BW220061, Core Operating Limits Report Cycle 24, Revision 19
| ML22285A011 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/12/2022 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22285A009 | List: |
| References | |
| BW220061 | |
| Download: ML22285A011 (16) | |
Text
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 24 CONSTELLATION TRACKING ID:
COLR BRAIDWOOD 1 REVISION 19
COLR BRAIDWOOD 1 Revision 19 Page 1 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 24 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 LCO 3.1.1 LCO 3.1.3 LCO 3.1.4 LCO 3.1.5 LCO 3.1.6 LCO 3.1.8 LCO 3.2.1 LCO 3.2.2 LCO 3.2.3 LCO 3.2.5 LCO 3.3.1 LCO 3.3.9 LCO 3.4.1 Reactor Core Safety Limits (SLs)
SHUTDOWN MARGIN (SOM)
Moderator Temperature Coefficient (MTC)
Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits PHYSICS TESTS Exceptions - MODE 2 Heat Flux Hot Channel Factor (Fo(Z))
Nuclear Enthalpy Rise Hot Channel Factor (FNAH)
AXIAL FLUX DIFFERENCE (AFD)
Departure from Nucleate Boiling Ratio (DNBR)
Reactor Trip System (RTS) Instrumentation Boron Dilution Protection System (BOPS)
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 (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 19 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 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.
14?] psra 5BO-+-__,___._____._ __..__..__....._ ______ ____._ _________..__......___,_-+____.__..__.,__-+-__.____,___.__
0 0.2 OA n6
~B 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
2.2 2.3 COLR BRAIDWOOD 1 Revision 19 Page 3 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 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.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).
Moderator Temperature Coefficient (MTG) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTG) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.607 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 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.5 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) 225 110
'2
==
ra..
"C
.r: -
~
Ill 0..
II) -
~
C 0
- 2 Ill 0 a.
.II::
C ra lD "C
0 0:::
COLR BRAIDWOOD 1 Revision 19 Page 4 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224)
(77%, 224) 220 200 180 160 140 120 100 80 60 40 20 I"
I"
/ V
/ V
/[BANKB
/
/~
I
/
V
--IL
/
j(O%, 162)
I
/
IBANKC r-
/
/'
r
/
/
/
/
IBANKD I
/
/ V V
-/-
f---.. *-
/
"I(*%, 47l I
/
~
i(3001o, *)v (100%, 161) 0 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 S P S 100)
Where P is defined as the core power (in percent).
2.6 COLR BRAIDWOOD 1 Revision 19 Page 5 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Heat Flux Hot Channel Factor (Fo(Z}) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
pRTP FQ (Z) :::;-Q-xK(Z) for P:::; 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 F8TP = 2.60 K(Z) is provided in Figure 2.6.1.
1.1 1
0.9 0.8 N o.7 0
- u.
'g 0.6
.t::!
n:s E o.5 0 z
~ 0.4
~
0.3 0.2 0.1 0
Figure 2.6.1 K(Z) - Normalized F 0(2) as a Function of Core Height (0.0, 1.0)
(6.0, 1.0)
(12.0, 1.0) 4111111$1111tLOCA Limiting Envelope 0
2 3
4 5
6 7
8 9
10 11 12 BOTTOM Core Height (ft)
COLR BRAIDWOOD 1 Revision 19 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 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 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 B.1 and B.2.
2.6.3 Uncertainty
The uncertainty, Urn, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula where:
Uqu = Base Fo measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS and cannot be less than 1.05 when OPERABLE.)
Ue = Engineering uncertainty factor= 1.03 2.6.4 PDMS Alarms:
Fo(Z) Warning Setpoint = 2% Fo(Z) Margin Fo(Z) Alarm Setpoint = 0% Fo(Z) Margin
COLR BRAIDWOOD 1 Revision 19 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 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 6000 14000 (feet)
MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2283 1.3268 1.2684 0.20 1.2218 1.3180 1.2623 0.40 1.2223 1.3163 1.2642 0.60 1.2267 1.3162 1.2707 0.80 1.2357 1.3202 1.2825 1.00 1.2354 1.3139 1.2849 1.20 1.2263 1.2997 1.2778 1.40 1.2131 1.2814 1.2669 1.60 1.1997 1.2619 1.2556 1.80 1.1852 1.2410 1.2433 2.00 1.1694 1.2186 1.2297 2.20 1.1529 1.1952 1.2150 2.40 1.1360 1.1719 1.1999 2.60 1.1189 1.1500 1.1847 2.80 1.1096 1.1291 1.1699 3.00 1.1079 1.1141 1.1537 3.20 1.1077 1.1078 1.1427 3.40 1.1069 1.1068 1.1422 3.60 1.1058 1.1057 1.1422 3.80 1.1043 1.1043 1.1446 4.00 1.1020 1.1026 1.1479 4.20 1.1012 1.1002 1.1501 4.40 1.1042 1.0976 1.1519 4.60 1.1063 1.0972 1.1528 4.80 1.1084 1.0975 1.1529 5.00 1.1112 1.0987 1.1521 5.20 1.1140 1.1003 1.1502 5.40 1.1161 1.1012 1.1473 5.60 1.1171 1.1023 1.1440 5.80 1.1203 1.1052 1.1426 6.00 1.1296 1.1097 1.1455 6.20 1.1432 1.1128 1.1561 6.40 1.1557 1.1160 1.1646 6.60 1.1679 1.1306 1.1732 6.80 1.1796 1.1466 1.1807 7.00 1.1901 1.1598 1.1860 7.20 1.1990 1.1719 1.1895 7.40 1.2062 1.1823 1.1911 7.60 1.2114 1.1912 1.1905 7.80 1.2148 1.1968 1.1879 8.00 1.2152 1.2046 1.1830 8.20 1.2149 1.2174 1.1777 8.40 1.2196 1.2288 1.1756 8.60 1.2236 1.2440 1.1743 8.80 1.2282 1.2594 1.1761 9.00 1.2409 1.2739 1.1853 9.20 1.2639 1.2849 1.1999 9.40 1.2879 1.2891 1.2155 9.60 1.3074 1.3190 1.2265 9.80 1.3237 1.3581 1.2363 10.00 1.3450 1.3926 1.2437 10.20 1.3737 1.4261 1.2457 10.40 1.3979 1.4551 1.2478 10.60 1.4202 1.4798 1.2486 10.80 1.4450 1.5030 1.2552 11.00 1.4617 1.5225 1.2625 11.20 1.4549 1.5265 1.2557 11.40 1.4041 1.4859 1.2196 11.60 1.3553 1.4408 1.1855 11.80 1.3554 1.4385 1.1720 12.00 (core top) 1.3450 1.4257 1.1531 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burn ups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 20000 MWD/MTU 1.1884 1.1802 1.1814 1.1882 1.2017 1.2065 1.2011 1.1920 1.1832 1.1739 1.1635 1.1525 1.1411 1.1294 1.1236 1.1252 1.1305 1.1349 1.1396 1.1480 1.1577 1.1664 1.1742 1.1808 1.1858 1.1902 1.1945 1.1974 1.1980 1.2000 1.2078 1.2192 1.2278 1.2353 1.2408 1.2435 1.2439 1.2416 1.2367 1.2294 1.2189 1.2076 1.2015 1.1997 1.2032 1.2146 1.2253 1.2312 1.2373 1.2402 1.2477 1.2661 1.2801 1.2912 1.3029 1.3085 1.2971 1.2576 1.2128 1.1947 1.1685
COLR BRAIDWOOD 1 Revision 19 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Table 2.6.2.b W(Z) versus Core Heightfor 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 6000 14000 (feet)
MWD/MTU MWD/MTU MWD/MTU 0.00 !core bottom) 1.3180 1.4105 1.3507 0.20 1.3109 1.4008 1.3435 0.40 1.3111 1.3974 1.3445 0.60 1.3153 1.3978 1.3505 0.80 1.3242 1.4012 1.3618 1.00 1.3230 1.3937 1.3628 1.20 1.3125 1.3780 1.3540 1.40 1.2977 1.3580 1.3410 1.60 1.2823 1.3366 1.3275 1.80 1.2656 1.3136 1.3126 2.00 1.2473 1.2889 1.2961 2.20 1.2278 1.2633 1.2783 2.40 1.2079 1.2388 1.2598 2.60 1.1888 1.2174 1.2409 2.80 1.1710 1.1960 1.2247 3.00 1.1629 1.1776 1.2144 3.20 1.1620 1.1659 1.2078 3.40 1.1587 1.1600 1.2012 3.60 1.1552 1.1554 1.1951 3.80 1.1512 1.1526 1.1908 4.00 1.1461 1.1503 1.1880 4.20 1.1415 1.1472 1.1854 4.40 1.1395 1.1436 1.1818 4.60 1.1371 1.1395 1.1774 4.80 1.1341 1.1347 1.1718 5.00 1.1305 1.1293 1.1659 5.20 1.1263 1.1233 1.1604 5.40 1.1218 1.1165 1.1541 5.60 1.1181 1.1081 1.1455 5.80 1.1212 1.1075 1.1449 6.00 1.1309 1.1102 1.1532 6.20 1.1425 1.1144 1.1638 6.40 1.1525 1.1174 1.1720 6.60 1.1623 1.1203 1.1802 6.80 1.1721 1.1287 1.1871 7.00 1.1824 1.1415 1.1919 7.20 1.1926 1.1545 1.1947 7.40 1.2013 1.1664 1.1955 7.60 1.2083 1.1771 1.1941 7.80 1.2138 1.1867 1.1908 8.00 1.2175 1.1950 1.1847 8.20 1.2194 1.2022 1.1779 8.40 1.2196 1.2082 1.1759 8.60 1.2174 1.2119 1.1738 8.80 1.2184 1.2188 1.1762 9.00 1.2250 1.2312 1.1871 9.20 1.2462 1.2529 1.2013 9.40 1.2723 1.2911 1.2167 9.60 1.2977 1.3308 1.2275 9.80 1.3206 1.3678 1.2370 10.00 1.3410 1.4033 1.2441 10.20 1.3586 1.4367 1.2458 10.40 1.3740 1.4657 1.2475 10.60 1.3882 1.4904 1.2480 10.80 1.4052 1.5136 1.2541 11.00 1.4148 1.5330 1.2608 11.20 1.4022 1.5367 1.2538 11.40 1.3463 1.4956 1.2172 11.60 1.3081 1.4499 1.1852 11.80 1.3030 1.4474 1.1712 12.00 (core too) 1.2922 1.4343 1.1919 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 1.3237 1.3136 1.3136 1.3196 1.3327 1.3356 1.3276 1.3153 1.3030 1.2897 1.2748 1.2588 1.2420 1.2248 1.2075 1.1935 1.1843 1.1797 1.1833 1.1892 1.1956 1.2008 1.2050 1.2079 1.2091 1.2088 1.2064 1.2028 1.2034 1.2090 1.2192 1.2307 1.2395 1.2473 1.2528 1.2555 1.2555 1.2527 1.2473 1.2394 1.2281 1.2161 1.2093 1.2070 1.2124 1.2266 1.2371 1.2431 1.2491 1.2519 1.2593 1.2777 1.2915 1.3024 1.3139 1.3194 1.3078 1.2677 1.2224 1.2039 1.1773
COLR BRAIDWOOD 1 Revision 19 Page 9 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWD/MTU)
Fac(z) 0 1.0200 150 1.0400 700 1.0800 1000 1.0800 1590 1.0595 2000 1.0450 2370 1.0330 2800 1.0260 3910 1.0250 4129 1.0200 6782 1.0200 7600 1.0330 8100 1.0310 8600 1.0310 9500 1.0260 10541 1.0200 20489 1.0200 21000 1.0300 21500 1.0330 24603 1.0330 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 Faw(Z) Exceeds Its Limits Required FoW(Z)
THERMAL POWER Negative AFD Band Positive AFD Band Margin Improvement Reduction (% RTP)
Reduction (% AFD)
Reduction (% AFD) s 1%
~3%
~ 1%
~ 1%
>1%ANDS2%
~6%
~2%
~2%
> 2%AND S3%
~9%
~3%
~3%
>3%
~50%
N/A NIA
2.7 COLR BRAIDWOOD 1 Revision 19 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Nuclear Enthalpy Rise Hot Channel Factor (FN,.,H) (LCO 3.2.2) 2.7.1 FNt.H ~ F§i1iP[1.0 + PFt.H(1.0 - P)]
where: P = the ratio of THERMAL POWER to RA TED THERMAL POWER (RTP)
F§~P = 1.70 PFt.H = 0.3
2.7.2 Uncertainty
The uncertainty, UFt.H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNt.H shall be calculated by the following formula:
where:
UFAHm = Base FN,.,H measurement uncertainty = 1.04 when PDMS is inoperable (UFt.Hm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)
2.7.3 PDMS Alarms:
FNt.H Warning Setpoint = 2% FN,.,H Margin FNt.H Alarm Setpoint = 0% FNt.H Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.9 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.
Departure from Nucleate Boiling Ratio (DNBR) (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 I Revision 19 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 24 Figure 2.8.1.a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power
~-----------------------------------
Normal Axial Flux Difference Limits 120 I (-10, 10oi I I (+10, 10oi 1 100 a:
w s 0
80 C.
...I
<(
~
a:
w 60
- c I-Una ceptab e I
\\
u,accept, ble OJ, eration I
\\
Dperatu n Acee,table
\\
I Oper ation
\\
C w
I
~ 40 a: -
I I
I (-20, SO) I I (+25, 50) I 0
20 0
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 1 Revision 19 Page 12 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 Figure 2.8.1.b:
120 100 c::::
w s 0
80 0..
...I
<C
~
c::::
w 60
- c I-0 w
~ 40 c:::: -
0 20..
0
-50 Una o,
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits I (-15, 10oi I 1 (+10, 100) I
~ceptab e I V
\\
~eration V
\\
Acee )table
\\
/
Opel ation
\\
U1
- accept, ble Jperatic n I (-35 50) I I
I I (+25, 50) I I
I I
I
-40
-30
-20
-10 0
10 20 30 40 AXIAL FLUX DIFFERENCE (%)
50
COLR BRAIDWOOD 1 Revision 19 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 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 Tav9 coefficient K2 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 Tav9 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 't1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant 't2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant 't3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant 't4 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 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 +3.4 7% / % Al.
2.10.15 The f1 (Al) "negative" slope shall be -2.61 % / % Al.
COLR BRAIDWOOD 1 Revision 19 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 24 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing Tavg.
2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg.
2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0.00245 I °F when T > T".
2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0 / °F when T:::;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 AT lead/lag time constant -r1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel~ T lead/lag time constant -r2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant 't3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant -re shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant 't7 shall be equal to 10 sec.
2.11.12 The fa (~I) "positive" breakpoint shall be O for all Al.
2.11.13 The fa (~I) "negative" breakpoint shall be O for all Al.
2.11.14 The fa (~I) "positive" slope shall be O for all Al.
2.11.15 The fa (~I) "negative" slope shall be O for all Al.
COLR BRAIDWOOD I Revision 19 Page 15 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 24 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) 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:::; 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 1750 b) for cycle burnups ::c: 0 MWD/MTU 1895 and < 16000 MWD/MTU c) for cycle burnups ::c: 16000 MWD/MTU 1511 2.13.2 a) prior to initial criticality 1830 b) for cycle burnups ::c: 0 MWD/MTU and < 16000 MWD/MTU 2132 c) for cycle burnups ::c: 16000 1661 MWD/MTU