ML062760240

Cycle 18, Revision 26 to Core Operating Limits Report (COLR)

ML062760240
Person / Time
Site:	Mcguire
Issue date:	09/20/2006
From:	Gordon Peterson Duke Energy Carolinas, Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MCC-1553.05-00-0447, Rev 0 MCEI-0400-47, Rev 26
Download: ML062760240 (34)

Text

GARY R. PETERSON I Duke Vice President Energy McGuire Nuclear Station Duke Energy Corporation MGOIVP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 704 875 5333 704 875 4809 fax grpeters@duke-energy.com September 20, 2006 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. 50-370 Unit 2, Cycle 18, Revision 26 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification (TS) 5.6.5.d, please find enclosed Revision 26 to the McGuire Unit 2 Cycle 18 Core Operating Limits Report (COLR).

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

Gary R. Peterson Attachment 7DO I www.duke-energy. com

U. S. Nuclear Regulatory Commission September 20, 2006 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

MCEI-0400-47 Page I of 32 Revision 26 McGuire Unit 2 Cycle 18 Core Operating Limits Report Revision 26 August 2006 Calculation Number: MCC-1553.05-00-0447 (Rev. 0)

Duke Energy Date Prepared By:

Checked By: AN q1 - aeL,0 /

/

Checked By:

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-0400-47 Page 2 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date:f/

(Sponsor)

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

Other( ) El Inspected By/Date:

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

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( ) Inspected By/Date:

MCEI-0400-47 Page 3 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Implementation Instructions For Revision 26 Revision Description and PIP Tracking Revision 26 of the McGuire Unit 2 COLR contains limits specific to the McGuire 2 Cycle 18 reload core. There is no PIP associated with this revision.

Implementation Schedule Revision 26 may become effective any time during No Mode between Cycles 17 and 18 but must become effective prior to entering Mode 6, which starts Cycle 18.

This revision replaces the current revision (MCEI-0400-47, Rev. 25).

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

Insertion/Deletion Instructions Remove Insert pages 1- 33 of Rev. 25 pages 1- 32 of Rev 26 (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-04(X)-47 Page 4 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report REVISION LOG Revision Issuance Date Effective Pages COLR Revisions 0-2 Superseded N/A M2C09 Revisions 3-6 Superseded N/A M2CIO Revisions 7-12 Superseded N/A M2CI1 Revision 13-15 Superseded N/A M2C12 Revision 16-17 Superseded N/A M2C13 Revision 18-20 Superseded N/A M2C14 Revision 21-22 Superseded N/A M2C15 Revision 23-24 Superseded N/A M2C16 Revision 25 March 2005 1-33 M2CI7 Revision 26 August 2006 1-32 M2CI8 (Orig. Issue)

MCEI-0400-47 Page 5 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference 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 TestsExceptions 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 FAIl, 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 Constants 3.4.1 RCS Pressure, Temperature, and Flow RCS Pressure, 2.11 26 DNB limits Temperature and Flow 3.5.1 Accumulators Max and Min Boron Cone. 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 Cone. for BAT/RWST 16.9.11 Borated Water Source - Operating Borated Water Volume and 2.17 30 Cone. for BAT/RWST

MCEI-0400-47 Page 6 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC, 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 M2C18

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 M2C18

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 I (Revision 2) and Volumes 2-5 (Revision 1)

Report Date: March 1998

5. BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B&W Proprietary).

Revision 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 M2C18

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

Revision 3 SER Date: September 24. 2003

MCEI-0400-47 Page 7 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)

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-0 1," (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 M2C18

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

Revision 2 SER Date: December 18, 2002

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

Revision I SER Date: April 26, 1996 Not Used for M2C18

MCEI-0400-47 Page 8 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision 2 SER Date: June 24,2003

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

Revision 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-0400-47 Page 9 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the 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 ForTS 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% 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 I and mode 2 with K-eff > 1.0.

2.3.6 ForTS 3.1.8, SDM shall be > 1.3% AK/K in mode 2 during Physics Testing.

MCE1-0400-47 Page 10 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 1 Reactor Core Sarety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 620 1-.

600 .....

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

MCEI-0400-47 Page 11 of 32 Revision 26 McGuire 2 Cycle 18 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/ 0 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/ 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 (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. 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-0400-47 Page 12 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 0.8 0.7 0.6 0 0.5 U* Q 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/2/AI6100/22 Unit 2 Data Book for details.

MCEI-0400-47 Page 13 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 3 Control 'Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231)N 231 220 (80 .2 1)

J 200 180 S..

160 (o%. 16.3.) 7 U,

a. 140 U,

a 120 (29.)

- 6%,231)

-. .-.

0 100 a

C 80 I-Control Bank 60

'C 0

-(0%.,47) -

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<5 P5 100}

Bank CCRIL = 2.3(P) + 47 {0 < P < 80}

Bank CBRIL = 2.3(P) + 163 {O*< P5 <29.6}

where P = %Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.

Refer to OP/2/A16100122 Unit 2 Data Book for details.

MCEI-0400-47 Page 14 of 32 Revision 26 McGuire 2 Cycle 18 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 BankD 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Stan 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Star 0 223 116 0Stant 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 Sart 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 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 0Start 0 0 2

226 Stop [10 0 0 2 7 Stop II1 0 0 226 116 0 Start 0 227 116 0Start 0 22 226 226 Stop 110 0 227 7 Stop 11I 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 stop IlI Fully Withdrawn at 228 Steps Fully Withdrawn at 229 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 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 OStart 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 Stcps 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 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 0Stan 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Sart 230 230 230 Stop 114 231 231 231 Stop 115

MCEI-0400-47 Page 15 of 32 Revision 26 McGuire 2 Cycle 18 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 the following relationships:

F 0Rr* *K(Z)/P for P > 0.5 F QRrP *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 the 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-QR, = 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:

D 2.7.5 F((X,Y,Z)OP = F6(X,Y,Z)

• MQ(X,Y,Z)

UMT

• MT

• TILT where:

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

F0D(X,Y,Z) = Design power distribution for FQ. F n(X,Y,Z) is provided in Appendix Table A-I for normal operating conditions, and in

MCET-0400-47 Page 16 of 32 Revision 26 McGuire 2 Cycle 18 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-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)

D F6(X,Y,Z)

• Mc(X,YZ) 2.7.6 FL(X,Y,Z) RPS UMT

• MT

• TILT where:

L FQ(X,Y,Z)RP = Cycle dependent maximum allowable design peaking factor that ensures 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.

Fý(X,Y,Z) = Design power distributions for FQ. F6(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.

MC(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z in 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-0400-47 Page 17 of 32 Revision 26 McGuire 2 Cycle 18 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 from 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 the OTAT trip setpoint required RPS to compensate for each 1% that F,' (X,YZ) exceeds FL (X,YZ) 2.7.8 FQ(X,Y,Z) penalty factors for Technical Specification Surveillance's 3.2.1.2 and 3.2.1.3 are provided in Table 2.

MCEI-0400-47 Page 18 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(XY,Z) as a Function of Core Height for Westinghouse RFA Fuel 1.200 (0.0. 1.00) (4.0, 1.00) 1.000 1.,.65 (40I .61)

(4.0,.0.9615) ( 12.0, 0.9615) 0.800 -

0.600 +

0.400 Core Height (fIt) K(Z) 0.0 1.000

<4 1.000 0.200 >4 0.9615 12.0 0.9615 0.000 -

0.00 2.00 4.00 6.00 8.00 10.00 12.00 Core Height (ft)

MCEI-0400-47 Page 19 of 32 Revision 26 McGuire 2 Cycle 18 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) F~A(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 2.00 464 2.00 2.00 489 2.00 2.00 499 2.00 2.00 514 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-0400-47 Page 20 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 2.8 Nuclear Enthalpy Rise Hot Channel Factor - FjH(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 FLI (X, Y) Lco = MARP (X,Y)

• 1.0 + R- (1.0 -

where:

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

FAI (X,Y)Lco 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, F* (X,Y), exceeds its limit. RRH also is used to scale the MARP limits as a function of power per the [FAH (X, Y)]tco 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.

L StURV -F*I(X,Y) xMAn (X,Y) 2.8.2 FL (X,Y) = U MR TL X UMRw TrLT where:

FAL (XY)sURv Cycle dependent maximum allowable design peaking factor that ensures the FAH(XY) limit will be preserved for operation within the LCO limits. FL,L (X,Y)SURv includes allowances for calculation/measurement uncertainty.

MCEI-0400-47 Page 21 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report F,'H (XY) = Design radial power distribution for F'a" FDH MY) provided in Appendix Table A-3 for normal operation, and in Appendix Table A-6 for power escalation testing during initial startup operation.

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

MAH(X,Y) is provided in Appendix Table A-3 for normal operation, and in Appendix Table A-6 for power escalation testing during initial startup operation.

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

TILT = Peaking penalty that accounts for 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, Fa (X,Y) exceeds its limit. (0 < P < 1.0) 2.8.4 TRH = 0.04 where:

TRH = Reduction in the 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 forTechnical 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-0400-47 Page 22 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

RFA MARPS 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-0400-47 Page 23 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

(-18, 100) (+10, 100)

_ I [?:* _

90 Unacceptable Operation Unacceptable Operation 80-Acceptable Operation 70-40 a.t 60

(-36, 50) 50

(+21, 50) 40-30+

20+

10-I 0I 20 30I4 5

-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 OPI2IA/6100122 Unit 2 Data Book for more details.

MCEI-0400-47 Page 24 of 32 Revision 26 McGuire 2 Cycle 18 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' <585.10 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 "t > 8 sec.

for AT t2 < 3 sec.

Time constant utilized in the lag compensator for AT x 3 < 2 sec.

Time constants utilized in the lead-lag compensator *t4 > 28 sec.

for T.,9 'r5 < 4 sec.

Time constant utilized in the measured Tv, lag x6 < 2 sec.

compensator fl(AI) "positive" breakpoint = 19.0 %AI fl(AI) "negative" breakpoint = NIA*

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

The fl(AI) "negative" breakpoints and the fl(AI) "negative" slope are less restrictive than the OPAT f 2 (Al) 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(AI) limits are reached. This makes implementation of the OTAT fl (AT) negative breakpoint and slope unnecessary.

MCEI-0400-47 Page 25 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T'" < 585.11F Overpower AT reactor trip setpoint K4 < 1.0864 Overpower AT reactor trip Penalty K5 = 0.021/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 forT< T" Time constants utilized in the lead-lag T, > 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 r6 <2 sec.

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

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

MCEI-0400-47 Page 26 of 32 Revision 26 McGuire 2 Cycle 18 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 I 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-0400-47 Page 27 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable Parameter Indication Channels Limits

1. Indicated RCS Average Temperature meter 4 < 587.2 IF meter 3 < 586.9 OF computer 4 < 587.7 IF 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 > 388,000 gpm

MCEI-0400-47 Page 28 of 32 Revision 26 McGuire 2 Cycle 18 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-0400-47 Page 29 of 32 Revision 26 McGuire 2 Cycle 18 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 > 460 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-0400-47 Page 30 of 32 Revision 26 McGuire 2 Cycle 18 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 temperature > 300 'F.

Parameter Limit Boric Acid Tank minimum contained borated 22,049 gallons water volume 38.0% Level Note: When cycle burnup is > 460 EFPD, Figure 6 may be used to determine the required BAT minimum level. I 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 2,875 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-0400-47 Page 31 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus RCS Boron Concentration (Valid When Cycle Burnup is > 460 EFPD)

This figure includes additional volumes listed in SLC 16.9.14 and 16.9.11 40.0-- -.-

RCS Boron 35.0, Concentration;: BAT Level (ppm) (%/.level) 0 < 300-- 37.0 30-<5  :-33.0

-'700'<1I000.... 23.0-Z. 1*0 3-0.0

• 1 "13.6 C>

ý- 25.0 -.. . .. 1300

. . .. ."-8.7

.

- 20.0.

Acceptable Operation 15.0o 10.0 -I Unacceptable Operation 5.0 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 20O0 20 2400 2600 2800 RCS Boron Concentration (ppmb)

MCEI-0400-47 Page 32 of 32 Revision 26 McGuire 2 Cycle 18 Core Operating Limits Report NOTE: Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire 2 Cycle 18 Maneuvering Analysis calculation file, MCC-1553.05-00-0437. 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.