ML020870344

Core Operating Limits Report (Colr), Revision 21, Cycle 15

ML020870344
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/20/2002
From:	Barron H Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-47, Rev. 21
Download: ML020870344 (32)

Text

Duke Energy Corporation Duke LEnergy. McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-9340 H. B. Barron (704) 875-4800 OFFICE Vice President (704) 875-4809 FAx March 20, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station, Docket No.50-369, 50-370 Unit 2 Cycle 15 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed the McGuire Unit 2 Core Operating Limits Report (COLR). Revision 21 contains limits specific to the McGuire Unit 2 Cycle 15 core.

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

H. B. Barron Attachment

ý\Orjý

U. S. Nuclear Regulatory Commission March 20, 2002 Page 2 cc: Mr. R. E. Martin, 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. Scott Shaeffer Senior Resident Inspector McGuire Nuclear Station

U.S. Nuclear Regulatory Commission March 20, 2002 Page 3 bxc: RGC File ECO50-ELL P. M. Abraham

MCEI-0400-47 Page I of 29 Revision 21 McGuire Unit 2 Cycle 15 Core Operating Limits Report Revision 21 February 2002 Calculation Number: MCC- 1553.05-00-0358 Duke Power Company Date Prepared By:

Checked By: 5. Ada Checked By:

Approved By: z 12'/1)/__4 QA Condition 1

MCEI-0400-47 Page 2 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 21 Revision 21 of the McGuire Unit 2 COLR contains limits specific to the McGuire 2 Cycle 15 core and may become effective any time during the no-mode between Cycles 14 and 15.

This revision must become effective prior to entering Mode 6 that starts Cycle 15.

This COLR revision also incorporates a list of reports describing the analytical methods used in determining core operating limits. This addition is based upon a pending Technical Specification Amendment that requires the COLR to contain a complete list of the Technical Specification 5.6.5 reference topical reports used for parameters contained in the COLR. Inclusion of the reference list alleviates the need to revise the COLR following NRC approval of the Technical Specification amendment.

MCEI-0400-47 Page 3 of 29 Revision 21 McGuire 2 Cycle 15 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 M2C1O Revisions 7-12 Superseded N/A M2C I1 Revision 13-15 Superseded N/A M2C12 Revision 16-17 Superseded N/A M2C13 Revision 18-20 Superseded N/A M2C14 Revision 21 February 12, 2002 1-29 M2C 15 - Orig. Issue

MCEI-0400-47 Page 4 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report INSERTION SHEET FOR REVISION 21 Remove pages Insert Rev. 21 pages Pages 1-27, 27a and Appendix A Pages 1-29 and Appendix A

MCEI-0400-47 Page 5 of 29 Revision 21 McGuire 2 Cycle 15 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 this report are listed below:

"TS Technical COLR COLR Section Specifications Section Page 1.1 Requirements for Operational Mode 6 2.1 8 3.1.1 Shutdown Margin 2.2 8 3.1.3 Moderator Temperature Coefficient 2.3 8 3.1.4 Shutdown Margin 2.2 8 3.1.5 Shutdown Margin 2.2 8 3.1.5 Shutdown Bank Insertion Limit 2.4 9 3.1.6 Shutdown Margin 2.2 8 3.1.6 Control Bank Insertion Limit 2.5 9 3.1.8 Physics Test Exceptions 2.2 8 3.2.1 Heat Flux Hot Channel Factor 2.6 13 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 2.7 18 3.2.3 Axial Flux Difference 2.8 19 3.3.1 Reactor Trip System Instrumentation Setpoint 2.9 22 3.5.1 Accumulators 2.10 24 3.5.4 Refueling Water Storage Tank 2.11 24 3.7.14 Spent Fuel Pool Boron Concentration 2.12 25 3.9.1 Refueling Operations - Boron Concentration 2.13 25 The Selected Licensee Commitments that reference this report are listed below:

SLC COLR COLR Section Selected License Commitments Section Page 16.9.14 Borated Water Source - Shutdown 2.14 26 16.9.11 Borated Water Source - Operating 2.15 27 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 M2C15

MCEI-0400-47 Page 6 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 1.1 Analytical Methods Continued

2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, " ( Proprietary).

Revision 0 Report Date: August 1985 Note: Amendments to this report are included in Ref. 12.

3. WCAP-10266-P-A, "THIE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", (W Proprietary).

Revision 2 Report Date: March 1987 Not Used for M2C15

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 M2C15

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

Revision 2 SER Date: October 14, 1998

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

Revision 0 Report Date: November 1991

MCEI-0400-47 Page 7 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report

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

Revision 3 SER Date: February 5, 1999

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 1 SER Date: November 7, 1996

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

Revision 0 SER Date: April 3, 1995

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

Revision 0 SER Date: September 22, 1999

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

Revision 1 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 0 Report Date: June 1985

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

Revision 0 Report Date: March 1990

MCEI-0400-47 Page 8 of 29 Revision 21 McGuire 2 Cycle 15 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 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6 and TS 3.1.8) 2.2.1 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.

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

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

2.2.4 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.

2.2.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in mode 1 and mode 2 with K-efft> 1.0.

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

2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:

The MTC shall be less positive than the upper limits shown in Figure 1. 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. 1E-04 AK/K/IF lower MTC limit.

MCEI-0400-47 Page 9 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.3.2 The 300 ppm MTC Surveillance Limit is:

The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.2E-04 AK/K/°F.

2.2.3 The 60 PPM MTC Surveillance Limit is:

The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to

-3.85E-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) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 226 steps. Shutdown banks are withdrawn in sequence and with no overlap.

2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.

MCEI-0400-47 Page 10 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 0

0.8 0

0 0.7 U

0 0.6 Cu I-i 0

0.5 0

0 0.4 0

0 0.3 Cu 0 0.2 0

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/A/6100/22 Unit 2 Data Book for details.

MCEI-0400-47 Page 11 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231) 231 220 200 180 PC

~160

o. 140 S120 0

o100 80 60 S40 20 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/A/6100/22 Unit 2 Data Book for details.

MCEI-0400-47 Page 12 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Table 1 RCCA Withdrawal Steps and Sequence RCCAs Fully Withdrawn at 226 SWD RCCAs Fully Withdrawn at 227 SWD Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D O Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 226 Stop 110 0 0 227 Stop 111 0 0 226 116 0 Start 0 227 116 0 Start 0 226 226 Stop 110 0 227 227 Stop 111 0 226 226 116 0 Start 227 227 116 0 Start 226 226 226 Stop 110 227 227 227 Stop 111 RCCAs Fully Withdrawn at 228 SWD RCCAs Fully Withdrawn at 229 SWD Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 0 Start 0 228 228 Stop 112 0 229 229 Stop 113 0 228 228 116 0 Start 229 229 116 0 Start 228 228 228 Stop 112 229 229 229 Stop 113 RCCAs Fully Withdrawn at 230 SWD RCCAs Fully Withdrawn at 231 SWD Control Control Control Control Control Control Control Control Bank A Bank B Bank C Bank D Bank A Bank B Bank C Bank D 0 Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 230 Stop 114 0 0 231 Stop 115 0 0 230 116 0 Start 0 231 116 0 Start 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Start 231 231 2 3 1 Stop 115 230 230 230 Stop 114

MCEI-0400-47 Page 13 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,YZ) steady-state limits are defined by the following relationships:

FRrP *K(Z)/P for P > 0.5 FQRT *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(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 the LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.

2.6.2 F-Q" = 2.50 x K(BU) 2.6.3 K(Z) is the normalized FQ(X,YZ) as a function of core height. The K(Z) function for both Mk-BW and Westinghouse RFA fuel is provided in Figure 3.

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

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

2 .5 Q(X,Y,Z)

• MQ(X,Y,Z)

Q = UMT

• MT

• TILT where:

FL (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. [ FL (X,Y,Z)IOP includes allowances for calculation and measurement uncertainties.

F (X,Y,Z) = Design power distribution for FQ. FQ)(X,Y,Z) is provided in Table 4, Appendix A, for normal operating conditions and in

MCEI-0400-47 Page 14 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Table 5, Appendix A 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 Table 4, Appendix A for normal operating conditions and in Table 5, Appendix A 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)

Note: [FL (X,Y,Z)]°a is the parameter identified as F"Ax (XY,Z) in DPC-NE-201 IPA.

FQ'(X,Y,Z)

• Mc(X,Y,Z) 2.6.6 [F*Q(X,Y,Z)]RPS = UMT

• MT

• TILT where:

[F}Q(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.

[FI$(X,Y,Z)]RPs includes allowances for calculation and measurement uncertainties.

FýQ(X,Y,Z) = Design power distributions for FQ. FQQ(X,Y,Z) is provided in Table 4, Appendix A for normal operating conditions and in Table 5, Appendix A for power escalation testing during initial startup operation.

MCEI-0400-47 Page 15 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report MC(X,Y,Z) = Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. Mc(X,Y,Z) calculations parallel the MQ(X,YZ) calculations described in DPC-NE 201 IPA, except that the LOCA limit is replaced with the CFM limit. MC(X,Y,Z) is provided in Table 6, Appendix A for normal operating conditions and in Table 7, Appendix A 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)

NOTE: [ FL (X,Y,Z)]RPs is the parameter identified as FmAx (X,Y,Z) in DPC-NE 201 IPA, except that MQ(X,Y,Z) is replaced by Mc(X,Y,Z).

2.6.7 KSLOPE = 0.0725 where:

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

2.6.8 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 16 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Mk-BW and Westinghouse RFA Fuel 1.2 (12.0, 1.0) 1.0 (0.0, 1.00) 0.8 0.6 0.4 0.2 0.0 I I I I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

MCEI-0400-47 Page 17 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAI(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) FAH(X,Y,Z)

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

0 2.00 2.00 4 2.97 2.00 12 2.72 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 2.00 535 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle burnups. All cycle burnups outside of the range of the table shall use a 2% penalty factor for both FQ(X,Y,Z) and FAH(X,Y) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.

MCEI-0400-47 Page 18 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)

The FAI1 steady-state limits referred to in Technical Specification 3.2.2 is defined by the following relationship.

2.7.1 [FaH(X,Y)]c° = MARP (X,Y)

• 1.0 + R (1.0- P) where:

[Fm ( Y)]Lco is defined as the steady-state, maximum allowed radial peak.

[FAL. (X, Y)]Lo° includes allowances for calculation-measurement uncertainty.

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

= Thermal Power Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, FM (X,Y), exceeds the limit.

RRH = 3.34 (0.0 < P < 1.0)

The following parameters are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.

SURV F*H(X,Y)x MaH(X, Y) 2.7.2 [ FaL, (X, Y)]I FA

=UV X )MA XY UMR x TILT where:

[FALH (X,Y)] URv Cycle dependent maximum allowable design peaking factor that ensures that the F ,1 (X,Y) limit will be preserved for includes operation within the LCO limits. [ F (,ý Y)]SURV allowances for calculation-measurement uncertainty.

MCEI-0400-47 Page 19 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report (X,Y) = Design radial power distribution for FH. F* (X,Y) is provided in Table 8, Appendix A for normal operation and in Table 9, Appendix A for power escalation testing during initial startup operation.

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

MAJH(X,Y) is provided in Table 8, Appendix A for normal operation and in Table 9, Appendix A for power escalation testing during initial startup operation.

UMR = Uncertainty value for measured radial peaks, (UMR= 1.04).

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).

NOTE: [FýH(XY)]sURv is the parameter identified as FAH(XY)MAX in DPC-NE-201 IPA.

2.7.3 RRH = 3.34 where:

RRH = Thermal power reduction required to compensate for each 1% that the measured radial peak, F* (X,Y) exceeds its limit.

2.7.4 TRH = 0.04 where:

TRH = Reduction in the OTAT K1 setpoint required to compensate for each 1%

that the measured radial peak, FH (X,Y) exceeds its limit.

2.7.5 FAF, (X,Y) penalty factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.

2.8 Axial Flux Difference - AFD (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 4.

MCEI-0400-47 Page 20 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

(Applicable to Both MkBW and RFA Fuel)

Core Axial Peak ----- >

Ht. (ft) 1.05 [r.10 1.20 1.30 1.40 1.50 1.60 0.12 1.687 1.716 1.782 1.838 1.888 1.933 1.863 1.20 1.684 1.715 1.776 1.830 1.878 1.896 1.839 2.40 1.683 1.711 1.767 1.819 1.858 1.845 1.789 3.60 1.681 1.707 1.758 1.802 1.810 1.795 1.742 4.80 1.678 1.701 1.747 1.785 1.759 1.744 1.692 6.00 1.674 1.695 1.733 1.748 1.703 1.692 1.643 7.20 1.669 1.687 1.716 1.696 1.649 1.633 1.587 8.40 1.664 1.675 1.685 1.643 1.595 1.579 1.534 9.60 1.656 1.660 1.635 1.585 1.543 1.529 1.487 10.80 1.645 1.633 1.587 1.535 1.488 1.476 1.434 12.00 1.620 1.592 1.538 1.490 1.442 1.432 1.394 Core Axial Peak ----- >

Ht. (ft) 1.70 1.80 1.90 2.10 3.00 3.25 0.12 1.807 1.723 1.645 1.543 1.218 1.153 1.20 1.815 1.740 1.664 1.548 1.188 1.123 2.40 1.772 1.715 1.659 1.561 1.170 1.108 3.60 1.721 1.667 1.617 1.555 1.213 1.141 4.80 1.674 1.624 1.574 1.510 1.227 1.182 6.00 1.627 1.579 1.533 1.465 1.197 1.148 7.20 1.571 1.527 1.488 1.424 1.165 1.116 8.40 1.522 1.479 1.440 1.373 1.134 1.089 9.60 1.476 1.436 1.399 1.337 1.110 1.065 10.80 1.427 1.390 1.355 1.294 1.075 1.033 12.00 1.389 1.356 1.327 1.273 1.061 1.017

MCEI-0400-47 Page 21 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report Figure 4 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 3

4) 0 I

4) 4)

0 4)

U I

4)

-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/2/A16100/22 Unit 2 Data Book of more details.

MCEI-0400-47 Page 22 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Value 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 T1 > 8 sec.

for AT ,.- AC Time constant utilized in the lag compensator for AT t3 < 2.0 sec.

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

for Tav.g "15< 4 sec.

Time constant utilized in the measured Tavg lag "E6 < 2.0 sec.

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

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

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

MCEI-0400-47 Page 23 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value K4 < 1.086359 Overpower AT reactor trip setpoint Overpower AT reactor trip heatup setpoint K6 = 0.001 179/°F penalty coefficient 1,1 Ž 8 sec.

Time constants utilized in the lead-lag compensator for AT r2 -<3 sec.

T35 <2.0 sec.

Time constant utilized in the lag compensator for AT Time constant utilized in the measured Tavg 'C6 < 2.0 sec.

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

controller for Tavg

= 35.0 %AI f2(AI) "positive" breakpoint

= -35.0 %AI f2(AI) "negative" breakpoint

= 7.0 %ATd %AI f2(AI) "positive" slope

= 7.0 %ATd %AI f2 (AI) "negative" slope

MCEI-0400-47 Page 24 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.10 Accumulators (TS 3.5.1) 2.10.1 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 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 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 25 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.12 Spent Fuel Pool Boron Concentration (TS 3.7.14) 2.12.1 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 2.13 Refueling Operations - Boron Concentration (TS 3.9.1) 2.13.1 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 26 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.14 Borated Water Source - Shutdown (SLC 16.9.14) 2.14.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during 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-0400-47 Page 27 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report 2.15 Borated Water Source - Operating (SLC 16.9.11) 2.15.1 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:

Parameter Limit Boric Acid Tank minimum contained borated 22,049 gallons water volume 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 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-0400-47 Page 28 of 29 Revision 21 McGuire 2 Cycle 15 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 Concentration BAT Level 35.0-(ppm) (Yievel) 0 < 300 37.0 300<500 33.0 30.0o 5_ <700 28.0 700 < 1000 23.0 T1000<13-00 1-3.-6

..... . .. 8.7 (D>1300

> 25.0 -....

-J

- 20.0

- rAcceptable Operation I< 15.0 10.0 5 Unacceptable Operation 5.0

' - V 0.0 0 200 400 60 800 1000 12W 1400 1600 1800 2"0) 220X) 2400 2600 2800 RCS Boron Concentration (ppmb)

MCEI-0400-47 Page 29 of 29 Revision 21 McGuire 2 Cycle 15 Core Operating Limits Report NOTE: Data contained in the Appendix to this document was generated in the McGuire 2 Cycle 15 Maneuvering Analysis calculation file, MCC-1553.05-00-0349. 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.