ML032880779

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Cycle 16, Revision 23 to Core Operating Limits Report
ML032880779
Person / Time
Site: Mcguire
Issue date: 10/02/2003
From: Gordon Peterson
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
MCEI-0400-47, Rev 23
Download: ML032880779 (33)
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Text

Duke GARY R. PETERSON rWPowere Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MGOI VP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy. corn October 2, 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

McGuire Nuclear Station, Docket No.50-370 Unit 2, Cycle 16 Core Operating Limits Report (COLR)

Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed Revision 23 to the McGuire Unit 2, Cycle 16 Core Operating Limits Report (COLR).

Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Compliance at

_74 7

Gary. Peerson Attachment AC0 o

www. duke-energy. corn

U. S. Nuclear Regulatory Cmmission October 2, 2003 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 IR Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30323 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station

MCEI-040047 Page 1 of 31 Revision 23 McGuire Unit 2 Cycle 16 Core Operating Limits Report Revision 23 September 2003 Calculation Number: MCC-1553.05-00-0391 Duke Power Company Date Prepared By:

Checked By:

Checked By:

Approved By:

'D~J'

,:30VI

?A t1-1/11' 7/3/03 (Sections 2.9-- 2.15)

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

MCEI-040047 Page 2 of 3l Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By.

P. =.

Date:.

q 11/c I (Sponso)

CATAWBA MCE (Mechanical & Civil)

RES (Electrical Only)

RES (Reactor)

MOD Other (

IInspection Waived El El..

0:El Ispected 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 0-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 Other(

)

Inspection Waived IN' 0LI Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

Inspected By/Date:

MCEI-040047 Page 3 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONSJFOR REVISION 23 Revision 23 to the McGuire Unit 2 COLR contains limits specific to the McGuire Unit 2 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-0400-47 Page 4 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Revision Revisions 0-2 Revisions 3-6 Revisions 7-12 Revision 13-15 Revision 16-17 Revision 18-20 Revision 21-22 Revision 23 REVISION LOG.,

Issuance Date Effective Pases Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A Superseded N/A September 3, 2003 1-31 COLR M2C09 M2C1O M2C1l M2C12 M2C13 M2C14 M2C15 M2C16 - Orig. Issue

MCEI-040047 Page 5 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report INSERTION SHEET FOR REYISION 23 Remove pages Pages I - 29 Appendix A*, 1-306 Insert Rev. 23 pages Pages 1 - 31 Appendix A*, 1-344

  • Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is only included in the COLR copy sent to the NRC.

MCEI-040047 Page 6 of 31 Revision 23 McGuire 2 Cycle 16 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.

TS Number 1.1 3.1.1 3.1.3 3.1.4 3.1.5 3.1.5 Technical Specifications Requirements for Operational Mode 6 Shutdown Margin Moderator Tempdrature Coefficient Shutdown Margin Shutdown Bank Insertion Limit Shutdown Bank Insertion Limit 3.1.6 Control Bank Insertion Limit 3.1.6 Control Bank Insertion Limnit 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 COLR Parameter Mode 6 Definition 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 F&H and AFD AFD OTAT and OPAT Constants Max and Min Boron Conc.

Max and Min Boron Conc.

Min Boron Concentration Min Boron Concentration COLR Section 2.1 2.2 2.3 2.2 2.2 2.4 2.2 2.5 2.2 2.6 2.7 2.8 2.9 2.10 2.11 2.12 2.13 El Pape 9

9 10 9

9 10 9

10 9

15 20 21 24 26 26 27 27 3.5.1 3.5.4 3.7.14 3.9.1 Accumulators Refueling Water Storage Tank Spent Fuel Pool Boron Concentration Reffieling Operations - Boron Concentration The Selected Licensee Commitments that reference this report are listed below:

SLC Number Selected Licensing Commitment COLR Parameter COLR Section 2.14 16.9.14 16.9.11 Borated Water Source - Shutdown Borated Water Volume and Conc. for BAT/RWST Borated Water Source - Operating Borated Water Volume and Conc. for BATIRWST EI Page 28 29 2.15

MCEI-0400-47 Page 7 of 31 Revision 23 McGuire 2 CQcle 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 are as follows.

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

Revision 0 Report Date: July 1985 Not Used for M2C16

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

Revision 0 Report Date: August 1985

3. WCAP-10266-P-A, "he 1981 Version Of Westinghouse Evaluation Model Using BASH Code",

(E Proprietary).

Revision 2 Report Date: March 1987 Not Used for M2C16

4. WCAP-12945-P-A, Volume I and Volumes 2-5, "Code Qualification Document for Best-Estimate Lois 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&4W 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-M2C16

6. DPC-NE-3000PA, "T'hermal-Hydraulic Transient Analysis Methodology," (DPC Proprietary).

Revision 2 SER Date: October 14, 1998

MCEI-0400-47 Page 8 of 31 Revision 23 McGuire 2 Cycle 16 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 15, 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-01,"'(DPC Proprietary).

Revision I SERDate: February20,1997

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

Revision I 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 2 SER Date: December I,'2002

13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-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-040047 Page 9 of 31 Revision 23 McGuire 2 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 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 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 (T'S 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 shaH be > 1.3% AK/K in modes 1 and 2.

2.2.A 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 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 Testing.

MCEI-040047 Page 10 of 31 Revision 23 McGuire 2 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/0F.

The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AKfK/0F 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 -3.65E-04 AKIKIJF.

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 4.125E-04 AK/KI0F.

Where: BOC = Beginning of Cycle (Bumup corresponding to the most positive MTC)

EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (I'S 3.1.5) 2A.1 Each shutdown bank shall be withdrawn to at least 222 steps. Shutdown banks are withdrawn in sequence and with no overlap.

2.5 Control Bank Insertion Limits (ES 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-040047 Page llof31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 -

10 U

$4.a..

a) 0 C..

Unacceptable Operation 0.8 -

0.7

.4 "tr C

4 4=1.4 0.6 -

0.5 -

0.4 -

0.3 -

Acceptable Operation I

I I

I 0.2 -

0.1 -

-0.0 II I

I I

I I

I I

I I

I I

4 0

10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance witf 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 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn 231 220 200 c

K 180 la-

  • 0 160 ffi 141) 9f 120

.2 0 100 t80

3. 60 9

40 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/21A/6100/22 Unit 2 Data Book for details.

MCEI-0400-47 Page 13 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Table I RCCA Withdrawal Steps an4tSequence RCCAs Fully Withdrawn at 222 SWI Control Control Control Control Bank A Bank B Bank C Bank D OStart 0

0 0

116 OStart 0

0 222 Stop 106 0:

0 222 116 O Start 0

222 222 Stop 106 0

222 222 116 OStart 222 222 222 Stop

106 RCCAs Fully Withdrawn at 223 SWD Control Control Control Control Bank A Bank B Bank C BankD 0 Start 0

0 0

116 0 Start 0

0 223 Stop 107 0

0 223 116 0 Start 0

223 223 Stop 107 0

.223 223 116 OStart 223 223 223 Stop 107 RCCAs Fully Withdrawn at 225 SWD Control Control Control Control Bank A Bank B Bank C Bank D OStart 0

0 0

116 OStart 0

0 225 Stop 109 0

.0 225 116 OStart 0

225 225 Stop 109 0

225 225 116 0 Start 225 225 225 Stop 109 RCCAs Fully Withdrawn at 224 SWD Coutrol Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 OStart 0

0 224 Stop 108 0

0 224 116 0 Start 0

224 224 Stop 108 0

224 224 116 OStart 224 224 224 Stop, 108 RCCAs Fully Withdrawn at 226 SWD Control Control Conttol 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 OStart 0

226 226 Stop 110 0

226 226 116 0 Start 226 226 226Stop 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 IIl 0

0 227 116 0 Start 0

227 227 Stop 111 0

227 227 116 0 Start 227 227 227 Stop 111

MCEI-040047 Page 14 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Table 1 Continued, RCCA Withdrawal Steps and-Sequence RCCAs Fully Withdrawn at 228 SWD Control Control Control Control Bank A Bank B Bank C Bank D OStart 0

0 0

116 0Start 0'

0 228 Stop 112 0

0 228 116 OStart 0

228 228 Stop 112 0

228 228 116 0 Start 228 228 228 Stop.

12 RCCAs Fully Withdrawn at 229 SWD Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0

0 0

116 OStart 0

0 229Stop 113 0

0 229 116 OStart 0

229 229 Stop 113 0

229 229 116 -

OStart 229 229 229 Stop 113 RCCAs Fully Withdrikwn at 230 SWD Control Control Control Control Bank A Bank B Bank C Bank D OStart 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 RCCAs Fully Withdrawn at 231 SWD Control Control Control Control Bank A Bank B Bank C Bank D OStart 0

0 0

116 OStart 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

MCEI-0400-47 Page 15 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor - FQ(XYZ) (TS ).2.1) 2.6.1 FQ(XY,Z) steady-state limits are defined by the following relationships:

F RTP *K(Z)/P for P > 0.5 F

E*K(Z)/0.5 for P < 0.5

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

Note: The measured FQ(XYZ) 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(XYZ) 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(XYIZ) as a function of bumup. K(BU) for both MkBW and Westinghouse RFA fuel is 1.0 for all burnups.

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

2.6.5 X

O FXZY0Z)

[Q(X'YZ )3 UMT

  • TILT where:

[FQ(XYZ)]0P = Cycle dependent maximum allowable design peaking factor that ensures that the FQ(XY,Z) LOCA limit will be-preserved for operation within the LCO limits. [ F (X,YZ)]OP includes allowances for calculation and measurement uncertainties.

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

MCEI-0400-47 Page 16 of 31 Revision 23 McGuire 2 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 XYZ to the LOCA limit in the transient power distribution. MQ(XYZ) 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) 2.6.6 [FL(XYZ)]

=

FQ(XYZ)

  • MC(XYZ)

UMT

  • TILT where:

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

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

Design power distributions for FQ. FQ(X,YZ) 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.

Mc(XYZ) =

Margin remaining to the CFM limit in core location X,YZ from the transient power distribution. MC(XY,Z) calculations parallel the MQ(XYZ) 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)

MCEI-0400-47 Page 17of31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report MT = Engineering Hot Channe4actor (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) 2.6.7 KSLOPE = 0.07.25 where:

KSLOPE is the adjustment to the K1 value from the OTAT trip setpoint required to compensate for each 1% that F? (XYZ) exceeds [ F (XYZ)]

2.6.8 FQ(XYZ) 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 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Figure 3.

K(Z), Normalized FQ(XYZ) as a Function of Core Height for Mk-BW and Westinghouse RFA Fuel 1.2 1.0 0.8 0.6 OA 0.2 0.0 (0.0, 1.00)

(12.0, 1.0)

~

~ ~

I I

I I

0.0 2.0 4.0 6.0 Core Height (ft)

.8.0

.10.0 12.0

MCEI-0400-47 Page 19of31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Table 2 FQ(XY,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 FQ(X,YZ)

FH(XMYZ)

(EFPD)

Penalty Factor (%)

Penalty Factor (%)

0 2.00 2.00 4

2.00 2.00 12 2.00 2.00 25 2.26 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 2.00 510 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(XY,Z) and FMH(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 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(XY) (TS 3.2.2)

The F&H steady-state limits referred to in TechnicA Specification 3.2.2 is defined by the following relationship.

2.7.1

[FL (X, Y)]Ic= MARP (X,Y) [1.0 +

(1.0

]P) where:

[FH (X, Y)]>C° is defined as the steady-state, maximum allowed radial peak.

[FL (X, Y)]Ico 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, F,:, (XY), exceeds its limit. RRH also is used to scale the MAARP limits as a function of power per the [F,(X,Y)]'

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.

2.7.2

[FL (XY)]suRv F(X,Y)xM,(X,Y)

UMR x TILT

-where:

[ FIH (X,Y)]

= Cycle dependent maximum allowable design peaking factor that ensures that the FH(XY) limit will be preserved for operation within the LCO limits.

F6LH (XY)]

includes allowances for calculation-measurement uncertainty.

MCEI-040047 Page 21 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report F^H (X,Y) = Design radial power distribution for F,. FH (XY) 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(XY) 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 MH(XY).

TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02, (TILT = 1.035).

2.7.3 RRH = 3.34 where:

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

2.7A4 TRH = 0.04.

where:

TRH = -Redurtion in the OTAT Kj setpoint required to compensate for each 1%

that the measured radial peak, F^m (X,Y) exceeds its limit.

2.7.5 F" (XY) penalty factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.

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

MCEI-0400-47 Page 22 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)

RFA MARPS Core Axial Peak->

Ht (ft) 1.05 1.1 1.2 13 1A 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 IA31 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 1316 1.277 8.4 1.823 1.829 1.847 1.857 1.816 1.795 1.739 1.722 1.673 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 Mk-BW MARPS Core Axial Peak-->

Ht. (ft.)

1.05 1.1 12 13 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25

  • .12 1.687 1.716 1.782 1.838 1.888 1.933 1.863 1.807 1.723 1.645 1.543 1.218 1.153 1.2 1.684 1.715 1.776 1.830 1.878 1.896 1.839 1.815 1.740 1.664 1.548. 1.188 1.123 2.4 1.683 1.711 1.767 1.819 1.858 1.845 1.789 1.772 1.715 1.659 1.561 1.170 1.108 3.6 1.681 1.707 1.758 1.802 1.810 1.795 1.742 1.721 1.667 1.617 1.555 1.213 1.141 4.8 1.678 1.701 1.747 1.785 1.759 1.744 1.692' 1.674 1.624 1.574 1.510 1.227 1.182 6.0 1.674 1.695 1.733' 1.748 1.703 1.692 1.643 1.627 1.579 1.533 1.465 1.197 1.148 7.2 1.669 1.687 1.716 '1.696 1.649 1.633 1.587 1.571 1.527 1.488 1.424 1.165 1.116 8.4 1.664 1.675 1.685 1.643 1.595 1.579 1.534 1.522 1.479 1.440 1.373 1.134 1.089 9.6 1.656 1.660 1.635 1.585 1.543 1.529 1.487 IA76 1.436 1.399 1.337 1.110 1.065 10.8 1.645 1.633 1.587 1.535 1.488 1.476 1.434 1.427 1.390 1.355 1.294 1.075 1.033 12.0 1.620 1.592 1.538 IA90 1.442 1.432 1.394 1.389 1.356 1.327 1.273.

1.061 1.017

MCEI-0400-47 Page 23 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Figure 4 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 8..

0 la S

E-4 p4

-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/A/6100122 Unit 2 Data Book of more details.

MCEI-0400-47 Page 24 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (ITS 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 = 0.0334PF penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator

-l > 8 sec.

for AT Time constant utilized in the lag compensator for AT Time constants utilized in the lead-lag compensator for T,,

Time constant utilized in the measured T., lag compensator fl (Al) "positive" breakpoint f1(AD "negative" breakpoint fl(Al) "positive" slope fl(AI) "negative" slope

I j

r 3 < 2.0 sec.

T4 >28 sec.

T5 < 4 sec.

-r6 <2.0 sec.

= 19.0 %AI

= NEAR

= 1.769 YoATOW %Al

= N/A The fl(Al) "negative" breakpoint and the fl(Al) "negative" slope are not applicable since the fj(Al) function is not required below the fl(AD) "positive" breakpoint of 19.0% Al.

MCEI-0400-47 Page 25 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report 2.9.2 Overpower AT Setpoint Parameter Values Parameter Overpower AT reactor trip setpoint 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 Tayg lag compensator Time constant utilized in the rate-lag controller for Tag f2(AI) "positive" breakpoint f2(AJ) "negative" breakpoint f2(AI) "positive" slope f2(AI) "negative" slope Value K4 < 1.0864 K 6 = 0.001 179/OF cl > 8 sec.

T2 < 3 sec.

r3 < 2.0 sec.

I r6 < 2.0 sec.

7 > 5 sec.

= 35.0 %AI

= -35.0 NISI

= 7.0 %ATO/ %AI

= 7.0 %ATc/ %AI

MCEI-0400-47 Page 26 of 31 Revision 23 McGuire 2 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 Cold Leg Accumulator minimum boron concentration.

Cold Leg Accumulator maximum boron concentration.

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

Refueling Water Storage Tank maximum boron concentration.

Limit 2,675 ppm 2,875 ppm

MCEI-0400-47 Page 27 of 31 Revision 23 McGuire 2 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.

assemblies are stored in the spent fuel pool.

Applicable when fuel 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 System, the refueling canal, and the refueling cavity.

2,675 ppm

MCEI-0400-47 Page 28 of 31 Revision 23 McGuire 2 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 OF 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 > 430 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 volhme 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-040047 Page 29 of 3l Revision 23 McGuire 2 Cycle 16 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 with all RCS cold leg temperature > 300 'F.

Parameter Limit Boric Acid Tank minimum contained borated water volume 22,049 gallons 38.0% Level l Note: When cycle burnup is > 430 EFPD, Figure 6 may be used to determine the required BAT minimum level.

1 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-040047 Page 30 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus RCS Boron Concentration' (Valid When Cycle Burnup is > 430 EFPD)

This figure Includes, additional volumes listed in SLC 16.9.14 and 16.9.11 40.0 35.0 30.0 25.0 b4

=

20.0

¢10 P4 15.0O i -

j i.

RCS Boron Concentration BAT Level (ppm)

(%level) 0<300

-37.0 300 < S0 33.0 500:< 700 28.0 700 < 1000 23.0 1000< 1300 13.6 _

Acceptable Operation Unacceptable Opemaonl I-I 0.I I

io.oI --

I j

5o A A 0

200 400 600 800 1000 1200 1400 1600 1800 2000 20 2400 260.

2800 RCS Boron Concentration (ppmb)

MCEI-040047 Page 31 of 31 Revision 23 McGuire 2 Cycle 16 Core Operating Limits Report NOTE: Data contained in the Appendix to this document was generated in the McGuire 2 Cycle 16 Maneuvering Analysis calculation file, MCC-1553.05-00-0378. The Plant Nuclear Engineering Section will control this information via computer file(s) and should be contacted if there is aneed to access this information.

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