ML12285A230
| ML12285A230 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 10/04/2012 |
| From: | Capps S Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| MCEI-0400-275 MCC-1553.05-00-0564, Revision 0 | |
| Download: ML12285A230 (35) | |
Text
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Duke 4Energy.
STEVEN D. CAPPS Vice President McGuire Nuclear Station Duke Energy MG01 VP / 12700 Hagers Ferry Rd.
Huntersviyle, NC 28078 980-875-4805 980-875-4809 fax Steven. Capps@duke-energy. corn October 4, 2012 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke)
McGuire Nuclear Station Docket No. 50-370 Unit 2, Cycle 22, Revision 0 Core Operating Limits Report Pursuant to McGuire Technical Specification (TS) 5.6.5.d, please find enclosed the McGuire Unit 2 Cycle 22, Revision 0, Core Operating Limits Report (COLR).
Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Affairs at (980) 875-4306.
Steven D. Capps Attachment IA W L(.
www. duke-energy. com
U. S. Nuclear Regulatory Commission October 4, 2012 Page 2 cc:
Mr. Jon H. Thompson, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Victor M. McCree Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. John Zeiler Senior Resident Inspector McGuire Nuclear Station
U.S. Nuclear Regulatory Commission October 4, 2012 Page 3 bxc:
RGC File ECO50-ELL Master File
MCEI-0400-275 Page 1 Revision 0 McGuire Unit 2 Cycle 22 Core Operating Limits Report Revision 0 July 2012 Calculation Number: MCC-1553.05-00-0564, Revision 0 Duke Energy Carolinas, LLC Date Prepared By:
Checked By:
Checked By:
Approved By:
(Sections 2.1 and 2.* - 2.17)
/9e X -C'.I
-7/2&
-7 124'z Ul QA Condition 1 The information presented in this report has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
MCEI-0400-275 Page 2 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS
(? Zýý Inspection Waived By:
(Sponsor)
Date: 7
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MCEI-0400-275 Page 3 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Implementation Instructions For Revision 0 Revision Description and PIP Tracking Revision 0 of the McGuire Unit 2 Cycle 22 COLR contains limits specific to the reload core.
The revision is applicable for Unit 2 operation with or without implementation of the measurement uncertainty recapture (MUR) power uprate.
There is no PIP associated with this revision.
Implementation Schedule Revision 0 may become effective any time during No MODE between cycles 21 and 22, but must become effective prior to entering MODE 6 which starts cycle 22. The McGuire Unit 2 Cycle 22 COLR will cease to be effective during No MODE between cycles 22 and 23.
Data files to be Implemented No data files are transmitted as part of this document.
MCEI-0400-275 Page 4 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report REVISION LOG Revision 0
Effective Date July 2012 Pages Affected 1-32, Appendix A*
- Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. Appendix A is included only in the electronic COLR copy sent to the NRC.
MCEI-0400-275 Page 5 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below.
TS Number COLR El Section Page Technical Specifications COLR Parameter 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 Tests 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 Setpoints 3.4.1 RCS Pressure, Temperature, and Flow DNB limits 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 5.6.5 Core Operating Limits Report (COLR)
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 Cone.
Max and Min Boron Cone.
Min Boron Concentration Min Boron Concentration Analytical Methods 2.2 2.3 2.2 2.2 2.4 2.2 2.5 2.2 2.6 9
11 9
9 11 9
15 9
15 2.1 9
2.7 20 2.8 2.9 2.10 2.11 2.12 2.13 2.14 21 24 26 26 26 28 28 1.1 6
The Selected Licensee Commitments that reference this report are listed below:
SLC Number Selected Licensing Commitment 16.9.14 Borated Water Source - Shutdown 16.9.11 Borated Water Source - Operating 16.9.7 Standby Shutdown System COLR Parameter Borated Water Volume and Cone. for BAT/RWST Borated Water Volume and Cone. for BAT/RWST Standby Makeup Pump Water Supply COLR El Section Pare 2.15 29 2.16 2.17 30 30
MCEI-0400-275 Page 6 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 1.1 Analytical Methods The analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC as specified in Technical Specification 5.6.5 are as follows.
- 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," (W Proprietary).
Revision 0 Report Date: July 1985 Not Used
- 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",
(WY Proprietary).
Revision 2 Report Date: March 1987 Not Used
- 4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," O Proprietary).
Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)
Report Date: March 1998
- 5. BAW-1 01 68P-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
Revision 4a Report Date: July 2009
MCEI-0400-275 Page 7 Revision.0 McGuire 2 Cycle 22 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 7. DPC-NE-3001 -PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision Ga Report Date: May 2009
Revision 4b Report Date: September 2010
- 9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-0 1," (DPC Proprietary).
Revision 2a Report Date: December 2008
- 10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 4a Report Date: December 2008
- 11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision la Report Date: December 2008 Not Used
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 3a Report Date: September 2011
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMJULATE-3P."
Revision la Report Date: January 2009 Not Used
MCEI-0400-275 Page 8 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 14. DPC-NF-201 0-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."
Revision 2a Report Date: December 2009
- 15. DPC-NE-201 1-PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision 1 a Report Date: June 2009
- 16. DPC-NE-1005-PA, "Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX,"
(DPC Proprietary).
Revision 1 Report Date: November 12, 2008
MCEI-0400-275 Page 9 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.0 Operating Limits 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 Reactor Core Safety Limits (TS 2.1.1) 2.1.1 The Reactor Core Safety Limits are shown in Figure 1.
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 1 and 2.
2.2.4 For TS 3.1.5, SDM shall be > 1.3% AK/K in MODE 1 and MODE 2 with any control bank not fully inserted.
2.2.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in MODE 1 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 TESTS.
MCEI-0400-275 Page 10 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN THIS AREA 660 650 640 400 psia 0.1 630 590 2280 psia 06 0
6204.
0._.
610 600 590 ACCE9PTABLE 580
______I_______
0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
MCEI-0400-275 Page 11 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:
MTC shall be less positive than the upper limits shown in Figure 2. BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/0 F.
EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AKIK/°F lower MTC limit.
2.3.2 300 PPM MTC Surveillance Limit is:
Measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/°F.
2.3.3 60 PPM MTC Surveillance Limit is:
60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 (K/Kv/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 222 steps. Shutdown banks are withdrawn in sequence and with no overlap.
MCEI-0400-275 Page 12 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 Unacceptable Operation 0.8 0.7
- 0.6 0.5 0.4 Acceptable Operation 0.3 0.2 0.1 UC 0.0 i I
I I
I I
i i
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 withdrawal limits.
Refer to OP/2/A/6100/22 Unit 2 Data Book for details.
MCEI-0400-275 Page 13 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power 231 220 200 180 160 140 120 0
° 100 80 6 0 0
°-
40 o 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Percent of Rated Thermal Power The Rod Insertion Limits (RIL) for Control Bank D (CD), Control Bank C (CC), and Control Bank B (CB) can be calculated by:
Bank CD PJL = 2.3 (P) - 69 Bank CC RIL = 2.3(P) +47 Bank CB RIL = 2.3(P) +163
{30 < P < 100)
{0 < P < 76.1)for CC RIL = 222 [76.1 < P < 100)
(O < P < 25.7} for CB RIL = 222 {25.7 < P < 100}
where P = %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-0400-275 Page 14 Revision 0 MeGuire 2 Cycle 22 Core Operating Limits Report Table 1 RCCA Withdrawal Steps and Sequence Fully Withdrawn at 222 Steps Control Control Control Control BankA BankB BankC BankD Fully Withdrawn at n23 Steps Control Control Control Control BankA BankB BankC BankD 0 Start 0
0 0
116 0 Start 0
0 222 Stop 106 0
0 222 116 0 Start 0
222 222 Stop 106 0
222 222 116 0 Start 222 222 222 Stop 106 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 0 Start 223 223 223 Stop 107 Fully Withdrawn at 224 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 224 Stop 108 0
0 224 116 0 Start 0
224 224 Stop 108 0
224 224 116 0 Start 224 224 224 Stop 108 Fully Withdrawn at 226 Steps Control Control Control Control BankA BankB BankC BankD Fully Withdrawn at 225 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 0
0 0
116 0 Start 0
0 225 Stop 109 0
0 225 116 0 Start 0
225 225 Stop 109 0
225 225 116 0 Start 225 225 225 Stop 109 Fully Withdrawn at 227 Steps 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 Fully Withdrawn at 228 Steps Control Control Control Control BankA BankB BankC BankD 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 IlI Fully Withdrawn at 229 Steps Control Control Control Control BankA BankB BankC BankD 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 Fully Withdrawn at 230 Steps Control Control Control Control BankA Bank B BankC BankD 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
. Fully Withdrawn at 231 Steps 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 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
MCEI-0400-275 Page 15 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 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 3. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.
2.6 Heat Flux Hot Channel Factor - FQ(XY,Z) (TS 3.2.1) 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 RrP *K(Z)/0.5 for P < 0.5 Q
- where, P = (Thermal Power)/(Rated Power)
Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.6.5 and 2.6.6.
2.6.2 FrP 2.70 x K(BU) 2.6.3 K(Z) is the normalized FQ(XY,Z) as a function of core height. The K(Z) function for Westinghouse RFA fuel is provided in Figure 4.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of bumnup. F "rP with the K(BU)
Q penalty for Westinghouse RFA fuel is analytically confirmed in cycle-specific reload calculations. K(BU) is set to 1.0 at all burnups.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
L FQ(X,Y,Z)
- MQ(XY,Z) 2.6.5 FQXYZ)'
=
UMT
- TILT
MCEI-0400-275 Page 16 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report where:
FL (XYZ)oP F D (X,y,Z)
=
MQ(X,Y,Z)
=
Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit will be preserved for operation within the LCO limits. FL (X,Y,Z)OP includes allowances for calculation and measurement uncertainties.
Design power distribution for FQ. FQD (X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions, and in Appendix Table A-4 for power escalation testing during initial startup operation.
Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is provided in Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
UMT = Total Peak Measurement Uncertainty. (UMT = 1.05)
MT = Engineering Hot Channel Factor. (MT = 1.03)
TILT = Peaking penalty to account for allowable quadrant power tilt ratio of 1.02. (TILT= 1.035) 2.6.6 F Q(X,Y,Z)'R"5 FQ(X,Y,Z)
- Mc(X,Y,Z)
UMT
- TILT where:
L FQ(XYZ)RPI Cycle dependent maximum allowable design peaking factor that ensures the FQ(X,YZ) Centerline Fuel Melt (CFM) limit will be preserved for operation within the LCO limits.
L FQ(XY,Z)RPS includes allowances for calculation and measurement uncertainties.
Design power distributions for FQ. FQ(X,Y,Z) is provided in Appendix Table A-I for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
F Q,Y, Z)
MCEI-0400-275 Page 17 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report mc(X,Y,Z)
= Margin remaining to the CFM limit in core location XY,Z from the transient power distribution. Mc(X,Y,Z) is provided in Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operation.
UMT = Total Peak Measurement Uncertainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty to account for allowable quadrant power tilt ratio of 1.02. (TILT= 1.035) 2.6.7 KSLOPE = 0.0725 where:
KSLOPE is the adjustment to K1 value from the OTAT trip setpoint required to RPS compensate for each 1% that Ffj (X,Y,Z) exceeds F* (X,Y,Z) 2.6.8 FQ(X,Y,Z) penalty factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.
MCEI-0400-275 Page 18 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel 1.200 (0.0, 1.00)
(4.0% 1.00) 1.000 (12.0,0.9259)
(4.0,0.9259) 0.800 0.600 0.400 Core Height faitM 0.0 1.0
<40 1.0 0.200
>4.0 0.9259 110 0.9259 0.000 0.0 2:0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
MCEI-0400-275 Page 19 Revision 0 McGuire 2 Cycle 22 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 (EFPD) 0 4
12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 435 460 468 478 493 503 FQ(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 2.00 2.00 2.00 2.00 2.00 2.00 2.00 FAH(X,Y)
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 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 bumups 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-0400-275 Page 20 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) (TS 3.2.2)
FAII steady-state limits referred to in Technical Specification 3.2.2 is defined by the following relationship.
2.7.1 F*L (X, Y)
= M 1
1
-'.,,u.-- -,
MAR (XY) 1.R+
H (1.0- P)]
where:
FLH (X, Y) " is the steady-state, maximum allowed radial peak and 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, FAH (XY), exceeds its limit. RRH also is used to scale the MARP limits as a function of power per the [FAH (X, Y)]t 0o 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 FFDH(X,Y)sxMAH(XY) 2.7.2 FAH(MY)
UMR x TILT where:
Fk1H (XY)sURv = Cycle dependent maximum allowable design peaking factor that ensures the FA(X,Y) limit will be preserved for operation SURV
- within the LCO limits. Fka (X,Y) includes allowances for calculation/measurement uncertainty.
MCEI-0400-275 Page 21 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report D
FAH (X,Y) = Design radial power distribution for FAH. FH (X,Y) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.
MAH(X,Y) = The margin remaining in core location XY relative to the Operational DNB limits in the transient power distribution.
MAH(XY) is provided in Appendix Table A-3 for normal operation and in Appendix Table A-6 for power escalation testing during initial startup operation.
UMR = Uncertainty value for measured radial peaks (UMR = 1.0).
UMR is 1.0 since a factor of 1.04 is implicitly included in the variable MAH(X,Y).
TILT Peaking penalty to account for 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, FAH (X,Y) exceeds its limit. (0 <P <5 1.0) 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, FAH (X,Y) exceeds its limit.
2.7.5 FAn (XY) 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 5.
MCEI-0400-275 Page 22 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)
RFA MARPS Core Axial Peak Ht (ft.)
1.05 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 1.809 1.855 1.949 1.995 1.974 2.107 2.050 2.009 1.933 1.863 1.778 1.315 1.246 1.2 1.810 1.854 1.940 1.995 1.974 2.107 2.019 1.978 1.901 1.831 1.785 1.301 1.224 2.4 1.809 1.853 1.931 1.978 1.974 2.074 1.995 1.952 1.876 1.805 1.732 1.463 1.462 3.6 1.810 1.851 1.920 1.964 1.974 2.050 1.966 1.926 1.852 1.786 1.700 1.468 1.387 4.8 1.810 1.851 1.906 1.945 1.974 2.006 1.944 1.923 1.854 1.784 1.671 1.299 1.258 6.0 1.810 1.851 1.892 1.921 1.946 1.934 1.880 1.863 1.802 1.747 1.671 1.329 1.260 7.2 1.807 1.844 1.872 1.893 1.887 1.872 1.809 1.787 1.733 1.681 1.598 1.287 1.220 8.4 1.807 1.832 1.845 1.857 1.816 1.795 1.736 1.709 1.654 1.601 1.513 1.218 1.158 9.6 1.807 1.810 1.809 1.791 1.738 1.718 1.657 1.635 1.581 1.530 1.444 1.143 1.091 10.8 1.798 1.787 1.761 1.716 1.654 1.632 1.574 1.557 1.509 1.462 1.383 1.101 1.047 11.4 1.789 1.765 1.725 1.665 1.606 1.583 1.529 1.510 1.464 1.422 1.346 1.067 1.014
MCEI-0400-275 Page 23 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits Cd
- 0 S.-
(-18, 100)
Unacceptable Operation Acceptable Operation
(-36, 50)
MIMIMI 90 +
80 +
Unacceptable Operation
(+21, 50)
(+10, 100) 70 4 60 +
50 +/-
40 4 30 +
20 -
10 I I
I I
II-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/2/A/6100/22 Unit 2 Data Book for more details.
MCEI-0400-275 Page 24 Revision 0 McGuire 2 Cycle 22 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 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 Tavg Time constant utilized in the measured Tavg lag compensator fl(A1) "positive" breakpoint fl(AI) "negative" breakpoint fl(AI) "positive" slope fl(AI) "negative" slope T' < 585.1°F P'= 2235 psig KI < 1.1978 K2 = 0.0334/°F K3 = 0.001601/psi t1 >8 sec.
-2 < 3 sec.
T3 < 2 sec.
T4 > 28 sec.
E5 < 4 sec.
T6 < 2 sec.
= 19.0 %AI
= N/A*
= 1.769 %AT 0/ %AI
= N/A*
The fl(Al) "negative" breakpoints and the fl(Al) "negative" slope are less restrictive than the OPAT f2(AI) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits, the OPAT f2 (AI) limits will result in a reactor trip before the OTAT fl (AI) limits are reached. This makes implementation of the OTAT fl (Al) negative breakpoint and slope unnecessary.
++ AT0 is assumed to be renormalized to 100% RTP following the MUR power uprate.
MCEI-0400-275 Page 25 Revision 0 McGuire 2 Cycle 22 Core Oper 2.9.2 Overpower AT Setpoint Parameter V 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 Tavg lag compensator Time constant utilized in the rate-lag controller for Tavg f2(AI) "positive" breakpoint f2(AI) "negative" breakpoint f2(AD) "positive" slope f2(AI) "negative" slope ating Limits Report alues Value T" < 585.10 F K4 < 1.0864 K5 = 0.02/'F for increasing Tavg K5 = 0.0 for decreasing Tavg K6 = 0.001 179/°F for T > T" K6 = 0.0 for T < T"
,1 > 8 sec.
[2 < 3 sec.
t 3 < 2 sec.
T6 < 2 sec.
'7 > 5 sec.
= 35.0 %AI
= -35.0 %AI
= 7.0 %AT 0/%AI
= 7.0 %AT 0/ %AI
++ ATo is assumed to be renormalized to 100% RTP following the MUR power uprate.
MCEI-0400-275 Page 26 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.10 RCS Pressure, Temperature and Flow Limits for DNB (T'S 3.4.1) 2.10.1 RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.11 Accumulators (IS 3.5.1) 2.11.1 Boron concentration limits during MODES 1 and 2, and MODE 3 with RCS pressure >1000 psi:
Parameter Applicable Burnup Limit Accumulator minimum boron 0 - 200 EFPD 2,475 ppm concentration.
Accumulator minimum boron 200.1 - 250 EFPD 2,408 ppm concentration.
Accumulator minimum boron 250.1 - 300 EFPD 2,346 ppm concentration.
Accumulator minimum boron 300.1 - 350 EFPD 2,277 ppm concentration.
Accumulator minimum boron 350.1 - 400 EFPD 2,207 ppm concentration.
Accumulator minimum boron 400.1 - 450 EFPD 2,142 ppm concentration.
Accumulator minimum boron 450.1 - 493 EFPD 2,075 ppm concentration.
Accumulator minimum boron 493.1 - 503 EFPD 2,017 ppm concentration.
Accumulator maximum boron 0 - 503 EFPD 2,875 ppm concentration.
2.12 Refueling Water Storage Tank - RWST (1S 3.5.4) 2.12.1 Boron concentration limits during MODES 1, 2, 3, and 4:
Parameter Limit RWST minimum boron concentration.
2,675 ppm RWST maximum boron concentration.
2,875 ppm
MCEI-0400-275 Page 27 Revision 0 McGuire 2 Cycle 22 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 OF meter 3
< 586.9 OF 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
> 388,000 gpm
MCEI-0400-275 Page 28 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.13 Spent Fuel Pool Boron Concentration (17S 3.7.14) 2.13.1 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 2.14 Refueling Operations - Boron Concentration (TS 3.9.1) 2.14.1 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 core Keff remains within 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-0400-275 Page 29 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.15 Borated Water Source - Shutdown (SLC 16.9.14) 2.15.1 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 BAT minimum contained borated water volume 10,599 gallons 13.6% Level Note: When cycle burnup is > 460 EFPD, Figure 6 may be used to determine required BAT minimum level.
I BAT minimum boron concentration BAT minimum water volume required to maintain SDM at 7,000 ppm RWST minimum contained borated water volume RWST minimum boron concentration RWST 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-0400-275 Page 30 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report 2.16 Borated Water Source - Operating (SLC 16.9.11) 2.16.1 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 BAT minimum contained borated water volume 22,049 gallons 38.0% Level Note: When cycle burnup is > 460 EFPD, Figure 6 may be used to determine required BAT minimum level.
i BAT minimum boron concentration 7,000 ppm BAT minimum water volume required to maintain SDM at 7,000 ppm RWST minimum contained borated water volume RWST minimum boron concentration RWST maximum boron concentration (TS 3.5.4)
RWST minimum water volume required to maintain SDM at 2,675 ppm 13,750 gallons 96,607 gallons 103.6 inches 2,675 ppm 2,875 ppm 57,107 gallons 2.17 Standby Shutdown System - (SLC-16.9.7) 2.17.1 Minimum boron concentration limit for the spent fuel pool required for Standby Makeup Pump Water Supply. Applicable for MODES 1, 2, and 3.
Parameter Spent fuel pool minimum boron concentration for TR 16.9.7.2.
Limit 2,675 ppm
MCEI-0400-275 Page 31 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus RCS Boron Concentration (Valid When Cycle Burnup is > 460 EFPD)
This figure includes additional volumes listed in SLC 16.9.14 and 16.9.11 40.0 35.0 30.0 25.0 20.0 15.0 10.0 5.0 0.0 RCS Boron Concentration BAT Level (ppm)
(%level) 0<300 37.0 300 < 500 33.0 500-< 700 28.0 700 <1000 23.0 1000 <1300~ 13.6
> 1300 8.7 Unacceptable Operation Acceptable
.1 I
I U -
200 400 600 800 1000 1200 1400 1600 1800 2000 RCS Boron Concentration (ppmb) 2200 2400 2600 2800
MCEI-0400-275 Page 32 Revision 0 McGuire 2 Cycle 22 Core Operating Limits Report NOTE: Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire 2 Cycle 22 Maneuvering Analysis calculation file, MCC-1553.05-00-0560. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke and is not included in the Duke internal copies of the COLR. The Plant Nuclear Engineering Section will control this information via computer file(s) and should be contacted if there is a need to access this information.
Appendix A is included in the COLR copy transmitted to the NRC.