ML18113A147: Difference between revisions

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{AFD) (LCO 3.2.3} 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD} Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.
{AFD) (LCO 3.2.3} 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD} Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.
a} Figure 2.8.1.a is the Normal AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.a. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.
a} Figure 2.8.1.a is the Normal AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.a. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.
b} Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.b. 2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
b} Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.b. 2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.  
2.9 Departure from Nucleate Boiling Ratio CDNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL :2:: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsL}
 
===2.9 Departure===
 
from Nucleate Boiling Ratio CDNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL :2:: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsL}
is applicable with THERMAL POWER :2:: 50% RTP when PDMS is OPERABLE.
is applicable with THERMAL POWER :2:: 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms: DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin COLR BRAIDWOOD 1 Revision 14 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.a: 120 100 a:: LU 3: 0 80 a. .... < :? a:: LU 60 ::c I-c LU 40 ... 0 20 0 -50 Una 01 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits with PDMS Inoperable I (-10, 100) I I (+10, 100) 1 cceptab e J \ U1 accept< ble 1eration I \ Jperatic n Acee )table \ I Ope1 ation \ I (-20, 5o) I I I I (+25, 50) I 30 10 0 10 20 30 40 AXIAL FLUX DIFFERENCE  
2.9.2 PDMS Alarms: DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin COLR BRAIDWOOD 1 Revision 14 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.a: 120 100 a:: LU 3: 0 80 a. .... < :? a:: LU 60 ::c I-c LU 40 ... 0 20 0 -50 Una 01 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits with PDMS Inoperable I (-10, 100) I I (+10, 100) 1 cceptab e J \ U1 accept< ble 1eration I \ Jperatic n Acee )table \ I Ope1 ation \ I (-20, 5o) I I I I (+25, 50) I 30 10 0 10 20 30 40 AXIAL FLUX DIFFERENCE  

Revision as of 01:35, 18 October 2018

Braidwood Station, Unit 1 - Core Operating Limits Report, Braidwood Unit 1 Cycle 21
ML18113A147
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 04/23/2018
From: Marchionda-Palmer M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW180044
Download: ML18113A147 (17)
v • d • e


Text

Exelon Generation April 23, 2018 BW180044 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRC Docket No. STN 50-456 Exelon Generation Company, LLC Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 www.exeloncoro.com

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 21 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 21 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 1 Cycle 21 COLR, Revision 14 was implemented during Braidwood Unit 1 Refueling Outage 20 in support of Cycle 21 operation.

Note that the revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLR, i.e., Braidwood Unit 1 Cycle 20, Revision 13. If you have any questions regarding this matter, please contact Ms. Marta Spillie, Acting Regulatory Assurance Manager, at (815) 417-4833.

Sincerely, (hWN Marri Marchionda-Palmer Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 21, Revision 14 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector

-Braidwood Station NRC Project Manager, NRR -Braidwood and Byron Stations CORE OPERATING LIMITS REPORT {COLR) FOR BRAIDWOOD UNIT 1 CYCLE 21 EXELON TRACKING ID: COLR BRAIDWOOD 1 REVISION 14 COLR BRAIDWOOD 1 Revision 14 Page 1of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 21 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS). The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) affected by this report are listed below: SL 2.1.1 Reactor Core Safety Limits (SLs) LCO 3.1.1 SHUTDOWN MARGIN (SOM) LCO 3.1.3 Moderator Temperature Coefficient (MTC) LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions

-MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (Fa(Z)) LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN AH) LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD) LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR) LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BOPS) LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual (TRM) affected by this report are listed below: TRM TLCO 3.1.b TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.i TRM TLCO 3.1.j TRM TLCO 3.1.k Boration Flow Paths -Operating Charging Pumps -Operating Borated Water Sources-Operating Position Indication System -Shutdown Shutdown Margin (SDM) -MODE 1 and MODE 2 with keff 1.0 Shutdown Margin (SDM) -MODE 5 Shutdown and Control Rods Position lndi.cation System -Shutdown (Special Test Exception)

COLR BRAIDWOOD 1 Revision 14 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 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 are applicable for the entire cycle unless otherwise identified.

These limits have been developed using the NRG-approved methodologies specified in Technical Specification 5.6.5. 2.1 Reactor Core Safety Limits (Sls) (SL 2.1.1) 2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1. 2471 psia ---

s -!-' 0 !..... Q) CL E (j) 1--

<l) c::n 0 !..... Cl) it: 530-+-_.__.__._-+--'---'---"'--f--'--'--"---+--'--'-_._-+-_.__.__._--+.---1.---1

__ .1.-..1 0 0.2 0.4 0.6 Q.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits COLR BRAIDWOOD 1 Revision 14 Page 3of15 CORE OPERATING Lll\1ITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.2 SHUTDOWN MARGIN CSDM) The SOM limit for MODES 1, 2, 3, and 4 is: 2.2.1 The SOM shall be greater than or equal to 1.3% Ak/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j}. The SOM limit for MODE 5 is: 2.2.2 SOM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j}. 2.3 Moderator Temperature Coefficient CMTCl (LCO 3.1.3) The Moderator Temperature Coefficient (MTC) limits are: 2.3.1 The BOUARO/HZP-MTC upper limit shall be +1.884 x 10-5 Ak/k/°F. 2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10-4 Ak/k/°F. 2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 Ak/k/°F. 2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 Ak/k/°F. where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps. 2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1. 2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps. 2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:

Park Position (step) Overlap Limit (step) 226 111 227 112 228 113 229 114 COLR BRAIDWOOD 1 Revision 14 Page4 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.5.1: Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 200 180 -c 160 ,, .c 140 llJ Cl. .!! !!?.. 120 c 0 i! ! 100 a. JC c nl m 80 ,, 0 IX 60 40 20 I' r / v / / hANKB I / / / 1(0%, 162) I IL / / IBANKC I / /' / , / v v IBANKD I / / v / / / / r1co%, 47l I ,/ (30%.0)v (100%, 161) 0 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BRAIDWOOD 1 Revision 14 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.6 Heat Flux Hot Channel Factor CFg{Z}) (LCO 3.2.1) 2.6.1 Total Peaking Factor: pRTP FQ(Z) forP 0.5 pRTP FQ (Z) _Q_xK(Z) for P > 0.5 p where: P = the ratio of THERMAL POWER to RATED THERMAL POWER

= 2.60 K(Z) is provided in Figure 2.6.1. 1.1 1 0.9 0.8 N' 0.7 J: i 0.6 .!:! c; e o.s 0 z 0.4 0.3 0.2 0.1 0 Figure 2.6.1 K(Z)-Normalized FQ(Z) as a Function of Core Height (0.0 1.0) (6.0 1.0) (12.C 0.924) -. ...... LOCA Limiting Envelope -0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP COLR BRAIDWOOD 1 Revision 14 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.6.2 W(Z) Values: a) When the Power Distribution Monitoring System (PDMS) is OPERABLE, W(Z) = 1.00000 for all axial points. b) When PDMS is inoperable, W(Z) is provided as: 1) Table 2.6.2.a are the normal operation W(Z) values that correspond to the NORMAL AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. The Normal AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values. 2) Table 2.6.2.b are the Expanded normal operation W(Z) values that correspond to the EXPANDED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The Expanded normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. The Expanded AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values. Table 2.6.2.c shows the Fe a(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fw a(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.c. 2.6.3 Uncertainty:

The uncertainty, UFa. to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula where: Uqu = Base Fa measurement uncertainty

= 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms: Fa(Z) Warning Setpoint = 2% Fa(Z) Margin Fa(Z) Alarm Setpoint = 0% Fa(Z) Margin COLR BRAIDWOOD 1 Revision 14 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Tabla 2.8.2.a W(Z) versus Cora Haight for Normal AFD Acceptable Operation Limits In Figura 2.8.1.a (Top and Bottom 8% Excluded perWCAP-10216)

Height 150 5000 14000 {feet) MWD/MTU MWD/MTU MWD/MTU 0.00 {core bottom\ 1.1893 1.2974 0.20 1.1798 1.2733 0.40 1.1767 1.2638 0.60 1.1717 1.2527 0.80 1.1355 1.2206 1.00 1.1284 1.1894 1.20 1.1539 1.2214 1.40 1.1529 1.2089 1.60 1.1443 1.1928 1.80 1.1367 1.1777 2.00 1.1297 1.1616 2.20 1.1216 1.1435 2.40 1.1145 1.1289 2.60 1.1064 1.1133 2.80 1.0993 1.0997 3.00 1.0927 1.0977 3.20 1.0878 1.0994 3.40 1.0877 1.1002 3.60 1.0885 1.1009 3.80 1.0934 1.1016 4.00 1.0983 1.1023 4.20 1.1024 1.1010 4.40 1.1055 1.1007 4.60 1.1086 1.0993 4.80 1.1107 1.0979 5.00 1.1111 1.0965 5.20 1.1114 1.0941 5.40 1.1197 1.0908 5.60 1.1273 1.0932 5.80 1.1339 1.0977 6.00 1.1406 1.1024 6.20 1.1453 1.1060 6.40 1.1491 1.1192 6.60 1.1517 1.1337 6.60 1.1525 1.1475 7.00 1.1524 1.1604 7.20 1.1527 1.1717 7.40 1.1663 1.1838 7.60 1.1789 1.1942 7.80 1.1908 1.2037 8.00 1.2018 1.2125 8.20 1.2118 1.2200 8.40 1.2219 1.2265 8.60 1.2294 1.2331 8.80 1.2369 1.2433 9.00 1.2444 1.2533 9.20 1.2492 1.2612 9.40 1.2546 1.2710 9.60 1.2576 1.2786 9.80 1.2564 1.2780 10.00 1.2485 1.2794 10.20 1.2428 1.2792 10.40 1.2312 1.2775 10.60 1.2201 1.2722 10.80 1.2260 1.2743 11.00 1.2297 1.2848 11.20 1.2460 1.2912 11.40 1.2565 1.3052 11.60 1.2573 1.3124 11.60 1.2599 1.3197 12.00 !core tool 1.2713 1.3389 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 1.2778 1.2629 1.2619 1.2509 1.2330 1.2207 1.2021 1.1909 1.1744 1.1725 1.1695 1.1686 1.1627 1.1557 1.1468 1.1379 1.1303 1.1255 1.1187 1.1190 1.1224 1.1267 1.1298 1.1319 1.1328 1.1344 1.1363 1.1385 1.1480 1.1645 1.1781 1.1888 1.1974 1.2032 1.2079 1.2097 1.2076 1.2036 1.1966 1.1887 1.1798 1.1679 1.1559 1.1504 1.1511 1.1518 1.1508 1.1559 1.1880 1.2220 1.2530 1.2810 1.3030 1.3220 1.3380 1.3410 1.3400 1.3320 1.3090 1.2923 1.2829 20000 MWD/MTU 1.2199 1.2129 1.2061 1.2054 1.2031 1.1997 1.1941 1.1874 1.1778 1.1688 1.1588 1.1452 1.1328 1.1172 1.1029 1.1017 1.1072 1.1175 1.1318 1.1451 1.1580 1.1709 1.1816 1.1912 1.1987 1.2045 1.2106 1.2142 1.2327 1.2493 1.2629 1.2715 1.2791 1.2808 1.2806 1.2775 1.2693 1.2603 1.2453 1.2304 1.2126 1.1908 1.1779 1.1737 1.1710 1.1679 1.1707 1.2050 1.2510 1.2910 1.3270 1.3590 1.3850 1.4107 1.4325 1.4463 1.4342 1.4221 1.4141 1.4099 1.4057 COLR BRAIDWOOD 1 Revision 14 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Tabla 2.6.2.b W(Z) varaus Cora Haight for Expanded AFD Acceptable Operation Umlts In Figura 2.8.1.b (Top and Bottom 8% Excluded perWCAP-10216)

Haight 150 5000 14000 {feat! MWD/MTU MWD/MTU MWD/MTU 0.00 lcore bottom) 1.3362 1.4231 0.20 1.3171 1.3949 0.40 1.3138 1.3847 0.60 1.3077 1.3726 0.80 1.2546 1.3375 1.00 1.2437 1.3068 1.20 1.2757 1.3357 1.40 1.2733 1.3206 1.60 1.2579 1.3001 1.80 1.2442 1.2811 2.00 1.2305 1.2611 2.20 1.2140 1.2368 2.40 1.1992 1.2160 2.60 1.1821 1.1934 2.80 1.1681 1.1764 3.00 1.1602 1.1721 3.20 1.1526 1.1678 3.40 1.1463 1.1635 3.60 1.1414 1.1578 3.80 1.1371 1.1519 4.00 1.1323 1.1456 4.20 1.1339 1.1374 4.40 1.1346 1.1296 4.60 1.1349 1.1204 4.80 1.1343 1.1116 5.00 1.1321 1.1032 5.20 1.1293 1.0990 5.40 1.1257 1.0943 5.60 1.1273 1.0932 5.80 1.1339 1.0977 6.00 1.1406 1.1024 6.20 1.1453 1.1060 6.40 1.1491 1.1192 8.60 1.1517 1.1337 6.80 1.1525 1.1475 7.00 1.1524 1.1604 7.20 1.1527 1.1717 7.40 1.1663 1.1838 7.60 1.1789 1.1942 7.80 1.1908 1.2037 8.00 1.2018 1.2125 8.20 1.2118 1.2200 8.40 1.2219 1.2265 8.60 1.2294 1.2331 8.80 1.2369 1.2433 9.00 1.2444 1.2533 9.20 1.2492 1.2612 9.40 1.2546 1.2710 9.60 1.2576 1.2786 9.80 1.2564 1.2780 10.00 1.2485 1.2794 10.20 1.2428 1.2792 10.40 1.2312 1.2775 10.60 1.2201 1.2722 10.80 1.2260 1.2743 11.00 1.2297 1.2848 11.20 1.2460 1.2912 11.40 1.2565 1.3052 11.60 1.2573 1.3124 11.80 1.2599 1.3197 12.00 lcore tool 1.2713 1.3389 Nata: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 1.4130 1.3940 1.3920 1.3790 1.3570 1.3420 1.3200 1.3060 1.2820 1.2690 1.2560 1.2400 1.2240 1.2093 1.1985 1.1876 1.1775 1.1718 1.1703 1.1683 1.1664 1.1629 1.1585 1.1535 1.1476 1.1406 1.1363 1.1385 1.1480 1.1645 1.1781 1.1888 1.1974 1.2032 1.2079 1.2097 1.2076 1.2036 1.1966 1.1887 1.1798 1.1679 1.1559 1.1504 1.1511 1.1518 1.1508 1.1559 1.1880 1.2220 1.2530 1.2810 1.3030 1.3220 1.3380 1.3410 1.3400 1.3320 1.3090 1.2923 1.2829 20000 MWD/MTU 1.3383 1.3307 1.3298 1.3279 1.3232 1.3184 1.3098 1.3011 1.2885 1.2768 1.2642 1.2467 1.2320 1.2125 1.1949 1.1806 1.1688 1.1731 1.1764 1.1797 1.1810 1.1817 1.1816 1.1912 1.1987 1.2045 1.2106 1.2142 1.2327 1.2493 1.2629 1.2715 1.2791 1.2808 1.2806 1.2775 1.2693 1.2603 1.2453 1.2304 1.2126 1.1908 1.1779 1.1737 1.1710 1.1679 1.1707 1.2050 1.2510 1.2910 1.3270 1.3590 1.3850 1.4107 1.4325 1.4463 1.4342 1.4221 1.4141 1.4099 1.4057 Notes: COLR BRAIDWOOD 1 Revision 14 Page 9 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor CMWD/MTU)

Fca(Z) 150 1.0200 500 1.0370 675 1.0460 851 1.0520 1027 1.0570 1201 1.0610 1376 1.0580 2602 1.0200 13460 1.0200 13635 1.0203 13986 1.0218 14162 1.0213 14861 1.0200 15387 1.0202 16613 1.0216 16963 1.0220 17488 1.0223 17663 1.0223 18014 1.0219 18714 1.0200 Linear interpolation is adequate for intermediate cycle bumups. All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLR BRAIDWOOD 1 Revision 14 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.7 Nuclear Enthalpy Rise Hot Channel Factor {FN@ (LCO 3.2.2} 2.7.1 FNAH

+ PFAH(1.0-P}] where: P =the ratio of THERMAL POWER to RATED THERMAL POWER (RTP}

= 1.70 PFAH = 0.3 2.7.2 Uncertainty:

The uncertainty, UFAH* to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNAH shall be calculated by the following formula: where: UFLlHm = Base FN AH measurement uncertainty

= 1.04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.}

2.7.3 PDMS Alarms: FN AH Warning Setpoint = 2% FN AH Margin FN AH Alarm Setpoint = 0% FN AH Margin 2.8 AXIAL FLUX DIFFERENCE

{AFD) (LCO 3.2.3} 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD} Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a} Figure 2.8.1.a is the Normal AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.a. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.

b} Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z} values in Table 2.6.2.b. 2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.

2.9 Departure

from Nucleate Boiling Ratio CDNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL :2:: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsL}

is applicable with THERMAL POWER :2:: 50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms: DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin COLR BRAIDWOOD 1 Revision 14 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.a: 120 100 a:: LU 3: 0 80 a. .... < :? a:: LU 60 ::c I-c LU 40 ... 0 20 0 -50 Una 01 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits with PDMS Inoperable I (-10, 100) I I (+10, 100) 1 cceptab e J \ U1 accept< ble 1eration I \ Jperatic n Acee )table \ I Ope1 ation \ I (-20, 5o) I I I I (+25, 50) I 30 10 0 10 20 30 40 AXIAL FLUX DIFFERENCE

(%) 50 COLR BRAIDWOOD 1 Revision 14 Page 12 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.b: Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power --*-*------*----------------*----------*--------------.

120 100 a: w 80 a. _, <C :E a: w 60 ::c Q w 40 .... 0 20 0 -50 Una 01 Expanded Axial Flux Difference Limits with PDMS Inoperable I (-1s, 100) 1 I (+10,100) 1 I \ ::ceptab e I ieration ( \ Acce1 >table .. / Ope1 at ion U1 accept< ble Jperati< n \ \ (-35, SO) I I I (+25, so) I 30 10 0 10 20 30 40 AXIAL FLUX DIFFERENCE

{%) 50 COLR BRAIDWOOD 1 Revision 14 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.10 Reactor Trip System CRTS} Instrumentation (LCO 3.3.1} -Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K 1 shall be equal to 1.325. 2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K 2 shall be equal to 0.0297 / °F. 2.10.3 The Overtemperature AT reactor trip setpoint pressure shall be equal to 0.00135 /psi. 2.10.4 The nominal T avg at RTP (indicated}

T' shall be less than or equal to 588.0 °F. 2.10.5 The nominal RCS operating pressure (indicated}

P' shall be equal to 2235 psig. 2.10.6 The measured reactor vessel AT lead/lag time constant i: 1 shall be equal to 8 sec. 2.10. 7 The measured reactor vessel AT lead/lag time constant 't 2 shall be equal to 3 sec. 2.10.8 The measured reactor vessel AT lag time constant i: 3 shall be less than or equal to 2 sec. 2.10.9 The measured reactor vessel average temperature lead/lag time constant i: 4 shall be equal to 33 sec. 2.10.10 The measured reactor vessel average temperature lead/lag time constant 'ts shall be equal to 4 sec. 2.10.11 The measured reactor vessel average temperature lag time constant 'ts shall be less than or equal to 2 sec. 2.10.12 The f 1 (Al} "positive" breakpoint shall be +10% Al. 2.10.13 The f 1 (Al} "negative" breakpoint shall be -18% Al. 2.10.14 The f 1 (Al} "positive" slope shall be +3.47% I% Al. 2.10.15 The f 1 (Al} "negative" slope shall be -2.61 % I% Al.

COLR BRAIDWOOD 1 Revision 14 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.11 Reactor Trip System CRTS) Instrumentation (LCO 3.3.1) -Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint Ki shall be equal to 1.072. 2.11.2 The Overpower AT reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0.02 / °F for increasing Tavg* 2.11.3 The Overpower AT reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing T avg* 2.11.4 The Overpower AT reactor trip setpoint T avg heatup coefficient Ka shall be equal to 0.00245 / °F when T > T". 2.11.5 The Overpower AT reactor trip setpoint T avg heatup coefficient Ka shall be equal to 0 I °F when 2.11.6 The nominal Tavg at RTP (indicated)

T" shall be less than or equal to 588.0 °F. 2.11. 7 The measured reactor vessel AT lead/lag time constant 't 1 shall be equal to 8 sec. 2.11.8 The measured reactor vessel AT lead/lag time constant 't 2 shall be equal to 3 sec. 2.11.9 The measured reactor vessel AT lag time constant 't 3 shall be less than or equal to 2 sec. 2.11.10 The measured reactor vessel average temperature lag time constant 'ts shall be less than or equal to 2 sec. 2.11.11 The measured reactor vessel average temperature rate/lag time constant 't 7 shall be equal to 1 O sec. 2.11.12 The f 2 (Al) "positive" breakpoint shall be 0 for all Al. 2.11.13 The f 2 (Al) "negative" breakpoint shall be 0 for all Al. 2.11.14 The f 2 (Al) "positive" slope shall be 0 for all Al. 2.11.15 The f 2 (Al) "negative" slope shall be 0 for all Al.

COLR BRAIDWOOD 1 Revision 14 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.12 Reactor Coolant System (RCS) Pressure.

Temperature.

and Flow Departure from Nucleate Boiling CDNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig. 2.12.2 The RCS average temperature (T avg) shall be less than or equal to 593.1 °F. 2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm. 2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the applicable value given in the Table below (LCO 3.9.1 ). The reported "prior to initial criticality

value also bounds the end-of-cycle requirements for the previous cycle. 2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the applicable value given in the Table below. COLR Conditions Boron Concentration Section (ppm) 2.13.1 a) prior to initial criticality 1700 b) for cycle burnups O MWD/MTU 1799 and < 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1448 2.13.2 a) prior to initial criticality 1767 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2028 c) for cycle burnups 16000 1594 MWD/MTU

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