ML040650658
| ML040650658 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 02/23/2004 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040650658 (66) | |
Text
Duke GARY R. PETERSON rwPowere Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpetersiduke-energy.com February 23, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station, Docket Nos. 50-369, 370 Unit 1, Cycle 16, Revision 26 Unit 2, Cycle 16, Revision 24 Core Operating Limits Report (COLR)
Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed revisions to the McGuire Unit 1 and Unit 2, Cycle 16 Core Operating Limits Report (COLR). These mid-cycle revisions were issued based upon NRC approval of License Amendments 219/201 dated January 14, 2004.
Questions regardigg-thJs submittal should be directed to Kay Crane, McGuire Regulatory Gary R. Peterson Attachment to(
www. duke-energy. corn
MCEI-040046 Page 1 of 32 Revision 26 McGuire Unit 1 Cycle 16 Core Operating Limits Report Revision 26 January 2004 Calculation Number: MCC-1553.05-00-0371, Rev. 2 Duke Power Company Date Prepared By: 1 /23 1200 V Checked By:
2L./
/ .Z2z- fRo7y 1/;23 Zo50 f Checked By: , >4 Rawe_~* (lctiotR-217)
Approved By: .I & 0i1 /eJ~oo4 IZ QA Condition 1 The information presented in this report has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
MCEI-040046 Page 2 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:. :.Nko Date: 0112f 41 2A34 (Sponsor)
CATAWBA Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) El Inspected By/Date:
RES (Reactor) El Inspected By/Date:
MOD El Inspected By/Date:
Other( ) El Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date: -
RES (Electrical Only) El Inspected By/Date:
RES (Reactor) El Inspected By/Date:
MOD El Inspected By/Date:
Other( ) El Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) Inspected By/Date:
RES (Reactor) Inspected By/Date:
Eel MOD Inspected By/Date:
Other( ) Inspected By/Date:
MCEI-040046 Page 3 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Rcport IMPLEMENTATION INSTRUCTIONS FOR REVISION 26 Revision 26 to the McGuire Unit 1 Cycle 16 COLR is being performed to relocate the following information from Technical Specifications to the COLR.
- a. "Reactor Core Safety limits" figure from Technical Specification 2.1.1.
- b. Overtemperature AT and Overpower AT nominal RCS operating pressure, nominal average temperature and K5 and K6 (for decreasing Tave) values from TS Table 3.3.1-1.
Limits from TS 3.4.1.
The relocation of the above information from Technical Specifications to the COLR is being performed based on the NRC approval of Technical Specification Amendment 219 dated January 14, 2004. This COLR revision should be performed concurrent with the Technical Specification change and should become effective prior to the expiration of the implementation period specified in the Amendment.
MCEI-0400-46 Page 4 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Pages COLR Revisions 0-3 Superseded NIA M1C09 Revisions 4-8 Superseded NIA MiCI0 Revisions 9-11 Superseded N/A MICHI Revisions 12-15 Superseded N/A M1C12 Revisions 16-17 Superseded N/A M1C13 Revision 18-20 Superseded N/A M1C14 Revision 21-23 Superseded N/A MlC15 Revision 24 August 30, 2002 Appendix A M1C16 (Original Issue)
Revision 25 September 3, 2003 N/A MlC16 (Revision 1)
Revision 26 January 26, 2004 1 -32 MlC16 (Revision 2)
MCEI-040046 Page 5 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report INSERTION SHEET FOR REVISION 26 Remove pages Insert Rev. 26 pages Pages 1 - 29 Inclusive Pages 1 - 32
MCEI-040046 Page 6 of 32 Revision 26 McGuirc 1 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 the Technical Specification 5.6.5. The Technical Specifications that reference the COLR are summarized below.
TS COLR El Number Technical Specifications
- COLRZ Parameter Section Pa9e 1.1 Requirements for Operational Mode 6 Mode 6 Definition 2.1 9 2.1.1 Reactor Core Safety Limits RCS Temperature and 2.2 9 Pressure Safety Limits 3.1.1 Shutdown Margin Shutdown Margin 2.3 9 3.1.3 Moderator Temperature Coefficient MTC 2.4 11 3.1.4 Rod Group Alignment Limits Shutdown Margin 2.3 9 3.1.5 Shutdown Bank Insertion Limits Shutdown Margin 2.3 9 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion 2.5 11 Limit 3.1.6 Control Bank Insertion Limits Shutdown Margin 2.3 9 3.1.6 Control Bank Insertion Limits Control Bank Insertion 2.6 11 Limit 3.1.8 Physics Test Exceptions Shutdown Margin 2.3 9 3.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.7 15 Penalty Factors 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.8 20 Factor Penalty Factors 3.2.3 Axial Flux Difference AFD 2.9 21 3.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.10 24 Setpoint Constants 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, 2.11 26 limits for DNB Temperature and Flow 3.5.1 Accumulators Max and Min Boron Conc. 2.12 26 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc. 2.13 26 3.7.14 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 28 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 28 Concentration The Selected Licensee Commitments that reference this report are listed below:
COLR El SLC Number Selected Licensing Commitment COLR Parameter Section Page 16.9.14 Borated Water Source - Shutdown Borated Water Volume and 2.16 29 Conc. for BAT/RWST 16.9.11 Borated Water Source - Operating Borated Water Volume and 2.17 30 Conc. for BATIRWST
MCEI-040046 Page 7 of 32 Revision 26 McGuire 1 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" (! Proprietary).
Revision 0 Report Date: July 1985 Not Used for M1C16
- 2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," (! Proprietary).
Revision 0 Report Date: August 1985
- 3. WCAP-10266-P-A, "The 1981 Version Of Westinghouse Evaluation Model Using BASH Code", (! Proprietary).
Revision 2 Report Date: March 1987 Not Used for M1C16
- 4. WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (i Proprietary).
Revision: Volume 1 (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 M1C16
Revision 2 SER Date: October 14, 1998
MCEI-040046 Page 8 of 32 Revision 26 McGuire 1 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 1991
Revision 4 SER Date: April 6, 2001
- 9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).
Revision 1 SER Date: February 20, 1997
- 10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 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 2 SER Date: December 18, 2002
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASM0-3/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 2 SER Date: June 24. 2003
MCEI-040046 Page 9 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 15. DPC-NE-2011PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision I SER Date: October 1, 2002 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified in Section 1.1.
2.1 Requirements for Operational Mode 6 The following condition is required for operational mode 6.
2.1.1 The Reactivity Condition requirement for operational mode 6 is that kff must be less than, or equal to 0.95.
2.2 Reactor Core Safety Limits (TS 2.1.1) 2.2.1 The Reactor Core Safety Limits are shown in Figure 1.
2.3 Shutdown Margin - SDM C(S 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6 and TS 3.1.8) 2.3.1 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.
2.3.2 For TS 3.1.1, SDM shall be > 1.0% AK/K in mode 5.
2.3.3 For TS 3.1.4, SDM shall be > 1.3% AK/K in modes 1 and 2.
2.3.4 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.
2.3.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in mode 1 and mode 2 with K-eff > 1.0.
2.3.6 For TS 3.1.8, SDM shall be > 1.3% AK/K in mode 2 during Physics Testing.
MCEI-040046 Page 10 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 _
DO NOT OPERATE IN THIS AREA 660 640 630 620 2100 pi 610 600 590 ACCEPTABLE 580 0.2 0 0 0.8 1.0 _ 1.2 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
MCEI-040046 Page I1 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.4 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.4.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the upper limits shown in Figure 2. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/IF.
The EOC, ARO, RTP MTC shall be less negative than the 4.3E-04 AK/K/ 0 F lower MTC limit.
2.4.2 The 300 PPM MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/0 F.
2.4.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 AKIK/ 0 F.
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) 2.5 Shutdown Bank Insertion Limit (TS 3.1.5) 2.5.1 Each shutdown bank shall be withdrawn to at least 226 steps. Shutdown banks are withdrawn in sequence and with no overlap.
2.6 Control Bank Insertion Limits (TS 3.1.6) 2.6.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.
MCEI-0400-46 Page 12 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 -
Unacceptable Operation
.i) 0.8 0.7 0.6 a:-
-al 0.5 0It 0.4 Acceptable Operation\
Ez 0 0.3 C:
1W 0.2 0.1 I* I 0.0 .4 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/1/A/6100/22 Unit 1 Data Book for details.
MCEI-040046 Page 13 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231) 231 220 200 E 180
= 160 v 140 2
= 120 0
100 o 80
_ 60 X 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/l/A/6100122 Unit 1 Data Book for details.
MCEI-040046 Page 14 of 32 Revision 26 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 OStart 0 0 0 116 0 Start 0 0 116 0 Start 0 0 226 Stop 110 0 0 227Stop 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 SWVD 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 0Start 0 0 116 0 Start 0 0 228 Stop 112 0 0 229 Stop 113 0 0 228 116 0 Start 0 229 116 0Start 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 OStart 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 230Stop - 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 0Start 230 230 230 Stop 114 231 231 231 Stop 115
MCEI-0400-46 Page 15 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.7 Heat Flux Hot Channel Factor - FQ(XY,Z) (TS 3.2.1) 2.7.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:
F P *K(Z)/P for P > 0.5 FQ *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 2.7.5 and 2.7.6.
2.7.2 FI = 2.50 x K(BU) 2.7.3 K(Z) is the normalized FQ(XYZ) as a function of core height. The K(Z) function for MkBW and Westinghouse RFA fuel is provided in Figure 4.
2.7.4 K(BU) is the normalized FQ(X,Y,Z) as a function of bumup. K(BU) for both MkBW and Wesinghouse RFA fuel is 1.0 for all bumups.
The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification 3.2.1:
FQ(X,YZ)
- MQ(X,YZ) 2.7.5 [Fm(XYZ)]OP = UMT
- TILT where:
[FQ (XYZ)]OP = 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. [ FL (XY,Z)]OP includes allowances for calculation and measurement uncertainties.
FQD (X,Y,Z) = Design power distribution for FQ. FQD (X,Y,Z) is provided in Table 4, Appendix A, for normal operating conditions and in
MCEI-040046 Page 16 of 32 Revision 26 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. (UMTI = 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)
F<(X,Yz)
- MCX,Y,Z) 2.7.6 [FQ(XYZ)] =
UMT
- TILT where:
[F (X,Y~Z)]Rns - 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.
[FLQ(X,Y,Z)]RPs includes allowances fcfr calculation and measurement uncertainties.
F,'(X,Y,Z) = 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(X,Y,Z) = Margin remaining to the CFM limit in core location X,YZ from the transient power distribution. 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.
MCEI-040046 Page 17 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report UMT = Total Peak Measurement Uncertainty (UMT = 1.05)
MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.7.7 KSLOPE = 0.0725 where:
KSLOPE is the adjustment to the K1 value from OTAT trip setpoint required to compensate for each 1% that FQ' (XY,Z) exceeds [ FQ (XYZ)]
2.7.8 FQ(X,Y,Z) penalty factors forTechnical Specification Surveillance's 3.2.1.2 and 3.2.1.3 are provided in Table 2.
MCEI-040046 Page 18 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(XY,Z) 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
- 0.6 0.4 0.2
.I I \ .
0.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
MCEI-0400-46 Page 19 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Table 2 FQ(X,Y,Z) and F]jH(XY) Penalty Factors Flor Technical Specification Surveillance's 3.2.1.2,3.2.1.3 and 3.2.2.2 Burnup FQ(X,YZ) FMI(X,Y,Z)
(E PD) 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 burnups outside of the range of the table shall use a 2% penalty factor for both FQ(X,YIZ) and FMH(XY) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
MCEI-040046 Page 20 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.8 Nuclear Enthalpy Rise Hot Channel Factor - FAII(X,Y) (TS 3.2.2)
The FPUH steady-state limits referred to in Technical Specification 3.2.2 is defined by the following relationship.
2.8.1 [FL (X, Y)]"Lo = MARP (XY) * [1.0 + I* (1.0- P)]
where:
[FwL(X,Y)]Lco is defined as the steady-state, maximum allowed radial peak.
[FuL (X,Y)]L' 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.
p Thermal Power Rated Thermal Power RRH =Thermal Power reduction required to compensate for each 1% that the measured radial peak, FS (X,Y), exceeds the limit. RRH also is used to scale the MARP limits as a function of power per the [FL, (X,Y)]Lco equation. (RRH = 3.34 (0.0 < P < 1.0))
The following parameters are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.
2L . (XY)]SURV FA,, (X, Y) XMAH (X, Y) 2.8.2 [ =MR xThILT where:
[FaLl (X,Y)]SU = Cycle dependent maximum allowable design peaking factor that ensures that the F,(X,Y) limit will be preserved for operation within the LCO limits. [Fm,1 (XY)]SURVincludes allowances for calculation-measurement uncertainty.
MCEI-040046 Page 21 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report F4 (X,Y) = Design radial power distribution for P2\H Fl '(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.
MAIH(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(XY).
TILT = Peaking penalty that accounts for the peaking increase for an allowable quadrant power tilt ratio of 1.02, (TILT = 1.035).
2.8.3 RRH = 3.34 where:
RRH = Therrnal power reduction required to compensate for each 1% that the measured radial peak, F2K (XY) exceeds its limit. (0 < P < 1.0) 2.8.4 TRH = 0.04 where:
TRH = Reduction in OTAT K1 setpoint required to compensate for each 1% that the measured radial peak, Fm (X,Y) exceeds its limit.
2.8.5 FAI,,(XY) penalty factors for Technical Specification Surveillance 3.2.2.2 are
- provided in Table 2.
2.9 Axial Flux Difference - AFD (TS 3.2.3) 2.9.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
MCEI-0400-46 Page 22 of 32 Revision 26 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 1.20 130 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-040046 Page 23 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits S.
0 10 I-6 C)
-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/1/A/6100/22 Unit 1 Data Book of more details.
MCEI-040046 Page 24 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.10 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.10.1 Overtemperature AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T'<585.10 F Nominal RCS Operating Pressure P' = 2235 psig Overtemperature AT reactor trip setpoint KI
- 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.0334/OF penalty coefficient Overtemperature AT reactor trip depressurization K3 = 0.001601/psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator ¶iS8sec.
for AT T2 <3 sec.
Time constant utilized in the lag compensator for AT Tr3
- 2 sec.
Time constants utilized in the lead-lag compensator T4 > 28 sec.
for Tayg r5 *4 sec.
Time constant utilized in the measured Tavg lag T6 < 2 sec.
compensator fl(Al) "positive" breakpoint = 19.0 %AI fi(AD)"negative" breakpoint = N/A*
f1 (AI) "positive" slope = 1.769 %AT'o %AI fl ( Al) "negative" slope = NIA*
- The f(AI) "negative" breakpoint and the f 1 (AI) "negative" slope are not applicable since the fl(Al) function is not required below the fl(AI) "positive" breakpoint of 19.0% Al.
MCEI-040046 Page 25 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T" < 585.10 F Overpower AT reactor trip setpoint Ki < 1.0864 Overpower AT reactor trip Penalty K5 = 0.02/0 F for increasing Tavg K5 = 0.0 for decreasing Tavg Overpower AT reactor trip heatup K6 = 0.001 179/0 F for T > T" setpoint penalty coefficient K 6 = 0.0 for T <T" Time constants utilized in the lead-lag lŽ> 8 sec.
compensator for AT T2 < 3 sec.
Time constant utilized in the lag T3 <2sec.
compensator for AT Time constant utilized in the T6 < 2 sec.
measured Tavg lag compensator Time constant utilized in the rate-lag T7 > 5 sec.
controller for Tavg f2 (AI) "positive" breakpoint =35.0 %AI f2 (AI) "negative" breakpoint -- 35.0 %AI f2 (AI) "positive" slope =7.0 %,&Td %AI f2 (AI) "negative" slope = 7.0 %ATTJ %AI
MCEI-040046 Page 26 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during modes 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 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 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-040046 Page 27 of 32 Revision 26 McGuire 1 Cycle 16 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 cF computer 4 < 587.7 OF computer 3 < 587.5 OF
- 2. Indicated Pressurizer Pressure meter 4 > 2219.8 psig meter 3 > 2222.1 psig computer 4 > 2215.8 psig computer 3 > 2217.5 psig
- 3. RCS Total Flow Rate > 390,000 gpm
MCEI-040046 Page 28 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.14) 2.14.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration. 2,675 ppm 2.15 Refueling Operations - Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keff <
0.95.
Parameter Limit Minimum Boron concentration of the Reactor Coolant 2,675 ppm System, the refueling canal, and the refueling cavity.
MCEI-040046 Page 29 of 32 Revision 26 McGuire 1 Cycle 16 Core Operating Limits Report 2.16 Borated Water Source - Shutdown (SLC 16.9.14) 2.16.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during mode 4 with any RCS cold leg temperature < 300 'F and modes 5 and 6.
Parameter Limit Boric Acid Tank minimum contained borated 10,599 gallons water volume 13.6% 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 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-040046 Page 30 of 32 Revision 26 McGuirc I Cycle 16 Core Operating Limits Report 2.17 Borated Water Source - Operating (SLC 16.9.11) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during modes 1, 2, 3, and mode 4 with all RCS cold leg temperatures > 300'F.
Parameter Limit Boric Acid Tank minimum contained borated 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-040046 Page 31 of 32 Revision 26 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
.n n I
i i I
i I Concentration BAT Level I (ppm) (%level) 0 < 300 37.0 I i; 300 < 500 33.0 500 < 700 28.0 700 < 1000 23.0
=, I e ! ; i :
1000 < 1300
> 1300 1 13.6 88.7 a)
-J ., ,
i- I e; - e~~ I j l - -
I I-- i i
i Acceptable Operation I
- 15.0- iI ! i I i
I 10.0 I
I I
I Unacceptable Operationl i 1 _ I -
U I
- I - I i
I i
- U - I - I -
I i,..
5.0- i i i ~ I . ..... ...I. i u.u i I I I i i I I 0 200 400 600 800 1000 1200 1400 1600 1800 20200 240u 260 2800 RCS Boron Concentration (ppmb)
MCEI-040046 Page 32 of 32 Revision 26 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.
MCEI-0400-47 Page 1 of 33 Revision 24 McGuire Unit 2 Cycle 16 Core Operating Limits Report Revision 24 January 2004 Calculation Number: MCC-1553.05-00-0391 (Rev. 1)
Duke Power Company Date Prepared By: I J.3 ];IOO'f Checked By:
/- .2c4 Checked By: R6AL M-(Secons 2. W - 2.17)
Approved By: Os1 12812I004*
a' 1 QA Condition 1 The information presented in this report has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
MCEI-0400-47 Page 2 of 33 Revision 24 McGuirc 2 Cycle 16 Core Operating Limits Report INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: htpnt
%F -I f. wwk Date:_'I /1.2eqi o4 (Sponsor)
CATAWBA Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) 0 Inspected By/Date:
RES (Reactor) E] Inspected By/Date:
MOD El Inspected By/Date:
Other( ) El Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) El Inspected By/Date:
RES (Reactor) El Inspected By/Date:
MOD El Inspected By/Date:
Other( ) El Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:
RES (Electrical Only)
R Inspected By/Date: -
RES (Reactor) Il Inspected By/Date:
12r Inspected By/Date:
[P.
Other ( ) Inspected By/Date:
MCEI-040047 Page 3 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 24 Revision 24 to the McGuire Unit 2 Cycle 16 COLR is being performed to relocate the following information from Technical Specifications to the COLR.
- a. "Reactor Core Safety limits" figure from Technical Specification 2.1.1.
- b. Overtemperature AT and Overpower AT nominal RCS operating pressure, nominal average temperature and constant K5 and K6 (decreasing Tave) values from TS Table 3.3.1-1.
Limits from TS 3.4.1.
The relocation of the above information from Technical Specifications to the COLR is being performed based on the NRC approval of Technical Specification Amendment 201, dated January 14, 2004. This COLR revision should be performed concurrent with the Technical Specification implementation and should become effective prior to expiration of the implementation period specified in Amendment 201.
MCEI-0400-47 Page 4 of 33 Revision 24 McGuire 2 Cycle 16 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 M2C10 Revisions 7-12 Superseded N/A M2C11 Revision 13-15 Superseded N/A M2C12 Revision 16-17 Superseded N/A M2C13 Revision 18-20 Superseded N/A M2C14 Revision 21-22 Superseded N/A M2C15 Revision 23 September 3, 2003 Appendix A M2C16 - Orig. Issue Revision 24 January26, 2003 1-33 M2C16-Rev. 1
MCEI-0400-47 Page 5 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report INSERTION SHEET FOR RE VISION 24 Remove pages Insert Rev. 24 pages Pages 1 - 31 Pages 1 - 33
MCEI-0400-47 Page 6 of 33 Revision 24 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. The Technical Specifications that reference the COLR are summarized below.
TS COLR El Number Technical Specifications COLR Parameter Section Page 1.1 Requirements for Operational Mode 6 Mode 6 Definition 2.1 9 2.1.1 Reactor Core Safety Limits RCS Temperature and 2.2 9 Pressure Safety Limits 3.1.1 Shutdown Margin Shutdown Margin 2.3 9 3.1.3 Moderator Temperature Coefficient MTC 2.4 11 3.1.4 Rod Group Alignment Limits Shutdown Margin 2.3 9 3.1.5 Shutdown Bank Insertion Limits Shutdown Margin 2.3 9 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion 2.5 11 Limit 3.1.6 Control Bank Insertion Limits Shutdown Margin 2.3 9 3.1.6 Control Bank Insertion Limits Control Bank Insertion 2.6 11 Limit 3.1.8 Physics Test Exceptions Shutdown Margin 2.3 9 3.2.1 Heat Flux Hot Channel Factor Fq, AFD, OTAT and 2.7 16 Penalty Factors 3.2.2 Nuclear Enthalpy Rise Hot Channel FAH, AFD and 2.8 21 Factor Penalty Factors 3.2.3 Axial Flux Difference AFD 2.9 22 3.3.1 Reactor Trip System Instrumentation OTAT and OPAT 2.10 25 Setpoint Constants 3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, 2.11 27 limits for DNB Temperature and Flow 3.5.1 Accumulators Max and Min Boron Conc. 2.12 27 3.5.4 Refueling Water Storage Tank Max and Min Boron Conc. 2.13 27 3.7.14 Spent Fuel Pool Boron Concentration Min Boron Concentration 2.14 29 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.15 29 Concentration The Selected Licensee Commitments that reference this report are listed below:
COLR El SLC Number Selected Licensing Commitment COLR Parameter Section Page 16.9.14 Borated Water Source - Shutdown Borated Water Volume and 2.16 30 Conc. for BAT/RWST 16.9.11 Borated Water Source - Operating Borated Water Volume and 2.17 31 Conc. for BAT/RWST
MCEI-040047 Page 7 of 33 Revision 24 McGuire 2 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 are as follows.
- 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," (WbProprietary).
Revision 0 Report Date: July 1985 Not Used for M2C16
- 2. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code, " OV Proprietary).
Revision 0 Report Date: August 1985
- 3. WCAP-10266-P-A, "The 1981 Version Of Westinghouse Evaluation Model Using BASH Code",
(Y 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 Loss of Coolant Analysis," (! 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 SERDates: August22, 1996andNovember26, 1996.
Revision 3 SER Date: June 15, 1994.
Not Used for M2C16
Revision 2 SER Date: October 14, 1998
MCEI-0400-47 Page 8 of 33 Revision 24 McGuirc 2 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods Continued
- 7. DPC-NE-300IPA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision 0 Report Date: November 15, 1991
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-0 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
- 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 18, 2002
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."
Revision I SER Date: April 26, 1996
- 14. DPC-NF-20 1OA, "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 33 Revision 24 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 1 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 kfr must be less than, or equal to 0.95.
2.2 Reactor Core Safety Limits (TS 2.1.1) 2.2.1 The Reactor Core Safety Limits are shown in Figure 1.
23 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6 and TS 3.1.8) 2.3.1 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.
2.3.2 For TS 3.1.1, SDM shall be > 1.0% AK/K in mode 5.
2.3.3 For TS 3.1.4, SDM shall be > 1.3% AK/K in modes I and 2.
2.3.4 For TS 3.1.5, SDM shall be > 1.3% AK/K in mode I and mode 2 with any control bank not fully inserted.
2.3.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in mode 1 and mode 2 with K-eff > 1.0.
2.3.6 For TS 3.1.8, SDM shall be > 1.3% AK/K in mode 2 during Physics Testing.
MCEI-0400-47 Page IOof 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation 670 DO NOT OPERATE IN TIlS AREA 660 650 640 1-4 VA 0 630 U 620 I\
2280 psi 610 600 I~I 590
. ACCE17ABLE 580 . I 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
MCEI-040047 Page 1I of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.4 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.4.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the upper limits shown in Figure 2. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/0 F.
The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/K/0 F lower MTC limit.
2.4.2 The 300 ppm MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AKIK/IF.
2.4.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 AKJKI 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) 2.5 Shutdown Bank Insertion Limit (TS 3.1.5) 2.5.1 Each shutdown bank shall be withdrawn to at least 222 steps. Shutdown banks are withdrawn in sequence and with no overlap.
2.6 Control Bank Insertion Limits (TS 3.1.6) 2.6.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 3. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table l.
MCEI-0400-47 Page 12of33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Figure 2 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 0.9 -
Unacceptable Operation U 0.8 c) 0.7 L) ca) 0.6 E.
(.
em 0.5 0.4 Acceptable Operation\
a) a)
e-
%-- 0.3
'.4 3-a) 0.2 0.1 I I I I 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-040047 Page 13 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Figure 3 Control Bank Insertion Limits Versus Percent Rated Thermal Power Fully Withdrawn (Maximum = 231) 231 220 200 K 180
- 160 V...
- o. 140 co (n
. 120
.2 o 100 o 80 5-
= 60 0
40 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/2/A/6100/22 Unit 2 Data Book for details.
MCEI-040047 Page 14 of 33 Revision 24 McGuirc 2 Cycle 16 Core Operating Limits Report Table I RCCA Withdrawal Steps and Sequence RCCAs Fully Withdrawn at 222 SNVD RCCAs Fully Withdrawn at 223 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 0Start 0 0 0 116 0Start 0 0 116 0 Start 0 0 222 Stop 106 0 0 223 Stop 107 0 0 222 116 0 Start 0 223 116 0 Start 0 222 222 Stop 106 0 223 223 Stop 107 0 222 222 116 0 Start 223 223 116 0 Start 222 222 222 Stop 106 223 223 223 Stop 107 RCCAs Fully Withdrawn at 224 SWVD RCCAs Fully Withdrawn at 225 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 0Start 0 0 0 0 Start 0 0 0 116 0 Start 0 0 116 0 Start 0 0 224 Stop 108 0 0 225 Stop 109 0 0 224 116 0 Start 0 225 116 0 Start 0 224 224 Stop 108 0 225 225 Stop 109 0 224 224 116 0 Start 225 225 116 0 Start 224 224 224 Stop 108 225 225 225 Stop 109 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 0Start 0 0 0 0Start 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 226Stop 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
MCEI-040047 Page 15 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Table 1 Continued RCCA Withdrawal Steps and Sequence 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 0Start 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 0Start 0 0 0 0Start 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 230 230 230 Stop 114 231 231 231 Stop 115
MCEI-040047 Page 16 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.7 Heat Flux Hot Channel Factor - FQ(XYZ) (TS 3.2.1) 2.7.1 FQ(XY,Z) steady-state limits are defined by the following relationships:
F RTP *K(Z)IP for P > 0.5 FQTP *K(Z)/0.5 for P < 0.5 where, P = (Thermal Power)/(Rated Power)
Note: The measured FQ(XY,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 2.7.5 and 2.7.6.
2.7.2 FR' = 2.50 x K(BU) 2.7.3 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 4.
2.7.4 K(BU) is the normalized FQ(XY,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:
L2.7.5 F6(XYZ)
- MQ(XYZ) 2.7.5 [F(XYZ)] UMT
- TILT where:
[FQ (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)]OP includes allowances for calculation and measurement uncertainties.
rJ, (X,Y,Z) = DesignpowerdistributionforFQ. F D (XY,Z) is provided in Table 4, Appendix A, for normal operating conditions and in
MCEI-0400-47 Page 17 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Table 5, Appendix A for power escalation testing during initial startup operation.
MQ(X,YZ) = Margin remaining in core location X,YZ 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)
D FQ(XYZ)
- MC(X,Y,Z) 2.7.6 [FQ(X,Y,Z)]'s =
UMT
- TILT where:
[FQ(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.
[FQ(X,Y,Z)]RPS includes allowances for calculation and measurement uncertainties.
FD(XYZ) = Design power distributions for FQ. FQ(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.
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) 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 18of33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report MT = Engineering Hot Channel Factor (MT = 1.03)
TILT = Peaking penalty that accounts for the peaking increase from an allowable quadrant power tilt ratio of 1.02. (TILT = 1.035) 2.7.7 KSLOPE = 0.0725 where:
KSLOPE is the adjustment to the K1 value from the OTAT trip setpoint required to compensate for each 1% that FQ' (XY,Z) exceeds [ FL (X,YZ)]
2.7.8 FQ(XY,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 19 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(XYZ) as a Function of Core Height for Mk-BW and Westinghouse RFA Fuel 1.2-1.0 -(0.0, 1.00) (12.0, 1.0) 0.8 0.6 0.4 0.2 0.0 I l l l I 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft)
MCEI-0400-47 Page 20 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Table 2 FQ(X,Y,Z) and FAII(XY) 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) r,,&,,z,YZ)
(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 bumups outside of the range of the table shall use a 2% penalty factor for both FQ(X,Y,Z) and FM&H(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 21 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.8 Nuclear Enthalpy Rise Hot Channel Factor - FAII(X,Y) (TS 3.2.2)
The 14AH steady-state limits referred to in Technical Specification 3.2.2 is defined by the following relationship.
2.8.1 [FQII(X,Y)]Lc= MARP (XY) * [ - I * (1.0 - P)]
where:
[FL(X,Y)]Ltc is defined as the steady-state, maximum allowed radial peak.
[FA}, (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.
p = Thermal Power Rated Thermal Power RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, Fs, (X,Y), exceeds its limit. RRH also is used to scale the MARP limits as a function of power per the [FL 1, (X,Y)]Lc equation. (RRH = 3.34 (0.0 < P < 1.0))
The following parameters are required for core monitoring per the Surveillance requirements of Technical Specification 3.2.2.
2.8.2 [FL (XY)VSURV - F& (X,Y)xM, 1 (X,Y) wh :R x TILT where:
[ F ,,, (X,Y)]s = Cycle dependent maximum allowable design peaking factor that ensures that the F,,1 (X,Y) limit will be preserved for operation within the LCO limits. [ FP,, (X,Y)] includes allowances for calculation-measurement uncertainty.
MCEI-0400-47 Page 22 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report D D F1S11 (X,Y) = Design radial power distribution for FAl. F 1H(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.
MMH(X,Y) 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= 1.04).
UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable MAH(XY).
TILT = Peaking penalty that accounts for the peak-ing increase for an allowable quadrant power tilt ratio of 1.02, (TILT = 1.035).
2.8.3 RRH = 3.34 where:
RRH = Thermal power reduction required to compensate for each 1% that the measured radial peak, F.SH (XY) exceeds its limit.
2.8.4 TRH = 0.04 where:
TRH = Reduction in the OTAT K1 setpoint required to compensate for each 1%
that the measured radial peak, Fm1 (X,Y) exceeds its limit.
2.8.5 Fw1 (X,Y) penalty factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.
2.9 Axial Flux Difference - AFD (TS 3.2.3) 2.9.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.
MCEI-040047 Page 23 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks (MARPS)
RFA MARPS Core Axial Peak-->
lit (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 1.847 1.882 1.947 1.992 1.974 2.068 2.090 2.049 1.972 1.900 1.778 1.315 1.246 1.2 1.843 1.879 1.938 1.992 1.974 2.068 2.054 2.012 1.935 1.862 1.785 1.301 1.224 2.4 1.846 1.876 1.931 1.981 1.974 2.068 2.025 1.981 1.903 1.832 1.757 1.468 1.456 3.6 1.843 1.869 1.920 1.964 1.974 2.068 2.005 1.968 1.892 1.820 1.716 1.471 1.431 4.8 1.838 1.868 1.906 1.945 1.974 2.006 1.945 1.925 1.862 1.802 1.725 1.326 1.285 6.0 1.834 1.856 1.891 1.921 1.946 1.934 1.878 1.863 1.802 1.747 1.673 1.384 1.317 7.2 1.828 1.845 1.871 1.893 1.887 1.872 1.809 1.787 1.732 1.681 1.618 1.316 1.277 8.4 1.823 1.829 1.847 1.857 1.816 1.795 1.739 1.722 1.675 1.630 1.551 1.247 1.211 9.6 1.814 1.812 1.809 1.792 1.738 1.724 1.678 1.665 1.621 1.578 1.492 1.191 1.137 10.8 1.798 1.784 1.761 1.738 1.697 1.682 1.626 1.605 1.558 1.512 1.430 1.149 1.097 11.4 1.789 1.765 1.725 1.684 1.632 1.614 1.569 1.557 1.510 1.466 1.392 1.113 1.060 Mk-BW MARPS Core Axiai Peak ->
Ht. (ft.) 1.05 1.1 1.2 1.3 1A 1.5 1.6 1.7 1.8 1.9 2.1 3.0 3.25 0.12 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 1.476 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 1.490 1.442 1.432 1.394 1.389 1.356 1.327 1.273 1.061 1.017
MCEI-040047 Page 24 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report Figure 5 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits co I-0 c,
Ed E-10 C,
Ak
-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 25 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.10 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.10.1 Overtemperature AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T'< 585.1IF Nominal RCS Operating Pressure P'- 2235 psig Overtemperature AT reactor trip setpoint KI < 1.1978 Overtemperature AT reactor trip heatup setpoint K2 = 0.0334/OF 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 T2 < 3 sec.
Time constant utilized in the lag compensator for AT T3 < 2.0 sec.
Time constants utilized in the lead-lag compensator T4> 28 sec.
for Tag r5 < 4 sec.
Time constant utilized in the measured Tav, lag T6 < 2.0 sec.
compensator f1 (Al) "positive" breakpoint = 19.0 %AI f1 (Al) "negative" breakpoint = N/A*
f1 (Al) "positive" slope = 1.769 %ATO/ %Al fl(Al) "negative" slope = NIA*
- The fl(Al) "negative" breakpoint and the fl(Al) "negative" slope are not applicable since the fl(Al) function is not required below the f1 (AT) "positive" breakpoint of 19.0% Al.
MCEI-040047 Page 26 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.10.2 Overpower AT Setpoint Parameter Values Parameter Value Nominal Tavg at RTP T" < 585.1OF Overpower AT reactor trip setpoint K44<1.0864 Overpower AT reactor trip Penalty K5 = 0.02/ 0F for increasing Tavg K5 = 0.0 for decreasing Tavg Overpower AT reactor trip heatup K6= 0.001 179/ 0 F forT> T' setpoint penalty coefficient K6= 0.0 for T < T" Time constants utilized in the lead-lag > 8 sec.
compensator for AT -2 < 3 sec.
Time constant utilized in the lag ¶3 < 2.0 sec.
compensator for AT Time constant utilized in the r6 < 2.0 sec.
measured Tavg lag compensator Time constant utilized in the rate-lag T7 > 5 sec.
controller for Ta.g f2 (AI) "positive" breakpoint = 35.0 %AI f2(AI) "negative" breakpoint = -35.0 %AI f2 (AI) "positive" slope = 7.0 %ATJ %AI f2(AD) "negative" slope = 7.0 %ATd %AI
MCEI-0400-47 Page 27 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.11 RCS Pressure, Temperature and Flow Limits for DNB (TS 3.4.1) 2.11.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.12 Accumulators (TS 3.5.1) 2.12.1 Boron concentration limits during modes 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 2.13 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.13.1 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 28 of 33 Revision 24 McGuire 2 Cycle 16 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 > 390,000 gpm
MCEI-0400-47 Page 29 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.14 Spent Fuel Pool Boron Concentration (TS 3.7.14) 2.14.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration. 2,675 ppm 2.15 Refueling Operations - Boron Concentration (TS 3.9.1) 2.15.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the Keff of the core will remain within the mode 6 reactivity requirement of Keff <
0.95.
Parameter Limit Minimum Boron concentration of the Reactor Coolant 2,675 ppm System, the refueling canal, and the refueling cavity.
MCEI-040047 Page 30 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.16 BoratedWaterSource-Shutdown (SLC 16.9.14) 2.16.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during mode 4 with any RCS cold leg temperature < 300 'F and modes 5 and 6.
Parameter Limit Boric Acid Tank minimum contained borated 10,599 gallons water volume 13.6% Level Note: When cycle bumup is > 430 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-040047 Page 31 of 33 Revision 24 McGuire 2 Cycle 16 Core Operating Limits Report 2.17 Borated Water Source - Operating (SLC 16.9.11) 2.17.1 Volume and boron concentrations for the Boric Acid Tank (BAT) and the Refueling Water Storage Tank (RWST) during modes 1, 2, 3, and mode 4 with all RCS cold leg temperature > 300 'F.
Parameter Limit Boric Acid Tank minimum contained borated 22,049 gallons water volume 38.0% 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 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-040047 Page 32 of 33 Revision 24 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 RCS Baron 35.0. .Concentration BAT Level (ppm) (%level) 0 < 300 37.0 300 < 500 33.0 30.0; 500 < 700 28.0 700 < 1000 23.0 1000 < 1300 13.6
>1300 8.7
>. 25.0
-20.0 I Acceptable Operation 15.0 _ __
10.0- --
Unacceptable Operation 5.0. - .. _ . . . .
0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 RCS Boron Concentration (ppmb)
MCEI-0400-47 Page 33 of 33 Revision 24 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 a need to access this information.