ML023030460

Core Operating Limits Report (COLR)

ML023030460
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/21/2002
From:	Jamil D Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-46 Rev 24
Download: ML023030460 (31)

Text

Duke Power SDuke McGuire Nuclear Station IAPower, 12700 Hagers Ferry Road Huntersville, NC 28078-9340 (704) 875-4000 (704) 875-5333 OFFICE D.M. Jamil (704) 875-4809 FAX Vice President,McGuire October 21, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station, Docket No.50-369, 50-370 Unit 1 Cycle 16 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed the McGuire Unit 1 Core Operating Limits Report (COLR). Revision 24 contains limits specific to the McGuire Unit I Cycle 16 core.

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

D. M. Jamil Attachment j2(ool

U. S. Nuclear Regulatory Commission October 21, 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 11 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 October 21, 2002 Page 3 bxc: RGC File ECO50-ELL P. M. Abraham Master File

MCEI-0400-46 Page 1 of 29 Revision 24 McGuire Unit 1 Cycle 16 Core Operating Limits Report Revision 24 August 2002 Calculation Number: MCC-1553.05-00-0371 Duke Power Company Date Prepared By:

Checked By: e. 26-002>

Checked By:

(Sections: 2.9 - 2.15)

Approved By:

7119 rn- A&_-

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 29 Revision 24 McGuiie 1 Cycle 16 Core Operating Limits Report I

IMPLEMENTATION INSTRUCTIONS FOR REVISION 24 Revision 24 to the McGuire Unit 1 COLR contains limits specific to the McGuire Unit 1 Cycle 16 core and may become effective any time after no-mode is reached between Cycles 15 and 16. This revision must become effective prior to entering Mode 6 that starts Cycle 16.

MCEI-0400-46 Page 3 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Pages COLR Revisions 0-3 Superseded N/A MIC09 Revisions 4-8 Superseded N/A MiClO Revisions 9-11 Superseded N/A MICll Revisions 12-15 Superseded N/A M1CI2 Revisions 16-17 Superseded N/A M1CI3 Revision 18-20 Superseded N/A MIC14 Revision 21-23 Superseded N/A MICI5 Revision 24 August 30, 2002 1-29 MIC16 (Original Issue)

MCEI-0400-46 Page 4 of 29 Revision 24 McGuire 1Cycle 16 Core Operating Limits Report INSERTION SHEET FOR REVISION 24 Remove pages Insert Rev. 24 pages Pages 1 - 26a Pages 1 - 29

MCEI-0400-46 Page 6 of 29 Revision 24 McGuire I Cycle 16 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," (IWProprietary).

Revision 0 Report Date: July 1985 Not Used for MIC16

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 MICI6

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 I SER Date: January 22. 1991 Revision 2 SER Dates: August 22. 1996 and November 26. 1996.

ReN ision 3 SER Date: June 15. 1994.

Not Used for MICI6 6 DPC-NE-3000PA. "'Thermal-t-lvdraulic Transient Analysis Mlethodology." (DPC Propi ietar, )

lRc' ision 2 SER Date. October 14. 1998

MCEI-0400-46 Page 7 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report I I 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

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-O 1," (DPC Proprietary).

Revision I SER Date: February 20, 1997

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

Revision I SER Date: November 7, 1996 1I. 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. I)PC-NF-2010A. "Duke PIower Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

Revision 0 Report Date Jutie 1985

"MCEI-0400-46 Page 8 of 29 Revision 24 McGuire 1 Cycle 16 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 0 Report Date: March 1990 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 ken- 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 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.

2.2.2 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 I and 2.

2.2.4 For TS 3.1.5, SDM shall be> 13.% AK/K in mode 1 and mode 2 with an)y control bank not fully inserted.

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

2.2.6 For TS 3.1.8. SDM shall be > 1.3% AK/K in mode 2 during physics testinio

MCEI-0400-46 Page 9 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report 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/0 F lower MTC limit.

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.

2.3.3 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/°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 %%ithinthe insertion. sequence. and oxerlap limits shown in

[ligure 2. Specific control bank %ithdrawal and overlap limits as a function of the full% v, ithdra\x n position are sho, n in Table 1.

I MCEI-0400-46 Page 10 of 29 Revision 24 McGuire I Cycle 16 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation 0.8 0.7 0.6 0.5 0,

E 0.4 Acceptable Operation 1_

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

MCEI-0400-46 Page I1 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 23 1) 231 220 200 R. 180 160

• - 140

= 120

r 100 80 60

~40 20 f .A Ufll. . . . .tL, I F(300% 0)1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

0 1 1 1 . -I 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 x\ ithdrawal limits.

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

MCEI-0400-46 Page 12 of 29 Revision 24 McGuire 1 Cycle 16 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 0 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 Full, 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 23 ! Stop 115 0 0 230 116 0 Start 0 231 116 0 Start 0 230 230 Stop 114 0 231 231 Stop 115 0 230 230 116 0 Start 231 231 116 0 Start 230 230 230 Stop 114 23) 231 231 Stop I 15

MCEI-0400-46 Page 13 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report 2.6 HeatFiux Hot Channel Factor - FQ(X,YZ) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:

F RrP *K(Z)/P for P > 0.5 F Rry *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)

Note: The measured Fo(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 2.6.5 and 2.6.6.

2.6.2 F 77' = 2.50 x K(BU)

Q 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height. The K(Z) function for MkBW and Westinghouse RFA fuel is provided in Figure 3.

2.6.4 K(BU) is the normalized FQ(X,YZ) as a function of burmup. K(BU) for both MkBW and Wesinghouse 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 2.6.5 [F F(X.Y,Z)

• MQ(X,YZ)

Q UMT

• MT

• TILT where:

r , (X.Y,Z)]OP = Cycle dependent maximum allowable design peaking factor that ensures that the Fo(X.Y.Z) LOCA limit will be preserved for operation within the LCO limits. [ FJ (X.Y.Z)]OP includes allowances for calculation and measurement uncertainties FI'(X.Y.Z) = Design po%%er distribution for I:. F7 (X.Y.Z) is provided in Table 4. Appendix A. for normal operating conditions and in

MCEI-0400-46 Page 14 of 29 Revision 24 McGuire 1 Cycle 16 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: [ F' (X,Y,Z)] is the parameter identified as F""7' (X,Y,Z) in DPC-NE-201 IPA.

D 2.6.6 L )RPS FQ(X,Y,Z)

• Mc(X,Y,Z) 2.6.6 [FQ(X,Y,Z)] UMT

• MT

• 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.

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

"FQ(X.Y,Z) = Design power distributions for FQ F8(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-0400-6 Page 15 of 29 Revision 24 McGuiir 1 Cycle 16 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,Y,Z) 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 for an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035)

Note: [F, (X,Y,Z)] is the parameter identified as F."' 4 (X.YZ) in DPC-NE 2011 PA, 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 K! value from OTAT trip setpoint required to RPS compensate for each I% that F." (X.Y.Z) exceeds [ FC (X,YZ)] .

2.6.8 Fo(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 16 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report Figure 3 K(Z), Normalized FQ(X,YZ) as a Function of Core Height for MkBW and Westinghouse RFA Fuel 1.2 (0.0, 1.00) (12.0, 1.0) 1.0 0.8 S0.6 0.4 0.2 0.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)

MCEI-0400-46 Page 17 of 29 Revision 24 McGuire 1 Cycle 16 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,&I(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 2.03 200 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 2.00 520 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 Fo(X.Y.Z) and FAHK(XY) for compliance with the Technical Specification Surveillances 3.2.1.2. 3.2.1.3 and 3.2.2 2.

MCEI-0400-46 Page 18 of 29 Revision 24 McGuir-e i Cycle 16 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)

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

2.7.1 [Fm(X,Y)]Lco= MARP (X,Y)* [.0+ * (1.0-P) where:

[FkH (X, y)]LcO is defined as the steady-state, maximum allowed radial peak.

[F6H (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, FA1' (X,Y), exceeds the limit. RRH also is used to scale the MARP limits as a function of power per the [F,, (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.

SURV F*I(XY)x M\!r(X,Y) 2.7.2 [ F*, (X.Y)] = M TILT UMR x TILT

%N here:

I F', (X.Y)I Q. cle dependent maxinmun allox%able design peaking factor that ensures that the F*,1(X.Y) limit will be preserved for operationixithin the LCO limits. [ l (X.Y)] inclS allowances for calculation-measurement uncertainty.

MCEI-0400-46 Page 19 of 29 Revision 24 McGuire I Cycle 16 Core Operating Limits Report D D FýH (X,Y) = Design radial power distribution for F... Ftj (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.

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

MAH(X,Y) is provided in 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 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: [F~1 (X,Y)]SURV is the parameter identified as FJ(X,Y)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, ,1 (XY) exceeds its limit. (0 < P < 1.0) 2.7.4 TRH = 0.04 where:

TRH = Reduction in OTAT KI setpoint required to compensate for each I% that thc measured radial peak. F",, (X.Y) exceeds its limit.

2.7.5 F[\K(X.Y) penalty factors for Technical Specification Surveillance 3.2.2.2 arc provided in Table 2.

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

MCEI-0400-46 Page 20 of 29 Revision 24 McGuire 1 Cycle 16 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 1.10 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-0400-46 Page 21 of 29 Revision 24 McGu~ie 1 Cycle 16 Core Operating Limits Report Figure 4 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits

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

Unacceptable Opei 90 Unacceptable Operation 80-70 Acceptable Operation E

60 -

50

(-36, 50) (+21, 50)

C C 40 -

30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta 1)

NOTE: Compliance %,ithTechnical Specification 3.2.1 may require more restrictive AFD limits Refer to OP/1/A/6100/22 Unit I Data Book of more details.

MCEI-0400-46 Page 22 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limfifts 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 r-- <1 cf r-Time constant utilized in the lag compensator for AT -t3 < 2 sec.

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

for Tat -C5 < 4 sec.

Time constant utilized in the measured Ta,,g lag "t6< 2 sec.

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

fl (AI) "positive" slope = 1.769 %AToI %Al fl (AI) "negative" slope = NIA*

Tile f I(AI) "negative" breakpoint and the fl (AI) "negative" slope are not applicable since the fl (AI) function is not required belox\ the f I(AI) "positive" breakpoint of 19.0% Al.

MCEI-0400-46 Page 23 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 < 1.0864 Overpower AT reactor trip heatup setpoint K6 = 0.001179/1F penalty coefficient Time constants utilized in the lead-lag -r1 > 8 sec.

compensator for AT r2 < 3 sec.

Time constant utilized in the lag T3 < 2 sec.

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

lag compensator Time constant utilized in the rate-lag C7 > 5 sec.

controller for Ta,,,

f2 (AI) "positive" breakpoint = 35.0 %AI fj,(AI) "negative" breakpoint = -35.0 %AI f,(AI) "positive" slope = 7.0 %AT0/ %AI f2 (AI) "negative" slope = 7.0 %ATo/ %AI

MCEI-0400-46 Page 24 of 29 Revision 24 McGuiri 1 Cycle 16 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-0400-46 Page 25 of 29 Revision 24 McGuire 1 Cycle 16 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-0400-46 Page 26 of 29 Revision 24 McGuire 1 Cycle 16 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 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 27 of 29 Revision 24 McGuire I Cycle 16 Core Operating Limits Report 2.15 Borated Water Sourie - 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 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 28 of 29 Revision 24 McGuire 1 Cycle 16 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 16.9.11 400-RCS Boron 35 0 Concentration BAT Level (ppm) (%level) 0 < 300 37.0

-0 <-5.00- .-33.0 300 500 < 700 28-0 700°<- 1000 . 23.b 1000 < 1300- 13.6

"( 250 >1300 87

-j

- 200 Acceptable Operation I

< 150 100 Unacceptable Operation 50 00 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 RCS Boron Concentration (ppmb)

"MCEI-0400-46 Page 29 of 29 Revision 24 McGuire 1 Cycle 16 Core Operating Limits Report NOTE: Data contained in the Appendix to this document was generated in the McGuire 1 Cycle 16 Maneuvering Analysis calculation file, MCC-1553.05-00-0353. 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.