-0400-46 Page 25 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T" < 585.1°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 decreasingTavg 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-lag "r > 8 sec.

compensator for AT T2 < 3 sec.

Time constant utilized in the lag T3 < 2 sec.

compensator for AT Time constant utilized in the T6 < 2 sec.

measured Tavg lag compensator Time constant utilized in the rate-lag T7 > 5 sec.

controller for Tavg f2 (AI) "positive" breakpoint = 35.0 %AI f2 (Al) "negative" breakpoint = -35.0 %AI f2(AI) "positive" slope = 7.0 %ATd %AI f2(AI) "negative" slope = 7.0 %ATo %AI

MCEI-0400-46 Page 26 of 32 Revision 30 McGuire 1 Cycle 19 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 Cold Leg Accumulator minimum boron concentration. 2,475 ppm Cold Leg 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 Refueling Water Storage Tank minimum boron 2,675 ppm concentration.

Refueling Water Storage Tank maximum boron 2,875 ppm concentration.

MCEI-0400-46 Page 27 of 32 Revision 30 McGuire 1 Cycle 19 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 °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 >390,000 gpm*
  • Note: The RCS minimum coolant flow rate assumed in the licensing analyses for the M1C19 core is 388,000 gpm. However, the flow is set at 390,000 gpm, which is conservative

MCEI-0400-46 Page 28 of 32 Revision 30 McGuire 1 Cycle 19 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-0400-46 Page 29 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 2.16 Borated Water Source - 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 Boric Acid Tank minimum contained borated 10,599 gallons water volume 13.6% Level Note: When cycle burnup is > 455 EFPD, Figure 6 may be used to determine the required BAT minimum level.

Boric Acid Tank minimum boron concentration 7,000 ppm Boric Acid Tank minimum water volume 2,300 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum 47,700 gallons contained borated water volume 41 inches Refueling Water Storage Tank minimum boron 2,675 ppm concentration Refueling Water Storage Tank minimum water 8,200 gallons volume required to maintain SDM at 2,675 ppm

MCEI-0400-46 Page 30 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report 2.17 Borated Water Source - 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 Boric Acid Tank minimum contained borated 22,049 gallons water volume 38.0% Level Note: When cycle burnup is > 455 EFPD, Figure 6 may be used to determine the required BAT minimum level.

Boric Acid Tank minimum boron concentration 7,000 ppm Boric Acid Tank minimum water volume 13,750 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum 96,607 gallons contained borated water volume 103.6 inches Refueling Water Storage Tank minimum boron 2,675 ppm concentration Refueling Water Storage Tank maximum boron 2875 ppm concentration (TS 3.5.4)

Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,675 ppm

MCEI-0400-46 Page 31 of 32 Revision 30 McGuire 1 Cycle 19 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 Bor on Concentra tion BAT Level 35.0-(ppm) (%level) 0< 300 37.0 300 <5C0, 33.0 30.0 - - . 500 < 7 0 28.0 700 < 1 )0 23.0 1000 < 13,00~ 13.6

_ t___- > 1300 817

> 25.0

-J

-0

- 20.0 CD. Acceptable Operation 15!.0.

10.0

  • rIn i Unacceptable Operation 5.0 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 280O 0 200 RCS Boron Concentration (ppmb)

MCEI-0400-46 Page 32 of 32 Revision 30 McGuire 1 Cycle 19 Core Operating Limits Report NOTE: Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire 1 Cycle 19 Maneuvering Analysis calculation file, MCC-1553.05-00-0453. 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.

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