BW250041, Core Operating Limits Report, Cycle 25, Revision 21
| ML25267A013 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  (NPF-072) |
| Issue date: | 09/24/2025 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML25267A011 | List: |
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| BW250041 | |
| Download: ML25267A013 (1) | |
Text
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 25 CONSTELLATION TRACKING ID:
COLR BRAIDWOOD 1 REVISION 21
COLR BRAIDWOOD 1 Revision 21 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 25 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 (FNt.H)
LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
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.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 Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SOM) - MODE 1 and MODE 2 with keff;:,: 1.0 Shutdown Margin (SOM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)
COLR BRAIDWOOD 1 Revision 21 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 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.
nee;--,------------.-------.-----.------.....-----.....
24".' 1 psia 2250 psia sec
\
\
\,
- r,;*, -!-_....._, _1'----'-1 __
_,_,_.J...1 ---1l--1-_........_,--'-l_...._1 __ --'-,-'--1--'-1--_,_1_....._l ---1'--1--........_l--'-I-\.J...I
---I J,_ '*'
i,L Figure 2.1.1: Reactor Core Limits
2.2 2.3 2.4 2.5 COLR BRAIDWOOD 1 Revision 21 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 SHUTDOWN MARGIN (SOM)
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.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).
Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC} limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.827 x 10-5 Ak/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 Ak/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 Ak/k/°F.
2.3.4 The EOL/ARO/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 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
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) 228 113
COLR BRAIDWOOD 1 Revision 21 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 25 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224)
(77%, 224) 220 200 180 "2
3= 160 I!!
"C
.c -
~ 140
- g_
Cl) -
~ 120 C
0..
'iii 100 0
Cl.
.II:
C 80 m
"C 0
a:::
60 40 20 0
,c*
...,..,,.,~,,.,
/ V
/ V J
VcBANKB I V
~
~
'V*
V j(O%, 162)
I IL
/
/
IBANK C I
/
/ "
/
V V
V !BANK D
/
/
/ V V
I
/
/
V dl'l<O%, 47) I
/
i'
~v 1(30%.0)v t
T (100%, 161) 0 10 20 30 40 50 60 70 80 90 100 Rated Thermal Power (Percent)
The bank position is given as follows:
Control Bank D: (161/70) * (P-100) + 161 (for 30 SP S 100)
Where P is defined as the core power (in percent).
2.6 COLR BRAIDWOOD 1 Revision 21 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Heat Flux Hot Channel Factor (Fo(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
pRTP FQ(Z) ::;-Q-xK(Z) forP ::;0.5 0.5 pRTP FQ (Z) ::; _Q_xK(Z) for P > 0.5 p
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FoHP = 2.60 K(Z) is provided in Figure 2.6.1.
Figure 2.6.1 K(Z) - Normalized F0 (Z) as a Function of Core Height (0.0, 1.0) 1.1 (6.0, 1.0)
(12.0, 1.0) 1--------------------*
0.9,
0.8
- N 0.7, a
- u.
al 0.6 *
"ii e o.s,
0 z
~ 0.4'
~
0.3
- 0.2
- 0.1
~LOCA Limiting Envelope 0 +-----,-------------~------------i 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM Core Height (ft)
COLR BRAIDWOOD 1 Revision 21 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 2.6.2 W(Z) Values:
- 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 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 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 Foc(z) penalty factors that are greater than 2% per the allowable surveillance frequency. These values shall be used to increase the Fow(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.
Table 2.6.2.d contains the required operating space reduction values for THERMAL POWER and AXIAL FLUX DIFFERENCE (AFD) when Fow(z) is not within its limits. These values are used in conjunction with Technical Specification LCO 3.2.1 Required Actions 8.1 and 8.2.
2.6.3 Uncertainty
The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula where:
Uqu = Base Fa measurement uncertainty = 1.05 Ue = Engineering uncertainty factor= 1.03
COLR BRAIDWOOD 1 Revision 21 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 25 Table 2.6.2.a W(Z) versus Core Height for Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per Braidwood SR 3.2.1.2 Bases)
Height 150 4000 14000 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2354 1.3622 1.2466 0.20 1.2287 1.3523 1.2403 0.40 1.2287 1.3485 1.2421 0.60 1.2326 1.3483 1.2487 0.80 1.2409 1.3509 1.2607 1.00 1.2398 1.3430 1.2633 1.20 1.2301 1.3273 1.2563 1.40 1.2164 1.3074 1.2455 1.60 1.2022 1.2862 1.2344 1.80 1.1876 1.2634 1.2224 2.00 1.1728 1.2391 1.2091 2.20 1.1585 1.2139 1.1948 2.40 1.1454 1.1885 1.1801 2.60 1.1340 1.1636 1.1653 2.80 1.1229 1.1394 1.1521 3.00 1.1118 1.1169 1.1413 3.20 1.1050 1.1034 1.1364 3.40 1.1049 1.1025 1.1368 3.60 1.1046 1.1029 1.1413 3.80 1.1065 1.1029 1.1460 4.00 1.1097 1.1025 1.1500 4.20 1.1121 1.1020 1.1537 4.40 1.1142 1.1020 1.1566 4.60 1.1159 1.1025 1.1588 4.80 1.1170 1.1042 1.1599 5.00 1.1176 1.1060 1.1601 5.20 1.1175 1.1071 1.1591 5.40 1.1168 1.1075 1.1569 5,60 1.1177 1.1072 1.1545 5.80 1.1212 1.1103 1.1541 6.00 1.1303 1.1167 1.1580 6.20 1.1441 1.1223 1.1693 6.40 1.1569 1.1267 1.1781 6,60 1.1692 1.1309 1.1871 6.80 1.1811 1.1400 1.1946 7.00 1.1918 1.1524 1.1999 7.20 1.2008 1.1637 1.2032 7.40 1.2080 1.1734 1.2043 7.60 1.2132 1.1817 1.2032 7.80 1.2166 1.1866 1.1998 8.00 1.2169 1.1941 1.1944 8.20 1.2165 1.2072 1.1890 8.40 1.2210 1.2188 1.1857 8.60 1.2245 1.2334 1.1825 8.80 1.2297 1.2498 1.1847 9.00 1.2442 1.2732 1.1934 9.20 1.2692 1.3041 1.2056 9.40 1.2944 1.3292 1.2194 9.60 1.3150 1.3544 1.2284 9,80 1.3320 1.3766 1.2383 10.00 1.3541 1.3951 1.2512 10.20 1.3847 1.4146 1.2622 10.40 1.4110 1.4376 1.2695 10.60 1.4331 1.4619 1.2744 10.80 1.4557 1.4844 1.2776 11.00 1.4784 1.5112 1.2858 11.20 1.4801 1.5206 1.2779 11.40 1.4163 1.4560 1.2237 11.60 1.3523 1.3951 1.1909 11.80 1.3440 1.3890 1.1772 12.00 /core too) 1.3201 1.3680 1.1581 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 20000 MWD/MTU 1.1869 1.1781 1.1791 1.1859 1.1996 1.2044 1.1987 1.1893 1.1804 1.1711 1.1608 1.1498 1.1386 1.1275 1.1161 1.1072 1.1046 1.1105 1.1233 1.1367 1.1491 1.1610 1.1719 1.1815 1.1897 1.1964 1.2010 1.2040 1.2076 1.2126 1.2213 1.2324 1.2408 1.2480 1.2530 1.2552 1.2547 1.2516 1.2456 1.2372 1.2254 1.2127 1.2050 1.2039 1.2107 1.2235 1.2320 1.2432 1.2491 1.2618 1.2815 1.2965 1.3078 1.3164 1.3235 1.3340 1.3297 1.2660 1.2144 1.2081 1.1955
COLR BRAIDWOOD 1 Revision 21 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per Braidwood SR 3.2.1.2 Bases)
Height 150 4000 14000 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3716 1.4488 1.3509 0.20 1.3632 1.4378 1.3434 0.40 1.3630 1.4332 1.3445 0.60 1.3647 1.4323 1.3507 0,80 1.3720 1.4343 1.3625 1.00 1.3684 1.4250 1.3638 1.20 1.3556 1.4076 1.3550 1.40 1.3383 1.3859 1.3420 1.60 1.3201 1.3626 1.3285 1.80 1.3004 1.3376 1.3138 2.00 1.2790 1.3108 1.2974 2.20 1.2564 1.2830 1.2797 2.40 1.2333 1.2549 1.2613 2.60 1.2102 1.2271 1.2426 2.80 1.1884 1.2008 1.2233 3.00 1.1722 1.1817 1.2059 3.20 1.1635 1.1711 1.1934 3.40 1.1603 1.1645 1.1874 3.60 1.1574 1.1573 1.1878 3.80 1.1539 1.1495 1.1885 4.00 1.1498 1.1444 1.1887 4.20 1.1453 1.1420 1.1883 4.40 1.1412 1.1392 1.1871 4.60 1.1375 1.1358 1.1848 4.80 1.1332 1.1318 1.1815 5.00 1.1284 1.1270 1.1770 5.20 1.1229 1.1218 1.1712 5.40 1.1179 1.1157 1.1642 5.60 1.1178 1.1082 1.1594 5.80 1.1220 1.1093 1.1634 6.00 1.1337 1.1157 1.1767 6.20 1.1511 1.1210 1.1895 6.40 1.1661 1.1271 1.2000 6.60 1.1798 1.1363 1.2084 6,80 1.1921 1.1457 1.2145 7.00 1.2027 1.1558 1.2182 7.20 1.2114 1.1669 1.2194 7.40 1.2179 1.1768 1.2180 7.60 1.2226 1.1855 1.2143 7.80 1.2237 1.1918 1.2065 8.00 1.2261 1.1999 1.2008 8.20 1.2341 1.2124 1.2003 8.40 1.2401 1.2245 1.1981 8.60 1.2486 1.2395 1.1987 8.80 1.2583 1.2569 1.2033 9.00 1.2710 1.2790 1.2153 9.20 1.2840 1.3040 1.2291 9.40 1.2903 1.3234 1.2379 9,60 1.3141 1.3425 1.2467 9.80 1.3466 1.3595 1.2527 10.00 1.3769 1.3834 1.2560 10.20 1.4047 1.4191 1.2630 10.40 1.4283 1.4482 1.2765 10.60 1.4480 1.4729 1.2877 10.80 1.4681 1.4951 1.2965 11.00 1.4888 1.5219 1.3090 11.20 1.4883 1.5312 1.3063 11.40 1.4219 1.4658 1.2443 11.60 1.3560 1.4044 1.1870 11.80 1.3463 1.3980 1.1802 12.00 /core tool 1.3202 1.3766 1.1599 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bum ups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 20000 MWD/MTU 1.2715 1.2615 1.2618 1.2682 1.2818 1.2853 1.2791 1.2707 1.2596 1.2486 1.2387 1.2291 1.2191 1.2091 1.1991 1.1883 1.1792 1.1761 1.1795 1.1865 1.1949 1.2017 1.2075 1.2119 1.2145 1.2169 1.2188 1.2185 1.2198 1.2310 1.2473 1.2610 1.2719 1.2798 1.2845 1.2861 1.2844 1.2795 1.2716 1.2590 1.2482 1.2424 1.2346 1.2300 1.2233 1.2213 1.2314 1.2419 1.2470 1.2546 1.2683 1.2828 1.2931 1.3004 1.3081 1.3187 1.3117 1.2499 1.1952 1.1947 1.1815
COLR BRAIDWOOD 1 Revision 21 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWD/MTU)
Foc(Z) 0 1.0200 150 1.0750 600 1.0870 1000 1.0850 2300 1.0300 2850 1.0200 6129 1.0200 6500 1.0310 7100 1.0310 7500 1.0370 7900 1.0420 9000 1.0330 10000 1.0250 10600 1.0200 18973 1.0200 19700 1.0310 21000 1.0340 22000 1.0390 22516 1.0370 24190 1.0370 Notes:
Linear interpolation is adequate for intermediate cycle burnups.
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.
Table 2.6.2.d Required Operating Space Reduction When Fow(Z) Exceeds Its Limits Required FoW(Z)
THERMAL POWER Negative AFD Band Positive AFD Band Marqin Improvement Reduction (% RTP)
Reduction (% AFD)
Reduction (% AFD)
- s; 1%
- 3%
- 1%
- 1%
> 1%AND :s; 2%
- 5%
- 2%
- 2%
> 2%AND :s; 3%
- 9%
- 3%
- 3%
>3%
- 50%
N/A N/A
2.7 COLR BRAIDWOOD 1 Revision 21 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7.1 FNAH:S:F§i!jP[1.0+PFAH(1.0-P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
F§~P = 1.67 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:
UF,1Hm = Base FNAH measurement uncertainty = 1.04 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 The AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below.
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. These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken. 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.
These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken.
2.9 DELETED
COLR BRAIDWOOD 1 Revision 21 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Figure 2.8.1.a:
120 100 a:
w
~
0 80 CL...,
<(
~
a:
w 60
- c
~
C w
~ 40 a: -
0
~
20 0
-50 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference limits Unacceptable Operation 1 (-10, 100) 1 1 (+10, 100) 1
.. Acc~pta_~le Operation Unacceptable Operation I (-20, SO)
I (+25, SO) I
-40
-30
-20
-10 0
10 20 30 40 AXIAL FLUX DIFFERENCE {%)
so
COLR BRAIDWOOD 1 Revision 21 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 Figure 2.8.1.b:
120 100 0::
LU
~
0 80 a..
...I
<(
0::
LU 60
- c
~
C LU
!ct 40 0:: -
0
~
20 0
-50 Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 1 (-15, 100) 1 Unacceptable Operation 1 {+10, 100) 1 Acceptab!e Operation Unacceptc1ble Operation 1 {-35, SO) l (+25, SO) I
-40
-30
-W
-10 0
10 W
30 40 AXIAL FLUX DIFFERENCE (%)
50
COLR BRAIDWOOD 1 Revision 21 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient Kz shall be equal to 0.0297 I °F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.
2.10.4 The nominal Tavg 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,1 shall be equal to 8 sec.
2.10. 7 The measured reactor vessel AT lead/lag time constant,2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant,3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant,4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant,s shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant,s shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) "positive" breakpoint shall be +10% Al.
2.10.13 The f1 (Al) "negative" breakpoint shall be -18% Al.
2.10.14 The f1 (Al) "positive" slope shall be +3.47% /%Al.
2.10.15 The f1 (Al) "negative" slope shall be -2.61 % /%Al.
COLR BRAIDWOOD 1 Revision 21 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower i'. T Setpoint Parameter Values 2.11.1 The Overpower i'. T reactor trip setpoint K4 shall be equal to 1. 072.
2.11.2 The Overpower i'. T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing Tav9.
2.11.3 The Overpower i'. T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg.
2.11.4 The Overpower i'. T reactor trip setpoint T avg heatup coefficient K6 shall be equal to 0.00245 / °F when T > T".
2.11.5 The Overpower i'. T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to O / °F when T ::s; T".
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 i'.T lead/lag time constant 11 shall be equal to 8 sec.
2.11.8 The measured reactor vessel i'. T lead/lag time constant 12 shall be equal to 3 sec.
2.11.9 The measured reactor vessel i'. T lag time constant 13 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant 16 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant 17 shall be equal to 10 sec.
2.11.12 The fa (i'.I) "positive" breakpoint shall be 0 for all i'.1.
2.11.13 The fa (i'.I) "negative" breakpoint shall be O for all i'.I.
2.11.14 The fa (i'.I) "positive" slope shall be 0 for all M 2.11.15 The fa (i'.I) "negative" slope shall be 0 for all i'.I.
COLR BRAIDWOOD 1 Revision 21 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 25 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (ON B) 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 (Tav9) 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 s 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 1766 b) for cycle burnups 2 0 MWD/MTU 1910 and < 16000 MWD/MTU c) for cycle burnups 2 16000 MWD/MTU 1484 2.13.2 a) prior to initial criticality 1839 b) for cycle burnups 2 0 MWD/MTU and < 16000 MWD/MTU 2125 c) for cycle burnups 2 16000 1616 MWD/MTU