ML040910258

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Cycle 17, Revision 27, Core Operating Limits Report (COLR)
ML040910258
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 03/24/2004
From: Gordon Peterson
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-46 Rev 27
Download: ML040910258 (34)
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Duke GARY R. PETERSON USPowere Vice President A Duke Energy Company McGuire Nuclear Station Duke Power MGOI VP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.com March 24, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station, Docket Nos. 50-369, 370 Unit 1, Cycle 17, Revision 27 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed Revision 27 to the McGuire Unit 1 Cycle 17 Core Operating Limits Report (COLR).

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

4terson Attachment uAoo www. duke-energy. corn

U. S. Nuclear Regulatory Commission March 24,2004 Page 2 cc:

Mr. Leonard Olshan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Luis Reyes, 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-040046 Page I of 32 Revision 27 McGuire Unit 1 Cycle 17 Core Operating Limits Report Revision 27 March 2004 Calculation Number: MCC-1553.05-00-0404 Duke Power Company Date Prepared By:

Checked By:

m;{ /

SkC x It/;.12af CI 2ii/Sz~

Checked By:

Approved By:

I(Setions 2.2kad 2.10 - 2.17)

_gP A

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

MCEI-040046 Page 2 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS IkAW-4e f. 

Inspection Waived By:

Date: S lZAt2.vv4 (Sponsor)

CATAWBA MCE (Mechanical & Civil)

RES (Electrical Only)

RES (Reactor)

MOD Other(

)

Inspection Waived El El El El Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

OCONEE MCE (Mechanical & Civil)

RES (Electrical Only)

RES (Reactor)

MOD Other (

Inspection Waived El El El El El Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

MCGUIRE MCE (Mechanical & Civil)

RES (Electrical Only)

RES (Reactor)

MOD Othcr (

Inspection Waived El Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

MCEI-0400-46 Page 3 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 27 Revision 27 to the McGuire Unit I COLR contains limits specific to the McGuire Unit 1 Cycle 17 core and may become effective any time after no-mode is reached between Cycles 16 and 17. This revision must become effective prior to entering Mode 6 that starts Cycle 17.

MCEI-040046 Page 4 of 32 Revision 27 Revision Revisions 0-3 Revisions 4-8 Revisions 9-11 Revisions 12-15 Revisions 16-17 Revision 18-20 Revision 21-23 Revision 24-26 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report REVISION LOG Effective Date Effective Pages Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A COLR MlCO9 MICI0 MiCl1 MIC12 MIC13 M1CL4 M1C15 MIC16 M1C17 (Original Issue)

Superseded March 12,2004 N/A 1 -32

MCEI-0400-46 Page 5 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report INSERTION SHEET FOR REVISION 27 Remove pages Insert Rev. 27 pages Pages 1 - 32 Pages 1 - 32

MCEI-0400-46 Page 6 of 32 Revision 27 McGuire I Cycle 17 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 Number Technical Specifications 1.1 Requirements for Operational Mode 6 2.1.1 Reactor Core Safety Limits 3.1.1 3.1.3 3.1.4 3.1.5 3.1.5 Shutdown Margin Moderator Temperature Coefficient Rod Group Alignment Limits Shutdown Bank Insertion Limits Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.8 Physics Test Exceptions 3.2.1 Heat Flux Hot Channel Factor 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Setpoint 3.4.1 RCS Pressure, Temperature and Flow limits for DNB 3.5.1 Accumulators 3.5.4 Refueling Water Storage Tank 3.7.14 Spent Fuel Pool Boron Concentration 3.9.1 Refueling Operations - Boron Concentration COLR Parameter Mode 6 Definition RCS Temperature and Pressure Safety Limits Shutdown Margin MTC Shutdown Margin Shutdown Margin Shutdown Bank Insertion Limit Shutdown Margin Control Bank Insertion Limit Shutdown Margin Fq, AFD, OTAT and Penalty Factors FAH, AFD and Penalty Factors AFD OTAT and OPAT Constants RCS Pressure, Temperature and Flow Max and Min Boron Conc.

Max and Min Boron Conc.

Min Boron Concentration Min Boron Concentration COLR Section 2.1 2.2 2.3 2.4 2.3 2.3 2.5 2.3 2.6 2.3 2.7 9

11 9

9 11 9

11 9

15 El Page 9

9 2.8 20 2.9 2.10 2.11 2.12 2.13 2.14 2.15 21 24 26 26 26 28 28 The Selected Licensee Commitments that reference this report are listed below:

SLC Number Selected Licensing Commitment COLR Parameter 16.9-14 Borated Water Source-Shutdown Borated Water Volume and Conc. for BATIRWST 16.9-11 Borated Water Source - Operating Borated Water Volume and Conc. for BAT/RWST COLR Section 2.16 El Page 29 2.17 30

MCEI-040046 Page 7 of 32 Revision 27 McGuire 1 Cycle 17 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 as follows.

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

Revision 0 Report Date: July 1985 Not Used for MIC17

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 MlC17

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

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

Report Date: March 1998

5. 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 MlC17

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

Revision 3 SER Date: September 24, 2003

MCEI-040046 Page 8 of 32 Revision 27 McGuire 1 Cycle 17 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-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 TAC03," (DPC Proprietary).

Revision 0 SER Date: April 3, 1995

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-3ISIMULATE-3P."

Revision I SER Date: April 26, 1996

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

MCEI-0400-46 Page 9 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report 1.1 Analytical Methods (continued)

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

Revision I SER Date: October 1,2002 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 kcrr 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 For TS 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 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 I and mode 2 with K-eff > 1.0.

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

MCEI-0400-46 Page I0of32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report Figure I Reactor Core Safety Limits Four Loops in Operation 670

.l DO NOT OPERATE IN THIlS AREA 660 650

\\

,D 640

40pia 0

630 O 620 I

\\

~2100 psia

\\

610 i

1

~1945 psa i

600 I.

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

MCEI-040046 Page I I of 32 Revision 27 McGuire I Cycle 17 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/0F.

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

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 AKIK/0F.

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 226 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 27 McGuire 1 Cycle 17 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 C.'

c.)

0.

E (U

cs C)

HI-Cu IC.

0 0.9 -

0.8 -

Unacceptable Operation "To (R

0.7 -

0.6 0.5 -

0.4 -

0.3 -

Acceptable Oper Lation

.I 0.2 -

0.1 -

0.0 l

Il 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-0400-46 Page 13 of32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum - 23 1) 231 220 200 c 180 2.

= 160 c 140 C 120

.2 o 100 P.

o 80 c

60 W 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Percent or 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-040046 Page 14 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report Table 1 RCCA Withdrawal Steps and Sequence RCCAs Fully Withdrawn at 226 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start 0

0 226 Stop 110 0

0 226 116 0 Start 0

226 226 Stop 110 0

226 226 116 0 Start 226 226 226 Stop 110 RCCAs Fully Withdrawn at 227 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start 0

0 227 Stop 111 0

0 227 116 0 Start 0

227 227 Stop 111 0

227 227 116 0 Start 227 227 227 Stop 111 RCCAs Fully Withdrawn at 228 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start 0

0 228 Stop 112 0

0 228 116 0 Start 0

228 228 Stop 112 0

228 228 116 0 Start 228 228 228 Stop 112 RCCAs Fully Withdrawn at 229 SWD Control Control Control Control Bank A Bank B Bank.C Bank D 0 Start 0

0 0

116 0 Start 0

0 229 Stop 113 0

0 229 116 0 Start 0

229 229 Stop 113 0

229 229 116 0 Start 229 229 229 Stop 113 RCCAs Fully Withdrawn at 231 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start 0

0 231 Stop 115 0

0 231 116 0 Start 0

231 231 Stop 115 0

231 231 116 0 Start 231 231 231 Stop 115 RCCAs Fully Withdrawn at 230 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 0 Start 0

0 230 Stop 114 0

0 230 116 0 Start 0

230 230 Stop 114 0

230 230 116 0 Start 230 230 230 Stop 114

MCEI-040046 Page 15 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report 2.7 Heat Flux Hot Channel Factor - FQ(X,YZ) (TS 3.2.1) 2.7.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

FRTP *K(Z)IP for P > 0.5 F T *K(Z)I0.5 for P < 0.5

where, P = (Thermal Power)I(Rated Power)

Note: The measured FQ(X,YZ) 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 FRTP =2.50xK(BU) 2.7.3 K(Z) is the normalized FQ(XYIZ) 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(XYIZ) 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:

FQ(X,Y,Z)

  • MQ(X,YZ) 2.7.5 PQ(XYZ)OP =

UMT

  • TILT where:

FQ (XY,Z)OP =

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

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

MCEI-0400-46 Page 16 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report Appendix Table A-2 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-2 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) 2.7.6 FQ(X,Y,Z)R

=

FQ(X,Y,Z)

  • MC(X,Y,Z)

UMT

  • TILT where:

FQ(X,YZ)RPS =

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

FQ(X,Y1Z)RPS includes allowances for calculation and measurement uncertainties.

FQ'(X,Y,Z) =

MC(X,Y,Z) =

Design power distributions for FQ. FQ(X,YIZ) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-2 for power escalation testing during initial startup operation.

Margin remaining to the CFM limit in core location XY,Z from the transient power distribution. Mc(X,YZ) is provided in Appendix Table A-3 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.

MCEI-0400-46 Page 17 of 32 Revision 27 McGuire I Cycle 17 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 compensate for each 1% that F"' (X,Y,Z) exceeds [ FL (X,Y,Z)]

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-0400-46 Page 18 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(XYZ) as a Function of Core Height for Westinghouse RFA Fuel 1.2 1.0 0.8 g

0.6 0.4 0.2 0.0 (0.0, 1.00)

(12.0, 1.0)

-t I

i 0.0 2.0 4.0 6.0 Core Height (ft) 8.0 10.0 12.0

MCEI-0400-46 Page 19 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAH(XY) Penalty Factors For Technical Specification Surveillance's 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burnup (EFPD) 0 4

12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 534 FQ(X,YZ)

Penalty Factor (%)

2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 FAII(X,Y,Z)

Penalty Factor (%)

2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 Note:

Linear interpolation is adequate for intermediate cycle burnups. All cycle burnups outside of the range of the table shall use a 2% penalty factor for both FQ(X,Y,Z) and FA}H(XY) for compliance with the Technical Specification Surveillances 3.2.1.2,3.2.1.3 and 3.2.2.2.

MCEI-040046 Page 20 of 32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report 2.8 Nuclear Enthalpy Rise Hot Channel Factor - FMH(XY)

(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 F4W1 (XY)Lco = MARP (XY) * [I.0 +

  • (1.0 - P)]

where:

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

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

MARP(X,Y) =

Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(XY) 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, FPa (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 Fan (XY)sURv Fa (X, Y) x M. (X, Y) whe:UMRxTLT where:

L SURV Fal (X,Y)

=

Cycle dependent maximum allowable design peaking factor that ensures that the FA,,(X,Y) limit will be preserved for F

SURV operation within the LCO limits. F,1 (X,Y) includes allowances for calculation-measurement uncertainty.

MCEI-0400-46 Page 21 of32 Revision 27 McGuire 1 Cycle 17 Core Operating Limits Report FaH (XY)

MMI(XY)

= Design radial power distribution for Fal F (XY) is provided in Appendix Table A-5 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.

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

MAH(XY) is provided in Appendix Table A-5 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.

IUMR = Uncertainty value for measured radial peaks. UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable M A,,(XY).

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, Fall (XY) 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, Fall (X,Y) exceeds its limit.

2.8.5 Ft,(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 27 McGuire 1 Cycle 17 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPs)

(Applicable for RFA Fuel)

Core Axial Peak->

lit (ft.)

1.05 1.1 1.2 13 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.847 1.882 1.947 1.992 1.974 2.068 2.090 2.049 1.972 1.900 1.778 1.315 1.246 1.2 1.843 1.879 1.938 1.992 1.974 2.068 2.054 2.012 1.935 1.862 1.785 1.301 1.224 2.4 1.846 1.876 1.931 1.981 1.974 2.068 2.025 1.981 1.903 1.832 1.757 1.468 1.456 3.6 1.843 1.869 1.920 1.964 1.974 2.068 2.005 1.968 1.892 1.820 1.716 1.471 1.431 4.8 1.838 1.868 1.906 1.945 1.974 2.006 1.945 1.925 1.862 1.802 1.725 1.326 1.285 6.0 1.834 1.856 1.891 1.921 1.946 1.934 1.878 1.863 1.802 1.747 1.673 1.384 1.317 7.2 1.828.

1.845 1.871 1.893 1.887 1.872 1.809 1.787 1.732 1.681 1.618 1.316 1.277 8.4 1.823 1.829 1.847 1.857 1.816 1.795 1.739 1.722 1.675 1.630 1.551 1.247 1.211 9.6 1.814 1.812 1.809 1.792 1.738 1.724 1.678 1.665 1.621 1.578 1.492 1.191 1.137 10.8 1.798 1.784 1.761 1.738 1.697 1.682 1.626 1.605 1.558 1.512 1.430 1.149 1.097 11.4 1.789 1.765 1.725 1.684 1.632 1.614 1.569 1.557 1.510 1.466 1.392 1.113 1.060

MCEI-040046 Page 23 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits i

iI 90 Unacceptable Operal 80 Ga 0

E I-L.

'I la

.-4 CI W.

r-cX cv 70 Acceptable Operation Unacceptable Operation

(+21, 50) 60 50

(-36,50) 40 30 -

20 +

10 +-

I

1-I I

I 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 I Data Book of more details.

MCEI-0400-46 Page 24 of 32 Revision 27 McGuire 1 Cycle 17 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 Nominal RCS Operating Pressure Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip heatup setpoint penalty coefficient Overtemperature AT reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constants utilized in the lead-lag compensator for Ta,,

Time constant utilized in the measured T3,g lag compensator fl (Al) "positive" breakpoint f l (AI) "negative" breakpoint f 1(Al) "positive" slope f1(Al) "negative" slope T'< 585.10F P'= 2235 psig KI < 1.1978 K2 = 0.0334/OF K3 = 0.001601/psi x1 >8sec.

x2 < 3 sec.

T3 < 2 sec.

xr4 > 28 sec.

rS < 4 sec.

T6<2sec.

= 19.0 %AI

= N/A*

= 1.769 %ATO/ %AI

= N/A*

  • The fl(Al) "negative" breakpoint and the fl(Al) "negative" slope are not applicable since the fl(Al) function is not required below the fl (Al) "positive" breakpoint of 19.0% Al.

MCEI-040046 Page 25 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower AT reactor trip setpoint Overpower AT reactor trip Penalty Overpower AT reactor trip heatup setpoint penalty coefficient Time constants utilized in the lead-lag compensator for AT Time constant utilized in the lag compensator for AT Time constant utilized in the measured T.,g lag compensator Time constant utilized in the rate-lag controller for Tavg f2(AI) "positive" breakpoint f2(Al) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Value T < 585.1OF K4 < 1.0864 K5 = 0.02/0F for increasing Tavg K5 = 0.0 for decreasing Tavg K6 = 0.001 179/0 F for T > T" K6 = 0.0 forT <T'"

> 8 sec.

<3 sec.

3< 2 sec.

r6 < 2 sec.

  • T7 > 5 sec.

= 35.0 %AI

= -35.0 %AI

= 7.0 %ATc/ %AI

= 7.0 %ATd %Al

MCEI-040046 Page 26 of 32 Revision 27 McGuire 1 Cycle 17 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 Cold Leg Accumulator minimum boron concentration.

Cold Leg Accumulator maximum boron concentration.

Limit 2,475 ppm 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 Refueling Water Storage Tank minimum boron concentration.

Refueling Water Storage Tank maximum boron concentration.

Limit 2,675 ppm 2,875 ppm

MCEI-040046 Page 27 of 32 Revision 27 McGuire I Cycle 17 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 0F meter 3

< 586.9 'F 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

MCEI-0400-46 Page 28 of 32 Revision 27 McGuire I Cycle 17 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 System, the refueling canal, and the refueling cavity.

2,675 ppm

MCEI-040046 Page 29 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report 2.16 Borated WaterSource-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 water volume 10,599 gallons 13.6% Level Note: When cycle burnup is > 455 EFPD, Figure 6 may be used to determine the required BAT minimum level.

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

MCEI-040046 Page 30 of 32 Revision 27 McGuire 1 Cycle 17 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 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.

Boric Acid Tank minimum boron concentration Boric Acid Tank minimum water volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained borated water volume Refueling Water Storage Tank minimum boron concentration Refueling Water Storage Tank maximum boron concentration (TS 3.5.4)

Refueling Water Storage Tank minimum water volume required to maintain SDM at 2,675 ppm 7,000 ppm 13,750 gallons 96,607 gallons 103.6 inches 2,675 ppm 2875 ppm 57,107 gallons

MCEI-0400-46 Page 31 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus RCS Boron Concentration (Valid When Cycle Burnup is > 455 EFPD)

This figure includes additional volumes listed in SLC 16.9-14 and 16.9-11 40.0-----

RCS Boron 35.0 tConcentration BAT Level (ppm)

.(level) 0 < 300 37.0 300 < 500 I

33.0 30.0 500<700

_28.0

_00 < 1000 23.0 1000 < 1300; 13.6 25.0

> 1300 8.7

-200 15.0 0

I 10.0]

50 Unacceptable Operation 5.0

0.

0 O 200 400 600 800 tO00 1200 1400 1600 t800 2000 2200 2400 260D 2800 RCS Boron Concentration (pprnb)

MCEI-0400-46 Page 32 of 32 Revision 27 McGuire I Cycle 17 Core Operating Limits Report NOTE: Data contained in the Appendix to this document was generated in the McGuire I Cycle 17 Maneuvering Analysis calculation file, MCC-1553.05-00-0387. 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.

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