MNS-16-025, Core Operating Limits Report
| ML16089A232 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 03/23/2016 |
| From: | Capps S Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| MCC-1553.05-00-0627, MCEI-0400-326, MNS-16-025 | |
| Download: ML16089A232 (33) | |
Text
(,DUKE
~;ENERGY Serial No: MNS-16-025 March 23, 2016 U.S. Nuclear Regulatory Commission
- ATTN: Document Control Desk Washington, D.C. 20555 I
Subject:
Duke Energy Carolinas, LLC McGuire Nuclear Station Docket No. 50-369 Unit 1, Cycle 25, Revision 0 Core Operating Limits Report Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC. 28078 O: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Pursuant to McGuire Technical Specification 5.6.5.d, please find enClosed the McGuire Unit 1 Cycle 25, Revision 0, Core Operating Limits Report (COLR).
Questions regarding this submittal should be directed to P.T. Vu, Regulatory Affairs at (980) 875-4302.
Steven D. Capps Attachment www.duke-energy.com
U.S. Nuclear Regulatory Commission March 23, 2016 Page 2 xc.
G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 J. Zeiler 1
NRC Senior Resident Inspector McGuire Nuclear Station
McGuire Unit 1Cycle25 Core Operating Limits Report Revision 0 March 2016 Calculation Number: MCC-1553.05-00-0627 QA Condition 1 MCEI-0400-326 Page I of3 I Revision 0 The information presented in this repott has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
McGuire 1 Cycle 25 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and CR Tracking MCEI-0400-326 Page 2 of31 Revision 0 Revision 0 of the McGuire Unit 1 Cycle 25 COLR contains limits specific to the reload core.
This is no CR associated with this revision.
Implementation Schedule The McCjiuire Unit 1 Cycle 25 COLR requires the reload 50.59 to b~ approved prior to implementation and fuel loading.
Revision 0 may become effective any time during No MODE between Cycle 24 and 25 but must become effective prior to entering MODE 6 which starts Cycle 25.
The McGuire Unit 1 Cycle 25 COLR will cease to be effective during No MODE between Cycles 25 and 26.
Data files to be Implemented No data files are transmitted as part of this document.
Revision 0
MCEI-0400-326 Page 3of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report Effective Date March2016 REVISION LOG Pages Affected 1-31, 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 NjRC.
i
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 4 of31 Revision 0 1.0 Core Operating Limits Report This Core Operating Limits Rep01t (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Technical Specifications that reference this report are listed below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.
TS COLR NRC Approved Section Technical Specifications COLR Parameter Section Methodology (Section 1.1 Number) 2.1.l Reactor Core Safety Limits RCS Temperature and Pressure 2.1 6, 7, 8, 9, 10, 12, 15,
~-~f ~!~-~l~!!.'.' ___________ --------------
16 3.1.1 Shutdown Margin I
Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 3.1.3 e--M~~eE~!or I~~P~E~!!:I!:~-g_~_~f!i_c;!~~_t__ MTC 2.3
-~_7_, __ ~._G2l'!iJ§zJ2__
--~--**-------*------*-*------*--**----
3.1.4 Rod Group Alignment Limits Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 -*-
3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Shutdown Bank Insertion Limits 2.4 10, 12, 14, 15, 1-~----
3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Control Bank Insertion Limits 2.5
__ _l_Q_,_l_?._z_l_~L!~!--!_~----
~PI~ysi~s Tests Exc~ptions ----:=
- --*---*-----------*-****--------------*---~-*---------------------
3.1.8
,_§_hutdown Margin 2.2 6,7,8, 12, 14, 15, 16 3.2.1 Heat Flux Hot Channel Factor Fo 2.6 2, 4, 6, 7, 8, 9, 10, AFD 2.8 12, 15, 16 OT~T 2.9 Penalty Factors 2.6 3.2.2 Nuclear Enthalpy Rise Hot Channel F~H 2.7 2,4,6 7, 8, 9, Factor Penalty Factors 2.7 10, 12, 15, 16 3.2.3 Axial Flux Difference AFD 2.8
--~4, 6,_7, 8, l~L~
3.3.l Reactor Trip System Instrumentation OT~T 2.9 6, 7, 8, 9, 10, 12 OP~T 2.9
'16
~------ -------*-*---**--------------------------*--**--**-**-*--*-----*--*--*-------*----------*--*------*--*- -------*------
3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, Temperature and Flow 2.10 6, 7, 8, 9, 10, 12 Limits for DNB
f--*
-*-~-*-**--*---*-----*-* ----------- --
3.5.l Accumulators Max and Min Boron Cone.
2.11 6, 7, 8, 12, 14, 16 3.5.4 Refueling Water Storage Tank Max and Min Boron Cone.
2.12 6, 7, 8, 12, 14, 16 3.7.14
,_§_pent Fuel Pool Boron Concentration Min Boron Concentration 2.13 6, 7, 8, 12, 14, 16 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.14 6, 7, 8, 12, 14, 16 Concentration 5.6.5 Core Operating Limits Repmt Analytical Methods 1.1 None (COLR)
The Selected Licensee Commitments that reference this report are listed below SLC COLR NRC Approved Section Selected Licensee Commitment COLR Parameter Section Methodology (Section 1.1 Number) 16.9.14 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.15 6, 7, 8, 12, 14, 16 Source - Shutdown BAT/RWST 16.9.11 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.16 6, 7, 8, 12, 14, 16 Source - Operating BAT/RWST
-*-r-------------
16.9.7 Standby Shutdown System Standby Makeup Pump Water Supply 2.17 6, 7, 8, 12, 14, 16
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods MCEI-0400-326 Page 5 of31 Revision 0 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 Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," (W Proprietary). (Referenced in Duke Letter DPC-06-101)
Revision 1 July 1997
- 3. WCAP-10266-P-A, "The 1981 Version of Westinghouse Evaluation Model Using BASH Code, 0fj_ 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," (W Proprietary).
Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)
Report Date: March 1998
- 5. BA W-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
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods (continued)
MCEI-0400-326 Page 6 of31 Revision 0
Revision Sa Report Date: October 2012
- 7. DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision Oa 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-01," (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 TAC03" (DPC Proprietary).
Revision 0 Report Date: April 1995 Not Used
- 12. DPC-NE-2009-P A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 3a Report Date: September 2011
- 13. DPC-NE-1004-A, "Nuclear Design Methodology Using CASM0-3/SIMULATE-3P."
Revision la Report Date: January 2009 Not Used
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods (continued)
MCEI-0400-326 Page 7 of31 Revision 0
- 14. DPC-NF-2010-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-2011-PA, "Duke Power Company Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision la Report Date: June 2009
- 16. DPC-NE-1005-PA, "Nuclear Design Methodology Using CASM0-4 I SIMULATE-3 MOX",
(DPC Proprietary).
Revision 1 Report Date: November 12, 2008
- 17. DPC-NE-1007-P A, "Conditional Exemption of the EOC MTC Measurement Methodology,
(DPC and W Proprietary)
Revision 0 Report Date: April 2015
McGuire 1 Cycle 25 Core Operating Limits Report 2.0 Operating Limits MCEI-0400-326 Page 8 of31 Revision 0 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 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, TS 3.1.8)
I 2.2.1 -For TS 3.1.1, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 2 with Keff < 1.0 and in MODES 3 and 4.
2.2.2 For TS 3.1.1, SDM shall be greater than or equal to 1.0%.!lK/K in MODE 5.
2.2.3 For TS 3.1.4, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 1 and MODE2.
2.2.4 For TS 3.1.5, SDM shall be greater than or equal to 1.3%.!lK/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 greater than or equal to 1.3%.!lK/K in MODE 1 and MODE 2 with Keff~ 1.0.
2.2.6 For TS 3.1.8, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 2 during PHYSICS TESTS.
£70
£60
£50 640 lL L.-£30 C) ffi r
if) £2D 0
0:::
£10 600 590 580 0.0 McGuire 1 Cycle 25 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation MCEI-0400-326 Page 9 of31 Revision 0 DO NOT OPERATE IN THIS AREA 2400 psia 2100 psia 1945 psia ACCEPTABLE OPERATION 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
McGuire 1 Cycle 25 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.l Moderator Temperature Coefficient (MTC) Limits are:
MCEI-0400-326 Page 10 of31 Revision 0 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 LiKIK/°F.
BOC, ARO, RTP MTC shall be less negative than the -4.3E-04 LiKIK/°F lower MTC limit.
2.3.2 300 ppm MTC Surveillance Limit is:
Measured 300 PPM ARO, equilibrium RTP MTC shall 1be less negative than or equal to -3.65E-04 LiK/K/°F.
2.3.3 The Revised Predicted near-BOC 300 ppm ARO RTP MTC shall be calculated using the procedure contained in DPC-NE-1007-PA If the Revised Predicted MTC is less negative than or equal to the 300 ppm SR 3.1.3.2 Surveillance Limit, and all benchmark data contained in the surveillance procedure is satisfied, then an MTC measurement in accordance with SR 3.1.3.2 is not required to be performed.
2.3.4 60 PPM MTC Surveillance Limit is:
Measured 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -4.125E-04 LiK/K/°F.
Where:
BOC = Beginning of Cycle (bumup corresponding to 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.
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.
McGuire 1 Cycle 25 Core Operating Limits Report Figure 2 MCEI-0400-326 Page 11of31 Revision 0 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 Unacceptable Operation Acceptable Operation 0.1 0.0 0
10 20 30 40 50' 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
231 220 200
,-._ =
~ 180
=
I.
'O
- E 160
~
IS. 140
~
~
= 120 Q :e., 100 Q
~ =
Q 80 t:
~
., = 60
'O
~ 40 20 0
McGuire 1 Cycle 25 Core Operating Limits Report Figure 3 MCEI-0400-326 Page 12 of31 Revision 0 Control Bank Insertion Limits Versus Percent Rated Thermal Power F 11 W"hd Uy It f~~
(Maximum=23 l)
~
~
~
/
r
/
/
/
/
/
/
Fully Withdrawn v
/
1 Contro!BankB :
(Minimum=222) v
/
/
/
/
1(100%, 161) F
/
E:l (0%, 163)
/
I/
/
/
/
/
/
/
Contro!BankC
/
/
v
/
/
/
/
/
/
/
/
/
/
/
- Contro!BankD
/
I/
/
/
/
/
/
H co%,47) v
/
/
/
>-- [jFully Inserted
/
~
(30%,0)
/
I I
I I/
0 10 20 30 40 so 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 RIL = 2.3(P)- 69 {30 ::;P::; JOO}
Bank CC RIL = 2.3(P) +47
{O ::;P::; 76.J} for CC RIL = 222 {76.J < P::; JOO}
Bank CB RIL = 2.3(P) +J63 {O ::;P ::;25. 7) for CB RIL = 222 {25. 7 < P::; JOO}
where P = %Rated Thermal Power NOTES: 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.
McGuire 1 Cycle 25 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully \\Vithdrawu at 222 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 116 222 Stop 222 222 222 222 0
0 Start 106 116 222 Stop 222 222 0
0 0
0 Start 106 116 222 Stop 0
0 0
0 0
0 Start 106 Fully Withdrawn at 224 Steps Control Control Control C':ontrol Bank A Bank B Bank C Bank D 0 Start 116 224 Stop 224 224 224 224 0
0 Start 108 116 224 Stop 224 224 0
0 0
0 Start 108 116 224 Stop 0
0 0
0 0
0 Start 108 Fully Withdrawn at 226 Steps Control Control Control Control Bank A Bank B Bank C Bank D OStart
()
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 Bank A Bank B Bank C Bank D 0 Start 116 228 Stop 228 228 228 228 0
0 Start 112 116 228 Stop 228 228 0
0 0
0 Start 112 116 228 Stop 0
0 0
0 0
0 Start 112 Fully Withdrawn at 230 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 Fully Withdrawn at 223 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 116 223 Stop 223 223 223 223 0
0 Start 107 116 223 Stop 223 223 0
0 0
0 Start 107 116 223 Stop 0
0 0
0 0
0 Start 107 Fully Withdrawn at 225 Steps Control Bank A 0 Start 116 225 Stop 225 225 225 225 Control Control BankB BankC 0
0 Start 109 116 225 Stop 225 225 0
0 0
0 Start 109 116 225 Stop Control BankD 0
0 0
0 0
0 Start 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
0 227 Stop 111 0
0 227 116 0 Start 0
227 227 Stop 111 0
227 227 116 0 Start 227 227 227 Stop 111 Fully Withdrawn at 229 Steps Control Control BankA BankB 0 Start 116 229 Stop 229 229 229 229 0
0 Start 113 116 229 Stop, 229 229 Control BankC 0
0 0
0 Start 113 116 229 Stop Control BankD 0
0 0
0 0
0 Start 113 Fully Withdrawn at 231 Steps Control Control BankA BankB Control BankC Control BankD 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-0400-326 Page 13 of31 Revision 0
MCEI-0400-326 Page 14 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor-FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:
- where, F ~TP *K(Z)/P F ~TP *K(Z)/0.5 P = (Thermal Power)/(Rated Power) for P > 0.5 for P :S 0.5 Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5%
1 to account for measurement uncertainty when comparing against the LCO limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined for COLR Sections 2.6.5 and 2.6.6.
RTP 2.6.2 F Q
= 2.70 x K(BU) 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height.. K(Z) for Westinghouse RF A fuel is provided in Figure 4.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. F~TP with the K(BU) penalty for Westinghouse RF A 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 F~(X,Y,Z)
- Mq(X,Y,Z) 2.6.5
[FQ(X,Y,Z)]OP =
UMT *MT* TILT where:
[Ft (X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
Ft (X,Y,Z) 0 P includes allowances for calculation and measurement uncertainties.
Design power distribution for F0. Ft (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.
MCEI-0400-326 Page 15 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report M0(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 Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
UMT MT TILT Total Peak Measurement Uncertainty. (UMT = 1.05)
Engineering Hot Channel Factor. (MT= 1.03)
Peaking penalty that acc?.unts for allowable quadrant power tilt ratio of 1.02. (TILT= 1.035)
L RPS F~(X,Y,Z)
- Mc(X,Y,Z) 2*6*6
[FQ(X,Y,Z)]
=
UMT *MT* TILT where:
[F~(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
[F~(X,Y,Z)]RPS includes allowances for calculation and measurement uncertainties.
D FQ(X,Y,Z)
Defined in Section 2.6.5.
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 Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operations.
UMT Defined in Section 2.6.5.
MT Defined in Section 2.6.5.
TILT Defined in Section 2.6.5.
McGuire 1 Cycle 25 Core Operating Limits Report 2.6.7 KSLOPE = 0.0725 where:
MCEI-0400-326 Page 16 of31 Revision 0 KS LOPE =Adjustment to K 1 value from OT Ll T trip setpoint required to RPS compensate for each I% FQM (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.
McGuire 1 Cycle 25 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel MCEI-0400-326 Page 17 of31 Revision 0 1.200 ~-------------------------------,
(0.0, 1.00)
(4.0, 1.00) 1.000.,_ _______
1 0.800
~ 0.600
~
0.400 0.200 0.000 0.0 Core Height
{ft) 0.0
- S4
>4 12.0 2.0 (4.0, 0.9259)
K(Z) 1.000 1.000 0.9259 0.9259 4.0 6.0 Core Height (ft)
(12.0, 0.9259) 8.0 10.0 12.0
McGuire 1 Cycle 25 Core Operating Limits Report Table 2 FQ(X,Y,Z) and F,rn(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burn up (EFPD) 4 12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 465 475 497 502 507 517 527 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 2.00 F'-rn(X,Y)
Penalty Factor (%)
2.00 2.00 2.00 2.00 2.09 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 burnups outside the range of the table shall use a 2%
penalty factor for both FQ(X,Y,Z) and F 1rn(X,Y) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
MCEI-0400-326 Page 18 of31 Revision 0
MCEI-0400-326 Page 19 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report
- 2. 7 Nuclear Enthalpy Rise Hot Channel Factor - F MI(X,Y) (TS 3.2.2)
F LlH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.
where:
[Fk8 (X, Y)tco is the steady-state, maximum allowed radial peak and includes I
allowances for calculation/measurement uncertaint~.
MARP(X,Y) =
Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in Table 3.
Thermal Power p =
Rated Thermal Power RRH =Thermal Power reduction required to compensate for each 1 % measured radial peak, F!!r (X,Y), exceeds the limit.
(RRH = 3.34, 0.0 < P :::; 1.0)
The following parameters are required for core monitoring per the surveillance requirements of Technical Specification 3.2.2.
L SURV -
FfH (X, Y)
- M l>H (X, Y) 2.7.2
[F,.,8 (X,Y)]
UMR *TILT where:
SURV
[Fktt (X,Y)]
=
Cycle dependent maximum allowable design peaking factor that ensures F Llli(X, Y) limit is not exceeded for operation
. h" h
d l".
L (
SURV wit mt e AFD, RIL, an QPTR im1ts. FM X,Y) includes allowances for calculation/measurement uncertainty.
F~H (X,Y) = Design radial power distribution for F t>H* F~H (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.
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 20 of31 Revision 0 Mti.ttCX,Y) =Margin remaining in core location X,Y relative to Operational DNB limits in the transient power distribution.
MLiH(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.
UMR
=Uncertainty value for measured radial peaks (UMR = 1.0).
UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable M,rn(X,Y).
TILT =Defined in Section 2.6.5.
I 2.7.3 RRH is defined in Section 2.7.1.
2.7.4 TRH = 0.04 where:
TRH = Reduction in OTLiT K1 setpoint required to compensate for each 1 %
measured radial peak, F~ (X,Y) exceeds its limit.
2.7.5 F,rn(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.
2.8 Axial Flux Difference - AFD (TS 3.2.3) 2.8.1 Axial Flux Difference (AFD) Limits are provided in Figure 5.
Core Height ft)
I.OS 1.1 0.12 1.8092 1.8553 1.20 l.8102 1.8540 2.40 l.8093 l.8525 3.60 1.8098 l.8514 4.80 1.8097 l.8514 6.00 1.8097 l.8514 7.20 1.8070 1.8438 8.40 1.8073 1.8319 9.60 1.8072 1.8102 10.80 1.7980 1.7868 11.40 1.7892 1.7652 McGuire 1 Cycle 25 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks'(MARPs)
RF A Fuel MARPs 100% Full Power Axial Peak 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9248 1.9146 1.9179 2.0621 2.0498 2.0090 l.9333 1.9248 1.9146 1.9179 2.1073 2.0191 1.9775 l.9009 1.9312 1.9146 l.9179 2.0735 l.9953 l.9519 l.8760 1.9204 1.9146 l.9179 i 2.0495 1.9656 1.9258 1.8524 1.9058 1.9146 1.9179 2.0059 1.9441 1.9233 1.8538 1.8921 1.9212 1.9179 1.9336 l.8798 1.8625 1.8024 l.8716 l.8930 1.8872 1.8723 1.8094 1.7866 l.7332 1.8452 l.8571 1.8156 1.7950 l.7359 1.7089 1.6544 1.8093 1.7913 l.7375 1.7182 1.6572 1.6347 1.5808 1.7611 l.7163 l.6538 1.6315 1.5743 1.5573 1.5088 1.7250 l.6645 1.6057 1.5826 1.5289 1.5098 l.4637 1.9 l.8625 1.8306 1.8054 l.7855 l.7836 1.7472 1.6812 1.6010 l.5301 1.4624 1.4218 MCEI-0400-326 Page 21 of31 Revision 0 2.1 3.0 3.25 1.7780 l.3151 l.2461 1.7852 l.3007 l.2235 1.7320 l.4633 1.4616 1.6996 l.4675 l.3874 i 1.6714 1.2987 1.2579 1.6705 l.3293 1.2602 1.5982 1.2871 1.2195 l.5127 1.2182 l.1578 l.4444 l.1431 1.0914 1.3832 l.1009 1.0470 1.3458 1.0670 1.0142
~
0
~
~
8.....
..c:
E-<
"O.. -
cu IZ 0 -=
~
-50 McGuire 1 Cycle 25 Core Operating Limits Report Figure 5 MCEI-0400-326 Page 22 of31 Revision 0 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-18, 100)
(+10, 100)
Unacc,eptable Operation 90 Unacceptable Operation 80 Acceptable Operation 70 I
60 50
(-36, 50)
(+21, 50) 40 30 20 10
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I)
NOTE: Compliance with Technic'al Specification 3.2.l may require more restrictive AFD limits. Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 23 of31 Revision 0 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature h.T Setpoint Parameter Values Parameter Nominal Tavg at RTP Nominal RCS Operating Pressure Overtemperature /1 T reactor trip setpoint ++
Overtemperature 11T reactor trip heatup setpoint penalty coefficient Overtemperature 11T reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for 11T Time constant utilized in the lag compensator for /1 T Time constants utilized in the lead-lag compensator for Tavg Time constant utilized in the measured Tavg lag compensator f 1 (111) "positive" breakpoint fi (111) "negative" breakpoint fi (111) "positive" slope fi (111) "negative" slope Nominal Value T' :S 585.1 °F P' = 2235 psig Kl :S 1.1978 K2 = 0.0334/'F KJ = 0.001601/psi
- 1 2: 8 sec.
- 2 :S 3 sec.
- 3 :S 2 sec.
- 4 2: 28 sec.
- 5 :S 4 sec.
"6 :S 2 sec.
= 19.0 %111
=NIA*
= 1.769 %11Tol %111
=NIA*
fi (.1I) negative breakpoints and slopes for OT.1T are less restrictive than the OP.1T f2(.1I) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits, OP.1T f2(.1I) limits will result in a reactor trip before OT.1T fi (.1I) limits are reached. This makes implementation of an OT.1T fi (.11) negative breakpoint and slope unnecessary.
++.1T0 is assumed to be renormalized to 100% RTP following the MUR power uprate.
MCEI-0400-326 Page 24 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.9.2 Overpower tiT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower L'lT reactor trip setpoint ++
Overpower L'l T reactor trip penalty Overpower L'lT reactor trip heatup setpoint penalty coefficient Time constants utilized in the lead-lag compensator for L'l T Time constant utilized in the lag compensator for L'l T Time constant utilized in the measured T avg lag compensator Time constant utilized in the rate-lag controller for Tavg fz(M) "positive" breakpoint fz(M) "negative'; breakpoint fz(M) "positive" slope fz(M). "negative" slope Nominal Value T"::::; 585.1 °P Ki::::; 1.0864 Ks= 0.02 I 0P for increasing Tavg Ks = 0.00 I 0 P for decreasing Tavg Ki6 = 0.001179/
0 P for T > T" K6 = 0.0 for T::::; T"
- i ~ 8 sec.
- 2 ::::; 3 sec.
- 3 ::::; 2 sec.
- 6 ::::; 2 sec.
= 35.0 %L'll
=-35.0 %M
++ LiT0 is assumed to be renormalized to 100% RTP following the MUR power uprate.
McGuire 1 Cycle 25 Core Operating Limits Report 2.10 RCS Pressure, Temperature and Flow DNB Limits (TS 3.4.1)
MCEl-0400-326 Page 25 of31 Revision 0 2.10.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.11 Accumulators (TS 3.5.1) 2.11.1 Boron concentration limits during MODES 1and2, and MODE 3 with RCS pressure > 1000 psi:
Parameter Applicable Bumuq Limit Accumulator minimum-boron concentration.
0 -200 EFPD 2,475 ppm Accumulator minimum boron concentration.
200.1 - 250 EFPD 2,475 ppm Accumulator minimum boron concentration.
250.l - 300 EFPD 2,475 ppm Accumulator minimum boron concentration.
300.1 - 350 EFPD 2,404 ppm Accumulator minimum boron concentration.
350.1 - 400 EFPD 2,294 ppm Accumulator minimum boron concentration.
400.1 - 450 EFPD 2,219 ppm Accumulator minimum boron concentration.
450.1 - 497 EFPD 2,148 ppm Accumulator minimum boron concentration.
497.l - 517 EFPD 2,079 ppm Accumulator minimum boron concentration.
517.1-527 EFPD 2,046 ppm Accumulator maximum boron concentration.
0-527 EFPD 2,875 ppm 2.12 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.12.1 Boron concentration limits during MODES 1, 2, 3, and 4:
Parameter R WST minimum boron concentration.
2,675 ppm RWST maximum boron concentration.
2,875 ppm
McGuire 1 Cycle 25 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable Parameter Indication Channels
- 1. Indicated RCS Average Temperature meter 4
meter 3
computer 4
computer 3
- 2. Indicated Pressurizer Pressure meter 4
meter 3
computer 4
computer 3
- 3. RCS Total Flow Rate MCEI-0400-326 Page 26 of31 Revision 0 Limits
- S 587.2 °F
- S 586.9 °F i
- S 587.7 °F
- S 587.5 °F 2:: 2212.3 psig 2:: 2215.0 psig 2:: 2209.1 psig 2:: 2211.3 psig 2:: 390,000 gpm*
- Note: The RCS minimum coolant flow rate assumed in the licensing analyses for the Ml C25 core is 388,000 gpm. However, the flow is set at 390,000 gpm, which is conservative.
McGuire 1 Cycle 25 Core Operating Limits Report 2.13 Spent Fuel Pool Boron Concentration (TS 3.7.14)
MCEI-0400-326 Page 27 of31 Revision 0 2.13.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter 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 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 Kerrremains within the MODE 6 reactivity requirement ofKeff:'S 0.95.
Parameter Minimum boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.
2,675 ppm
MCEI-0400-326 Page 28 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.15 Boration Systems 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 NOTE: When cycle burnup is ~ 475 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.
I BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 68°F BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9.14)
RWST minimum boron concentration Volume of2,675 ppm boric acid solution required to maintain SDM at 68 °F R WST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9.14) 7,000 ppm 2,300 gallons 10,599 gallons (13.6%)
2,675 ppm 8,200 gallons 47,700 gallons (41 inches)
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 29 of31 Revision 0 2.16 Boration Systems Borated Water Source - Operating (SLC 16.9.11) 2.17 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 temperatures> 300°F.*
- NOTE: The SLC 16.9.11 applicability is down to MODE 4 temperatures of
> 300°F. The minimum volumes calculated support cooldown to 200°F to satisfy UFSAR Chapter 9 requirements.
Parameter NOTE: When -cycle burnup is ~ 475 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.
BAT minimum boron concentration 7,000 ppm Volume of7,000 ppm boric acid solution required 13,750 gallons to maintain SDM at 300°F BAT Minimum Shutdown Volume (Includes the 22,049 gallons additional volumes listed in SLC 16.9.11)
(38.0%)
R WST minimum boron concentration 2,675 ppm RWST maximum boron concentration (TS 3.5.4) 2,875 ppm Volume of2,675 ppm boric acid solution required 57,107 gallons to maintain SDM RWST Minimum Shutdown Volume (Includes the 96,607 gallons additional volumes listed in SLC 16.9.11)
(103.6 inches)
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.
2,675 ppm
McGuire 1 Cycle 25 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is 2: 475 EFPD)
MCEI-0400-326 Page 30 of31 Revision 0 This figure includes additional volumes listed in SLC 16.9.11 and 16.9.14 40.0 ~~-~-~!
--i-~--1-~--.-----.--~--.-----.--~--.
I I
35.o --- -
j-----o--~--- --j---T -
Concentration BAT Level i
I 1
(ppm)
(%level) i I
o < 300 37.o I
I I
-l T ---i-- -- i
~~~ : ~~~ -~¥a--
i 700 < 1000 23.0 I
I 1000<1300 13.6 I
I
>1300 s.1
(' *-***.... r '
- 1
...,...I ____
.,.--~
~
20.0 -
---- --*---l----! ------!-----*-~-----~------~- -- _; __ --L---
~
I Accepta~le
'I I
1
~
~ 15.0 ------
i----- i ---- ___ i_ ___ 1----,,;-----1-*-t* ---
f l
__..;. _____ - ~------*_,;_____
1
- -r*------ -- --- ---
1-----r- -- 1-- --- ---- -
'*' I Un:ooprabm Opo 1~uon..
i _
10.0 I
I '
0.0+---+---+----ic--+----+---+----iC--+----i----+--r---r---i----!
0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 RCS Boron Concentration (ppmb)
McGuire 1 Cycle 25 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors MCEI-0400-326 Page 31 of31 Revision 0 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire I Cycle 25 Maneuvering Analysis calculation file, MCC-1553.05-00-0622. 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 controls this information via computer files and should be contacted ifthere is a need to access this information.
Appendix A is included in the COLR copy transmitted to the +/--ffi.c.
(,DUKE
~;ENERGY Serial No: MNS-16-025 March 23, 2016 U.S. Nuclear Regulatory Commission
- ATTN: Document Control Desk Washington, D.C. 20555 I
Subject:
Duke Energy Carolinas, LLC McGuire Nuclear Station Docket No. 50-369 Unit 1, Cycle 25, Revision 0 Core Operating Limits Report Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC. 28078 O: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Pursuant to McGuire Technical Specification 5.6.5.d, please find enClosed the McGuire Unit 1 Cycle 25, Revision 0, Core Operating Limits Report (COLR).
Questions regarding this submittal should be directed to P.T. Vu, Regulatory Affairs at (980) 875-4302.
Steven D. Capps Attachment www.duke-energy.com
U.S. Nuclear Regulatory Commission March 23, 2016 Page 2 xc.
G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 J. Zeiler 1
NRC Senior Resident Inspector McGuire Nuclear Station
McGuire Unit 1Cycle25 Core Operating Limits Report Revision 0 March 2016 Calculation Number: MCC-1553.05-00-0627 QA Condition 1 MCEI-0400-326 Page I of3 I Revision 0 The information presented in this repott has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
McGuire 1 Cycle 25 Core Operating Limits Report Implementation Instructions for Revision 0 Revision Description and CR Tracking MCEI-0400-326 Page 2 of31 Revision 0 Revision 0 of the McGuire Unit 1 Cycle 25 COLR contains limits specific to the reload core.
This is no CR associated with this revision.
Implementation Schedule The McCjiuire Unit 1 Cycle 25 COLR requires the reload 50.59 to b~ approved prior to implementation and fuel loading.
Revision 0 may become effective any time during No MODE between Cycle 24 and 25 but must become effective prior to entering MODE 6 which starts Cycle 25.
The McGuire Unit 1 Cycle 25 COLR will cease to be effective during No MODE between Cycles 25 and 26.
Data files to be Implemented No data files are transmitted as part of this document.
Revision 0
MCEI-0400-326 Page 3of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report Effective Date March2016 REVISION LOG Pages Affected 1-31, 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 NjRC.
i
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 4 of31 Revision 0 1.0 Core Operating Limits Report This Core Operating Limits Rep01t (COLR) has been prepared in accordance with requirements of Technical Specification 5.6.5. Technical Specifications that reference this report are listed below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.
TS COLR NRC Approved Section Technical Specifications COLR Parameter Section Methodology (Section 1.1 Number) 2.1.l Reactor Core Safety Limits RCS Temperature and Pressure 2.1 6, 7, 8, 9, 10, 12, 15,
~-~f ~!~-~l~!!.'.' ___________ --------------
16 3.1.1 Shutdown Margin I
Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 3.1.3 e--M~~eE~!or I~~P~E~!!:I!:~-g_~_~f!i_c;!~~_t__ MTC 2.3
-~_7_, __ ~._G2l'!iJ§zJ2__
--~--**-------*------*-*------*--**----
3.1.4 Rod Group Alignment Limits Shutdown Margin 2.2 6, 7, 8, 12, 14, 15, 16 -*-
3.1.5 Shutdown Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Shutdown Bank Insertion Limits 2.4 10, 12, 14, 15, 1-~----
3.1.6 Control Bank Insertion Limit Shutdown Margin 2.2 2, 4, 6, 7, 8, 9, Control Bank Insertion Limits 2.5
__ _l_Q_,_l_?._z_l_~L!~!--!_~----
~PI~ysi~s Tests Exc~ptions ----:=
- --*---*-----------*-****--------------*---~-*---------------------
3.1.8
,_§_hutdown Margin 2.2 6,7,8, 12, 14, 15, 16 3.2.1 Heat Flux Hot Channel Factor Fo 2.6 2, 4, 6, 7, 8, 9, 10, AFD 2.8 12, 15, 16 OT~T 2.9 Penalty Factors 2.6 3.2.2 Nuclear Enthalpy Rise Hot Channel F~H 2.7 2,4,6 7, 8, 9, Factor Penalty Factors 2.7 10, 12, 15, 16 3.2.3 Axial Flux Difference AFD 2.8
--~4, 6,_7, 8, l~L~
3.3.l Reactor Trip System Instrumentation OT~T 2.9 6, 7, 8, 9, 10, 12 OP~T 2.9
'16
~------ -------*-*---**--------------------------*--**--**-**-*--*-----*--*--*-------*----------*--*------*--*- -------*------
3.4.1 RCS Pressure, Temperature and Flow RCS Pressure, Temperature and Flow 2.10 6, 7, 8, 9, 10, 12 Limits for DNB
f--*
-*-~-*-**--*---*-----*-* ----------- --
3.5.l Accumulators Max and Min Boron Cone.
2.11 6, 7, 8, 12, 14, 16 3.5.4 Refueling Water Storage Tank Max and Min Boron Cone.
2.12 6, 7, 8, 12, 14, 16 3.7.14
,_§_pent Fuel Pool Boron Concentration Min Boron Concentration 2.13 6, 7, 8, 12, 14, 16 3.9.1 Refueling Operations - Boron Min Boron Concentration 2.14 6, 7, 8, 12, 14, 16 Concentration 5.6.5 Core Operating Limits Repmt Analytical Methods 1.1 None (COLR)
The Selected Licensee Commitments that reference this report are listed below SLC COLR NRC Approved Section Selected Licensee Commitment COLR Parameter Section Methodology (Section 1.1 Number) 16.9.14 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.15 6, 7, 8, 12, 14, 16 Source - Shutdown BAT/RWST 16.9.11 Boration Systems - Borated Water Borated Water Volume and Cone. for 2.16 6, 7, 8, 12, 14, 16 Source - Operating BAT/RWST
-*-r-------------
16.9.7 Standby Shutdown System Standby Makeup Pump Water Supply 2.17 6, 7, 8, 12, 14, 16
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods MCEI-0400-326 Page 5 of31 Revision 0 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 Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," (W Proprietary). (Referenced in Duke Letter DPC-06-101)
Revision 1 July 1997
- 3. WCAP-10266-P-A, "The 1981 Version of Westinghouse Evaluation Model Using BASH Code, 0fj_ 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," (W Proprietary).
Revision: Volume 1 (Revision 2) and Volumes 2-5 (Revision 1)
Report Date: March 1998
- 5. BA W-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
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods (continued)
MCEI-0400-326 Page 6 of31 Revision 0
Revision Sa Report Date: October 2012
- 7. DPC-NE-3001-PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
Revision Oa 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-01," (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 TAC03" (DPC Proprietary).
Revision 0 Report Date: April 1995 Not Used
- 12. DPC-NE-2009-P A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 3a Report Date: September 2011
- 13. DPC-NE-1004-A, "Nuclear Design Methodology Using CASM0-3/SIMULATE-3P."
Revision la Report Date: January 2009 Not Used
McGuire 1 Cycle 25 Core Operating Limits Report 1.1 Analytical Methods (continued)
MCEI-0400-326 Page 7 of31 Revision 0
- 14. DPC-NF-2010-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-2011-PA, "Duke Power Company Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision la Report Date: June 2009
- 16. DPC-NE-1005-PA, "Nuclear Design Methodology Using CASM0-4 I SIMULATE-3 MOX",
(DPC Proprietary).
Revision 1 Report Date: November 12, 2008
- 17. DPC-NE-1007-P A, "Conditional Exemption of the EOC MTC Measurement Methodology,
(DPC and W Proprietary)
Revision 0 Report Date: April 2015
McGuire 1 Cycle 25 Core Operating Limits Report 2.0 Operating Limits MCEI-0400-326 Page 8 of31 Revision 0 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 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, TS 3.1.8)
I 2.2.1 -For TS 3.1.1, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 2 with Keff < 1.0 and in MODES 3 and 4.
2.2.2 For TS 3.1.1, SDM shall be greater than or equal to 1.0%.!lK/K in MODE 5.
2.2.3 For TS 3.1.4, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 1 and MODE2.
2.2.4 For TS 3.1.5, SDM shall be greater than or equal to 1.3%.!lK/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 greater than or equal to 1.3%.!lK/K in MODE 1 and MODE 2 with Keff~ 1.0.
2.2.6 For TS 3.1.8, SDM shall be greater than or equal to 1.3%.!lK/K in MODE 2 during PHYSICS TESTS.
£70
£60
£50 640 lL L.-£30 C) ffi r
if) £2D 0
0:::
£10 600 590 580 0.0 McGuire 1 Cycle 25 Core Operating Limits Report Figure 1 Reactor Core Safety Limits Four Loops in Operation MCEI-0400-326 Page 9 of31 Revision 0 DO NOT OPERATE IN THIS AREA 2400 psia 2100 psia 1945 psia ACCEPTABLE OPERATION 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power
McGuire 1 Cycle 25 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.l Moderator Temperature Coefficient (MTC) Limits are:
MCEI-0400-326 Page 10 of31 Revision 0 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 LiKIK/°F.
BOC, ARO, RTP MTC shall be less negative than the -4.3E-04 LiKIK/°F lower MTC limit.
2.3.2 300 ppm MTC Surveillance Limit is:
Measured 300 PPM ARO, equilibrium RTP MTC shall 1be less negative than or equal to -3.65E-04 LiK/K/°F.
2.3.3 The Revised Predicted near-BOC 300 ppm ARO RTP MTC shall be calculated using the procedure contained in DPC-NE-1007-PA If the Revised Predicted MTC is less negative than or equal to the 300 ppm SR 3.1.3.2 Surveillance Limit, and all benchmark data contained in the surveillance procedure is satisfied, then an MTC measurement in accordance with SR 3.1.3.2 is not required to be performed.
2.3.4 60 PPM MTC Surveillance Limit is:
Measured 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -4.125E-04 LiK/K/°F.
Where:
BOC = Beginning of Cycle (bumup corresponding to 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.
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.
McGuire 1 Cycle 25 Core Operating Limits Report Figure 2 MCEI-0400-326 Page 11of31 Revision 0 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 Unacceptable Operation Acceptable Operation 0.1 0.0 0
10 20 30 40 50' 60 70 80 90 100 Percent of Rated Thermal Power NOTE: Compliance with Technical Specification 3.1.3 may require rod withdrawal limits.
Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
231 220 200
,-._ =
~ 180
=
I.
'O
- E 160
~
IS. 140
~
~
= 120 Q :e., 100 Q
~ =
Q 80 t:
~
., = 60
'O
~ 40 20 0
McGuire 1 Cycle 25 Core Operating Limits Report Figure 3 MCEI-0400-326 Page 12 of31 Revision 0 Control Bank Insertion Limits Versus Percent Rated Thermal Power F 11 W"hd Uy It f~~
(Maximum=23 l)
~
~
~
/
r
/
/
/
/
/
/
Fully Withdrawn v
/
1 Contro!BankB :
(Minimum=222) v
/
/
/
/
1(100%, 161) F
/
E:l (0%, 163)
/
I/
/
/
/
/
/
/
Contro!BankC
/
/
v
/
/
/
/
/
/
/
/
/
/
/
- Contro!BankD
/
I/
/
/
/
/
/
H co%,47) v
/
/
/
>-- [jFully Inserted
/
~
(30%,0)
/
I I
I I/
0 10 20 30 40 so 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 RIL = 2.3(P)- 69 {30 ::;P::; JOO}
Bank CC RIL = 2.3(P) +47
{O ::;P::; 76.J} for CC RIL = 222 {76.J < P::; JOO}
Bank CB RIL = 2.3(P) +J63 {O ::;P ::;25. 7) for CB RIL = 222 {25. 7 < P::; JOO}
where P = %Rated Thermal Power NOTES: 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.
McGuire 1 Cycle 25 Core Operating Limits Report Table 1 Control Bank Withdrawal Steps and Sequence Fully \\Vithdrawu at 222 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 116 222 Stop 222 222 222 222 0
0 Start 106 116 222 Stop 222 222 0
0 0
0 Start 106 116 222 Stop 0
0 0
0 0
0 Start 106 Fully Withdrawn at 224 Steps Control Control Control C':ontrol Bank A Bank B Bank C Bank D 0 Start 116 224 Stop 224 224 224 224 0
0 Start 108 116 224 Stop 224 224 0
0 0
0 Start 108 116 224 Stop 0
0 0
0 0
0 Start 108 Fully Withdrawn at 226 Steps Control Control Control Control Bank A Bank B Bank C Bank D OStart
()
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 Bank A Bank B Bank C Bank D 0 Start 116 228 Stop 228 228 228 228 0
0 Start 112 116 228 Stop 228 228 0
0 0
0 Start 112 116 228 Stop 0
0 0
0 0
0 Start 112 Fully Withdrawn at 230 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 Fully Withdrawn at 223 Steps Control Control Control Control Bank A Bank B Bank C Bank D 0 Start 116 223 Stop 223 223 223 223 0
0 Start 107 116 223 Stop 223 223 0
0 0
0 Start 107 116 223 Stop 0
0 0
0 0
0 Start 107 Fully Withdrawn at 225 Steps Control Bank A 0 Start 116 225 Stop 225 225 225 225 Control Control BankB BankC 0
0 Start 109 116 225 Stop 225 225 0
0 0
0 Start 109 116 225 Stop Control BankD 0
0 0
0 0
0 Start 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
0 227 Stop 111 0
0 227 116 0 Start 0
227 227 Stop 111 0
227 227 116 0 Start 227 227 227 Stop 111 Fully Withdrawn at 229 Steps Control Control BankA BankB 0 Start 116 229 Stop 229 229 229 229 0
0 Start 113 116 229 Stop, 229 229 Control BankC 0
0 0
0 Start 113 116 229 Stop Control BankD 0
0 0
0 0
0 Start 113 Fully Withdrawn at 231 Steps Control Control BankA BankB Control BankC Control BankD 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-0400-326 Page 13 of31 Revision 0
MCEI-0400-326 Page 14 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.6 Heat Flux Hot Channel Factor-FQ(X,Y,Z) (TS 3.2.1) 2.6.1 FQ(X,Y,Z) steady-state limits are defined by the following relationships:
- where, F ~TP *K(Z)/P F ~TP *K(Z)/0.5 P = (Thermal Power)/(Rated Power) for P > 0.5 for P :S 0.5 Note: The measured FQ(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5%
1 to account for measurement uncertainty when comparing against the LCO limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined for COLR Sections 2.6.5 and 2.6.6.
RTP 2.6.2 F Q
= 2.70 x K(BU) 2.6.3 K(Z) is the normalized FQ(X,Y,Z) as a function of core height.. K(Z) for Westinghouse RF A fuel is provided in Figure 4.
2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup. F~TP with the K(BU) penalty for Westinghouse RF A 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 F~(X,Y,Z)
- Mq(X,Y,Z) 2.6.5
[FQ(X,Y,Z)]OP =
UMT *MT* TILT where:
[Ft (X,Y,Z)]OP = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) LOCA limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
Ft (X,Y,Z) 0 P includes allowances for calculation and measurement uncertainties.
Design power distribution for F0. Ft (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.
MCEI-0400-326 Page 15 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report M0(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 Appendix Table A-1 for normal operating conditions and in Appendix Table A-4 for power escalation testing during initial startup operation.
UMT MT TILT Total Peak Measurement Uncertainty. (UMT = 1.05)
Engineering Hot Channel Factor. (MT= 1.03)
Peaking penalty that acc?.unts for allowable quadrant power tilt ratio of 1.02. (TILT= 1.035)
L RPS F~(X,Y,Z)
- Mc(X,Y,Z) 2*6*6
[FQ(X,Y,Z)]
=
UMT *MT* TILT where:
[F~(X,Y,Z)]RPS = Cycle dependent maximum allowable design peaking factor that ensures FQ(X,Y,Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within the AFD, RIL, and QPTR limits.
[F~(X,Y,Z)]RPS includes allowances for calculation and measurement uncertainties.
D FQ(X,Y,Z)
Defined in Section 2.6.5.
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 Appendix Table A-2 for normal operating conditions and in Appendix Table A-5 for power escalation testing during initial startup operations.
UMT Defined in Section 2.6.5.
MT Defined in Section 2.6.5.
TILT Defined in Section 2.6.5.
McGuire 1 Cycle 25 Core Operating Limits Report 2.6.7 KSLOPE = 0.0725 where:
MCEI-0400-326 Page 16 of31 Revision 0 KS LOPE =Adjustment to K 1 value from OT Ll T trip setpoint required to RPS compensate for each I% FQM (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.
McGuire 1 Cycle 25 Core Operating Limits Report Figure 4 K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for Westinghouse RFA Fuel MCEI-0400-326 Page 17 of31 Revision 0 1.200 ~-------------------------------,
(0.0, 1.00)
(4.0, 1.00) 1.000.,_ _______
1 0.800
~ 0.600
~
0.400 0.200 0.000 0.0 Core Height
{ft) 0.0
- S4
>4 12.0 2.0 (4.0, 0.9259)
K(Z) 1.000 1.000 0.9259 0.9259 4.0 6.0 Core Height (ft)
(12.0, 0.9259) 8.0 10.0 12.0
McGuire 1 Cycle 25 Core Operating Limits Report Table 2 FQ(X,Y,Z) and F,rn(X,Y) Penalty Factors For Tech Spec Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2 Burn up (EFPD) 4 12 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 425 450 465 475 497 502 507 517 527 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 2.00 F'-rn(X,Y)
Penalty Factor (%)
2.00 2.00 2.00 2.00 2.09 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 burnups outside the range of the table shall use a 2%
penalty factor for both FQ(X,Y,Z) and F 1rn(X,Y) for compliance with the Technical Specification Surveillances 3.2.1.2, 3.2.1.3 and 3.2.2.2.
MCEI-0400-326 Page 18 of31 Revision 0
MCEI-0400-326 Page 19 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report
- 2. 7 Nuclear Enthalpy Rise Hot Channel Factor - F MI(X,Y) (TS 3.2.2)
F LlH steady-state limits referred to in Technical Specification 3.2.2 are defined by the following relationship.
where:
[Fk8 (X, Y)tco is the steady-state, maximum allowed radial peak and includes I
allowances for calculation/measurement uncertaint~.
MARP(X,Y) =
Cycle-specific operating limit Maximum Allowable Radial Peaks. MARP(X,Y) radial peaking limits are provided in Table 3.
Thermal Power p =
Rated Thermal Power RRH =Thermal Power reduction required to compensate for each 1 % measured radial peak, F!!r (X,Y), exceeds the limit.
(RRH = 3.34, 0.0 < P :::; 1.0)
The following parameters are required for core monitoring per the surveillance requirements of Technical Specification 3.2.2.
L SURV -
FfH (X, Y)
- M l>H (X, Y) 2.7.2
[F,.,8 (X,Y)]
UMR *TILT where:
SURV
[Fktt (X,Y)]
=
Cycle dependent maximum allowable design peaking factor that ensures F Llli(X, Y) limit is not exceeded for operation
. h" h
d l".
L (
SURV wit mt e AFD, RIL, an QPTR im1ts. FM X,Y) includes allowances for calculation/measurement uncertainty.
F~H (X,Y) = Design radial power distribution for F t>H* F~H (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.
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 20 of31 Revision 0 Mti.ttCX,Y) =Margin remaining in core location X,Y relative to Operational DNB limits in the transient power distribution.
MLiH(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.
UMR
=Uncertainty value for measured radial peaks (UMR = 1.0).
UMR is set to 1.0 since a factor of 1.04 is implicitly included in the variable M,rn(X,Y).
TILT =Defined in Section 2.6.5.
I 2.7.3 RRH is defined in Section 2.7.1.
2.7.4 TRH = 0.04 where:
TRH = Reduction in OTLiT K1 setpoint required to compensate for each 1 %
measured radial peak, F~ (X,Y) exceeds its limit.
2.7.5 F,rn(X,Y) Penalty Factors for Technical Specification Surveillance 3.2.2.2 are provided in Table 2.
2.8 Axial Flux Difference - AFD (TS 3.2.3) 2.8.1 Axial Flux Difference (AFD) Limits are provided in Figure 5.
Core Height ft)
I.OS 1.1 0.12 1.8092 1.8553 1.20 l.8102 1.8540 2.40 l.8093 l.8525 3.60 1.8098 l.8514 4.80 1.8097 l.8514 6.00 1.8097 l.8514 7.20 1.8070 1.8438 8.40 1.8073 1.8319 9.60 1.8072 1.8102 10.80 1.7980 1.7868 11.40 1.7892 1.7652 McGuire 1 Cycle 25 Core Operating Limits Report Table 3 Maximum Allowable Radial Peaks'(MARPs)
RF A Fuel MARPs 100% Full Power Axial Peak 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9248 1.9146 1.9179 2.0621 2.0498 2.0090 l.9333 1.9248 1.9146 1.9179 2.1073 2.0191 1.9775 l.9009 1.9312 1.9146 l.9179 2.0735 l.9953 l.9519 l.8760 1.9204 1.9146 l.9179 i 2.0495 1.9656 1.9258 1.8524 1.9058 1.9146 1.9179 2.0059 1.9441 1.9233 1.8538 1.8921 1.9212 1.9179 1.9336 l.8798 1.8625 1.8024 l.8716 l.8930 1.8872 1.8723 1.8094 1.7866 l.7332 1.8452 l.8571 1.8156 1.7950 l.7359 1.7089 1.6544 1.8093 1.7913 l.7375 1.7182 1.6572 1.6347 1.5808 1.7611 l.7163 l.6538 1.6315 1.5743 1.5573 1.5088 1.7250 l.6645 1.6057 1.5826 1.5289 1.5098 l.4637 1.9 l.8625 1.8306 1.8054 l.7855 l.7836 1.7472 1.6812 1.6010 l.5301 1.4624 1.4218 MCEI-0400-326 Page 21 of31 Revision 0 2.1 3.0 3.25 1.7780 l.3151 l.2461 1.7852 l.3007 l.2235 1.7320 l.4633 1.4616 1.6996 l.4675 l.3874 i 1.6714 1.2987 1.2579 1.6705 l.3293 1.2602 1.5982 1.2871 1.2195 l.5127 1.2182 l.1578 l.4444 l.1431 1.0914 1.3832 l.1009 1.0470 1.3458 1.0670 1.0142
~
0
~
~
8.....
..c:
E-<
"O.. -
cu IZ 0 -=
~
-50 McGuire 1 Cycle 25 Core Operating Limits Report Figure 5 MCEI-0400-326 Page 22 of31 Revision 0 Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits
(-18, 100)
(+10, 100)
Unacc,eptable Operation 90 Unacceptable Operation 80 Acceptable Operation 70 I
60 50
(-36, 50)
(+21, 50) 40 30 20 10
-40
-30
-20
-10 0
10 20 30 40 50 Axial Flux Difference (% Delta I)
NOTE: Compliance with Technic'al Specification 3.2.l may require more restrictive AFD limits. Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 23 of31 Revision 0 2.9 Reactor Trip System Instrumentation Setpoints (TS 3.3.1) Table 3.3.1-1 2.9.1 Overtemperature h.T Setpoint Parameter Values Parameter Nominal Tavg at RTP Nominal RCS Operating Pressure Overtemperature /1 T reactor trip setpoint ++
Overtemperature 11T reactor trip heatup setpoint penalty coefficient Overtemperature 11T reactor trip depressurization setpoint penalty coefficient Time constants utilized in the lead-lag compensator for 11T Time constant utilized in the lag compensator for /1 T Time constants utilized in the lead-lag compensator for Tavg Time constant utilized in the measured Tavg lag compensator f 1 (111) "positive" breakpoint fi (111) "negative" breakpoint fi (111) "positive" slope fi (111) "negative" slope Nominal Value T' :S 585.1 °F P' = 2235 psig Kl :S 1.1978 K2 = 0.0334/'F KJ = 0.001601/psi
- 1 2: 8 sec.
- 2 :S 3 sec.
- 3 :S 2 sec.
- 4 2: 28 sec.
- 5 :S 4 sec.
"6 :S 2 sec.
= 19.0 %111
=NIA*
= 1.769 %11Tol %111
=NIA*
fi (.1I) negative breakpoints and slopes for OT.1T are less restrictive than the OP.1T f2(.1I) negative breakpoint and slope. Therefore, during a transient which challenges the negative imbalance limits, OP.1T f2(.1I) limits will result in a reactor trip before OT.1T fi (.1I) limits are reached. This makes implementation of an OT.1T fi (.11) negative breakpoint and slope unnecessary.
++.1T0 is assumed to be renormalized to 100% RTP following the MUR power uprate.
MCEI-0400-326 Page 24 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.9.2 Overpower tiT Setpoint Parameter Values Parameter Nominal Tavg at RTP Overpower L'lT reactor trip setpoint ++
Overpower L'l T reactor trip penalty Overpower L'lT reactor trip heatup setpoint penalty coefficient Time constants utilized in the lead-lag compensator for L'l T Time constant utilized in the lag compensator for L'l T Time constant utilized in the measured T avg lag compensator Time constant utilized in the rate-lag controller for Tavg fz(M) "positive" breakpoint fz(M) "negative'; breakpoint fz(M) "positive" slope fz(M). "negative" slope Nominal Value T"::::; 585.1 °P Ki::::; 1.0864 Ks= 0.02 I 0P for increasing Tavg Ks = 0.00 I 0 P for decreasing Tavg Ki6 = 0.001179/
0 P for T > T" K6 = 0.0 for T::::; T"
- i ~ 8 sec.
- 2 ::::; 3 sec.
- 3 ::::; 2 sec.
- 6 ::::; 2 sec.
= 35.0 %L'll
=-35.0 %M
++ LiT0 is assumed to be renormalized to 100% RTP following the MUR power uprate.
McGuire 1 Cycle 25 Core Operating Limits Report 2.10 RCS Pressure, Temperature and Flow DNB Limits (TS 3.4.1)
MCEl-0400-326 Page 25 of31 Revision 0 2.10.1 The RCS pressure, temperature and flow limits for DNB are shown in Table 4.
2.11 Accumulators (TS 3.5.1) 2.11.1 Boron concentration limits during MODES 1and2, and MODE 3 with RCS pressure > 1000 psi:
Parameter Applicable Bumuq Limit Accumulator minimum-boron concentration.
0 -200 EFPD 2,475 ppm Accumulator minimum boron concentration.
200.1 - 250 EFPD 2,475 ppm Accumulator minimum boron concentration.
250.l - 300 EFPD 2,475 ppm Accumulator minimum boron concentration.
300.1 - 350 EFPD 2,404 ppm Accumulator minimum boron concentration.
350.1 - 400 EFPD 2,294 ppm Accumulator minimum boron concentration.
400.1 - 450 EFPD 2,219 ppm Accumulator minimum boron concentration.
450.1 - 497 EFPD 2,148 ppm Accumulator minimum boron concentration.
497.l - 517 EFPD 2,079 ppm Accumulator minimum boron concentration.
517.1-527 EFPD 2,046 ppm Accumulator maximum boron concentration.
0-527 EFPD 2,875 ppm 2.12 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.12.1 Boron concentration limits during MODES 1, 2, 3, and 4:
Parameter R WST minimum boron concentration.
2,675 ppm RWST maximum boron concentration.
2,875 ppm
McGuire 1 Cycle 25 Core Operating Limits Report Table 4 Reactor Coolant System DNB Parameters No. Operable Parameter Indication Channels
- 1. Indicated RCS Average Temperature meter 4
meter 3
computer 4
computer 3
- 2. Indicated Pressurizer Pressure meter 4
meter 3
computer 4
computer 3
- 3. RCS Total Flow Rate MCEI-0400-326 Page 26 of31 Revision 0 Limits
- S 587.2 °F
- S 586.9 °F i
- S 587.7 °F
- S 587.5 °F 2:: 2212.3 psig 2:: 2215.0 psig 2:: 2209.1 psig 2:: 2211.3 psig 2:: 390,000 gpm*
- Note: The RCS minimum coolant flow rate assumed in the licensing analyses for the Ml C25 core is 388,000 gpm. However, the flow is set at 390,000 gpm, which is conservative.
McGuire 1 Cycle 25 Core Operating Limits Report 2.13 Spent Fuel Pool Boron Concentration (TS 3.7.14)
MCEI-0400-326 Page 27 of31 Revision 0 2.13.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter 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 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 Kerrremains within the MODE 6 reactivity requirement ofKeff:'S 0.95.
Parameter Minimum boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity.
2,675 ppm
MCEI-0400-326 Page 28 of31 Revision 0 McGuire 1 Cycle 25 Core Operating Limits Report 2.15 Boration Systems 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 NOTE: When cycle burnup is ~ 475 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.
I BAT minimum boron concentration Volume of 7,000 ppm boric acid solution required to maintain SDM at 68°F BAT Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9.14)
RWST minimum boron concentration Volume of2,675 ppm boric acid solution required to maintain SDM at 68 °F R WST Minimum Shutdown Volume (Includes the additional volumes listed in SLC 16.9.14) 7,000 ppm 2,300 gallons 10,599 gallons (13.6%)
2,675 ppm 8,200 gallons 47,700 gallons (41 inches)
McGuire 1 Cycle 25 Core Operating Limits Report MCEI-0400-326 Page 29 of31 Revision 0 2.16 Boration Systems Borated Water Source - Operating (SLC 16.9.11) 2.17 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 temperatures> 300°F.*
- NOTE: The SLC 16.9.11 applicability is down to MODE 4 temperatures of
> 300°F. The minimum volumes calculated support cooldown to 200°F to satisfy UFSAR Chapter 9 requirements.
Parameter NOTE: When -cycle burnup is ~ 475 EFPD, Figure 6 may be used to determine the required BAT Minimum Level.
BAT minimum boron concentration 7,000 ppm Volume of7,000 ppm boric acid solution required 13,750 gallons to maintain SDM at 300°F BAT Minimum Shutdown Volume (Includes the 22,049 gallons additional volumes listed in SLC 16.9.11)
(38.0%)
R WST minimum boron concentration 2,675 ppm RWST maximum boron concentration (TS 3.5.4) 2,875 ppm Volume of2,675 ppm boric acid solution required 57,107 gallons to maintain SDM RWST Minimum Shutdown Volume (Includes the 96,607 gallons additional volumes listed in SLC 16.9.11)
(103.6 inches)
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.
2,675 ppm
McGuire 1 Cycle 25 Core Operating Limits Report Figure 6 Boric Acid Storage Tank Indicated Level Versus Primary Coolant Boron Concentration (Valid When Cycle Burnup is 2: 475 EFPD)
MCEI-0400-326 Page 30 of31 Revision 0 This figure includes additional volumes listed in SLC 16.9.11 and 16.9.14 40.0 ~~-~-~!
--i-~--1-~--.-----.--~--.-----.--~--.
I I
35.o --- -
j-----o--~--- --j---T -
Concentration BAT Level i
I 1
(ppm)
(%level) i I
o < 300 37.o I
I I
-l T ---i-- -- i
~~~ : ~~~ -~¥a--
i 700 < 1000 23.0 I
I 1000<1300 13.6 I
I
>1300 s.1
(' *-***.... r '
- 1
...,...I ____
.,.--~
~
20.0 -
---- --*---l----! ------!-----*-~-----~------~- -- _; __ --L---
~
I Accepta~le
'I I
1
~
~ 15.0 ------
i----- i ---- ___ i_ ___ 1----,,;-----1-*-t* ---
f l
__..;. _____ - ~------*_,;_____
1
- -r*------ -- --- ---
1-----r- -- 1-- --- ---- -
'*' I Un:ooprabm Opo 1~uon..
i _
10.0 I
I '
0.0+---+---+----ic--+----+---+----iC--+----i----+--r---r---i----!
0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 2600 2800 RCS Boron Concentration (ppmb)
McGuire 1 Cycle 25 Core Operating Limits Report Appendix A Power Distribution Monitoring Factors MCEI-0400-326 Page 31 of31 Revision 0 Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the McGuire I Cycle 25 Maneuvering Analysis calculation file, MCC-1553.05-00-0622. 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 controls this information via computer files and should be contacted ifthere is a need to access this information.
Appendix A is included in the COLR copy transmitted to the +/--ffi.c.