ML22166A015
| ML22166A015 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/15/2022 |
| From: | Constellation Energy Company |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22166A013 | List: |
| References | |
| BW220036 | |
| Download: ML22166A015 (16) | |
Text
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 23 CONSTELLATION TRACKING ID:
COLR BRAIDWOOD 1 REVISION 18
COLR BRAIDWOOD 1 Revision 18 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 23 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 (Fo(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN.iH)
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 Boration Flow Paths - Operating TRM TLCO 3.1.d Charging Pumps - Operating TRM TLCO 3.1.f Borated Water Sources - Operating TRM TLCO 3.1.g Position Indication System - Shutdown TRM TLCO 3.1.h Shutdown Margin (SOM) - MODE 1 and MODE 2 with keff ::c: 1.0 TRM TLCO 3.1.i Shutdown Margin (SOM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)
COLR BRAIDWOOD 1 Revision 18 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 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.
680--.--------.-------,------,-------,-------.------,
2471 psia Li._
660 2250 psia 0,
(L) c::i
(]_)
\,._ 640
- J
~.,-
0
\,._
Q}
o__
1860 psia E ..............
(]_)
f--
620
(]_)
er, 0
(]_)
<(
600 580-1-__.___._....._-+-__,__..._...._-+-____._.,__....._--+---'-....._-'--+-'--.......--'---+-.,__.....__._---I 0 Q.2 0.4 G.6 0.8 Fruction of i\Jornincil Power Figure 2.1.1: Reactor Core Limits
COLR BRAIDWOOD 1 Revision 18 Page 3 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 2.2 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% 11k/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% 11k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 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 +2.233 x 10- 5 11k/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 11k/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 11k/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 11k/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
COLR BRAIDWOOD I Revision 18 Page4ofl5 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 23 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 r r
/
V /
/ I 200 180 ~
/[BANKB I
/
'2 /, /
3: 160 f
"0
.s:::.
~ 140 1(0%, 162)
I
. ---*- >---~----
IL1 IBANKC I
-7 (100%, 161)
/ /
ti)
C.
.s
!!!. 120 C
0 "iii
/~ i
/
/
0 100 ll.
.ll: / V IBANKD I C
Ill ID 80 / /
"0 0
a::: V V 60 / /
40
/
- "l(0%, 47) I
/
V I
20
~/ I 1(30%.0)v 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 SP S 100)
Where P is defined as the core power (in percent).
COLR BRAIDWOOD I Revision 18 Page5ofl5 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 23 2.6 Heat Flux Hot Channel Factor {Fo(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
pRTP FQ(Z) :s;-Q-xK(Z) forP:s;0.5 0.5 pRTP FQ(Z)~-Q-xK(Z) forP>0.5 p
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F&TP = 2.60 K(Z) is provided in Figure 2.6.1.
Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height (0.0, 1.0) (6.0, 1.0) (12.0, 1.0) 1.1 0.9 0.8 N 0.7 0
'C Cl) 0.6 ia
...0 E 0.5
~
z I -.-LOCA Limiting N 0.4 Envelope
~ I 0.3 0.2 0.1 0
0 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
COLR BRAIDWOOD 1 Revision 18 Page6ofl5 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNfT 1 CYCLE 23 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 8.1 and 8.2.
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 I Revision 18 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 23 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 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3178 1.4068 1.1995 1.1873 0.20 1.3105 1.3970 1.1937 1.1789 0.40 1.3108 1.3931 1.1957 1.1798 0.60 1.3.129 1.3925 1.2022 1.1863 0.80 1.3201 1.3946 1.2140 1.1995 1.00 1.3173 1.3861 1.2170 1.2041 1.20 1.3059 1.3698 1.2108 1.1985 1.40 1.2901 1.3493 1.2010 1.1893 1.60 1.2736 1.3273 1.1910 1.1805 1.80 1.2558 1.3035 1.1802 1.1712 2.00 1.2365 1.2780 1.1684 1.1609 2.20 1.2161 1.2515 1.1555 1.1499 2.40 1.1954 1.2248 1.1428 1.1388 2.60 1.17 49 1.1983 1.1345 1.1276 2.80 1.1538 1.1725 1.1317 1.1167 3.00 1.1383 1.1482 1.1314 1.1054 3.20 1 1315 1 1323 1.1312 1.1015 3.40 1.1299 1.1288 1.1307 1.1065 3.60 1.1289 1.1276 1.1297 1.1195 3.80 1.1275 1.1261 1.1298 1.1327 4.00 1.1256 1.1238 1.1328 1.1453 4.20 1.1233 1.1216 1.1375 1.1572 4.40 1.1204 1.1201 1.1412 1.1682 4.60 1.1174 1.1181 1.1442 1.1780 4.80 1.1171 1.1154 1.1463 1.1864 5.00 1.1177 1.1123 1.1479 1.1932 5.20 1.1171 1.1097 1.1496 1.1982 5.40 1.1160 1.1079 1.1510 1.2013 5.60 1.1156 1.1070 1.1512 1.2033 5.80 1.1178 1.1084 1.1513 1.2090 6.00 1.1258 1.1125 1.1553 1.2193 6.20 1.1378 1.1158 1.1667 1.2304 6.40 1.1505 1.1181 1.1755 1.2392 6.60 1.1619 1.1217 1.1844 1.2469 6.80 1.1718 1.1292 1.1920 1.2522 7.00 1.1802 1.1392 1.1973 1.2548 7.20 1.1868 1.1487 1.2007 1.2548 7.40 1.1915 1.1566 1.2020 1.2520 7.60 1.1945 1.1632 1.2010 1.2465 7.80 1.1943 1.1667 1.1979 1.2385 8.00 1.1955 1.1728 1.1923 1.2271 8.20 1.2023 1.1844 1.1865 1.2147 8.40 1.2074 1.1949 1.1843 1.2073 8.60 1.2154 1.2083 1.1817 1.2067 8.80 1.2241 1.2244 1.1838 1.2139 9.00 1.2358 1.2451 1.1922 1.2272 9.20 1.2488 1.2688 1.2063 1.2364 9.40 1.2556 1.2871 1.2281 1.2481 9.60 1.2756 1.3049 1.2492 1.2544 9.80 1.3048 1.3223 1.2684 1.2639 10.00 1.3347 1.3467 1.2863 1.2798 10.20 1.3612 1.3811 1.3020 1.2953 10.40 1.3847 1.4092 1.3146 1.3075 10.60 1.4044 1.4326 1.3242 1.3171 10.80 1.4243 1.4563 1.3321 1.3269 11.00 1.4364 1.4785 1.3368 1.3325 11.20 1.4266 1.4827 1.3304 1.3225 11.40 1.3723 1.4282 1.2916 1.2820 11.60 1.3207 . 1.3862 1.2473 1.2369 11.80 1.3209 1.3826 1.2260 1.2176 12.00 (core too) 1.3099 1.3776 1.2456 1.2470 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
COLR BRAIDWOOD 1 Revision 18 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 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 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.4330 1.4875 1.3002 1.2934 0.20 1.4012 1.4765 1.2938 1.2833 0.40 1.3889 1.4715 1.2956 1.2833 0.60 1.3909 1.4703 1.3023 1.2892 0.80 1.3992 1.4714 1.3145 1.3021 1.00 1.3929 1.4615 1.3172 1.3052 1.20 1.3809 1.4436 1.3102 1.2976 1.40 1.3639 1.4213 1.2994 1.2859 1.60 1.3439 1.3973 1.2884 1.2744 1.80 1.3240 1.3715 1.2764 1.2620 2.00 1.3026 1.3439 1.2631 1.2483 2.20 1.2811 1.3152 1.2488 1.2335 2.40 1.2617 1.2862 1.2340 1.2182 2.60 1.2423 1.2573 1.2191 1.2027 2.80 1.2221 1.2307 1.2036 1.1857 3.00 1.2051 1.2117 1.1922 1.1746 3.20 1.1940 1 1990 1.1865 1.1737 3.40 1.1878 1.1884 1.1831 1.1784 3.60 1.1837 1.1819 1.1808 1.1825 3.80 1.1791 1.1754 1.1816 1.1884 4.00 1.1744 1.1700 1.1831 1.1952 4.20 1.1700 1.1660 1.1835 1.2009 4.40 1.16.48 1.1609 1.1832 1.2055 4.60 1.1590 1.1550 1.1818 1.2087 4.80 1.1524 1.1485 1.1794 1.2100 5.00 1.1451 1.1411 1.1757 1.2113 5.20 1.1372 1.1333 1.1709 1.2123 5.40 1.1285 1.1253 1.1646 1.2113 5.60 1.1178 1.1170 1.1563 1.2136 5.80 1.1174 1.1115 1.1586 1.2240 6.00 1.1261 1.1120 1.1709 1.2389 6.20 1.1377 1.1159 1.1847 1.2526 6.40 1.1504 1.1181 1.1960 1.2633 6.60 1.1617 1.1235 1.2053 1.2710 6.80 1.1715 1.1301 1.2123 1.2759 7.00 1.1798 1.1385 1.2170 1.2776 7.20 1.1863 1.1483 1.2192 1.2761 7.40 1.1909 1.1562 1.2189 1.2715 7.60 1.1938 1.1628 1.2164 1.2641 7.80 1.1936 1.1662 1.2097 1.2520 8.00 1.1947 1.1723 1.2058 1.2418 8.20 1.2015 1.1840 1.2056 1.2364 8.40 1.2067 1.1945 1.2048 1.2290 8.60 1.2146 1.2079 1.2057 1.2286 8.80 1.2239 1.2244 1.2124 1.2286 9.00 1.2361 1.2455 1.2256 1.2265 9.20 1.2491 1.2691 1.2403 1.2:l!55 9.40 1.2558 1.2875 1.2500 1.2339 9.60 1.2760 1.3052 1.2595 1.2541 9.80 1.3052 1.3226 1.2663 1.2765 10.00 1.3349 1.3470 1.2695 1.2961 10.20 1.3611 1.3812 1.2748 1.3137 10.40 1.3843 1.4091
- 1.2877 1.3278 10.60 1.4038 1.4324 1.2996 1.3395 10.80 1.4234 1.4559 1.3104 1.3512 11.00 1.4353 1.4779 1.3175 1.3574 11.20 1.4252 1.4820 1.3118 1.3475 11.40 1.3708 1.4273 1.2762 1.3078 11.60 1.3191 1.3852 1.2343 1.2625 11.80 1.3191 1.3815 1.2145 1.2433 12.00 (core top) 1.3079 1.3763 1.2340 1.2722 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
COLR BRAIDWOOD 1 Revision 18 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 23 Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWD/MTU) Foc(z) 0 1.0200 150 1.0560 371 1.0640 592 1.0622 812 1.0595 1254 1.0528 1475 1.0461 1695 1.0383 2137 1.0240 2358 1.0200
- 5669 1.0200 6111 1.0285 6553 1.0378 6773 1.0415 7215 1.0395 8098 1.0200 8981 1.0200 9202 1.0253 9423 1.0248 10527 1.0200 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 Marc:iin Improvement Reduction (% RTP) Reduction (% AFD) Reduction (% AFD)
- 5 1% 2:3% 2: 1% 2: 1%
>1%AND:52% 2: 6% 2: 2% 2: 2%
> 2% AND :5 3% 2: 9% 2: 3% 2: 3%
>3% 2: 50% N/A N/A
COLR BRAIDWOOD 1 Revision 18 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNdH} (LCO 3.2.2) where: P = the ratio ofTHERMAL POWER to RATED THERMAL POWER (RTP)
F§~P = 1.70 PFdH = 0.3
2.7.2 Uncertainty
The uncertainty, UFdH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNdH shall be calculated by the following formula:
where:
UFJHm = Base FNdH measurement uncertainty = 1.04 when PDMS is inoperable (UFdHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)
2.7.3 PDMS Alarms:
FNdH Warning Setpoint = 2% FNdH Margin FNdH Alarm Setpoint = 0% FNdH Margin 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 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL ;c: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER
2.9.2 PDMS Alarms:
DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin
COLR BRAIDWOOD l Revision 18 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 23 Figure 2.8.1.a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 120 t 1
1 1 (-10,: 100) I 1 (+10, 100) I t
i 100
!\\I 0:::
LU I i
3: Una;cceptab e I u 1accept, ble 0
C. 80 I ,Jperat1c n 01 Deration Il
....I
<(
- E 0::: Acee itable \
LU
- c 60 I-Ope1 ation .\
0 LU I
~ 40 I I 0:::
0
'cf-20 I (-20, SO)
I I (+25, 50) I 0 ..
-50 -40 -30 -W -W O W W 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 1 Revision 18 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 Figure 2.8.1.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 i I i
! I i I (-15, 100) I 1(+10, 100) I l ! !
100 I/ I
\
a:
LU I 3: I 0
- a. 80 Una~ceptab,e I u 1accept, ble
,erationv Jperatic n
...I
<t
~
a:
01 Acce1 ~table
\ I\
- c 60 LU I-C LU I
/I I Ope, ation
\
!;: I (-35, SO) ! I I 40 I (+25, SO) I a: I 0
20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE(%)
COLR BRAIDWOOD l Revision 18 Page 13 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 23 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature ~T Setpoint Parameter Values 2.10.1 The Overtemperature ~ T reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature ~ T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / °F.
2.10.3 The Overtemperature ~T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 / 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 ~ T lead/lag time constant ,1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel~ T lead/lag time constant ,2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel ~ T 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 (~I) "positive" breakpoint shall be +10% ~I.
2.10.13 The f1 (~I) "negative" breakpoint shall be -18% ~I.
2.10.14 The f1 (~I) "positive" slope shall be +3.47% /%~I.
2.10.15 The f1 (~I) "negative" slope shall be -2.61 % / % ~I.
COLR BRAIDWOOD 1 Revision 18 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 2.11 Reactor Trip System (RTS} Instrumentation (LCO 3.3.1) - Overpower~ T Setpoint Parameter Values 2.11.1 The Overpower~ T reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower~T reactor trip setpoint Tav9 rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing Tavg.
2.11.3 The Overpower~ T reactor trip setpoint Tav9 rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg.
2.11.4 The Overpower~ T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 I °F when T > T".
2.11.5 The Overpower~ T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to O / °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 ~T lead/lag time constant ,1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel ~ T lead/lag time constant ,2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel ~T lag time constant ,3 shall be less than or equal to 2 sec.
2.11.10
- The measured reactor vessel average temperature lag time constant ,6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant n shall be equal to 10 sec.
2.11.12 The fz (~I) "positive" breakpoint shall be 0 for all M 2.11.13 The f2 (~I) "negative" breakpoint shall be 0 for all ~I.
2.11.14 The fz (~I) "positive" slope shall be 0 for all M 2.11.15 The fz (~I) "negative" slope shall be 0 for all ~I.
COLR BRAIDWOOD 1 Revision 18 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 23 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 8.2 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 loom) 2.13.1 a) prior to initial criticality 1754 b) for cycle burnups 2: 0 MWD/MTU 1900 and < 16000 MWD/MTU c) for cycle burnups 2: 16000 MWD/MTU 1480 2.13.2 a) prior to initial criticality 1853 b) for cycle burnups 2: 0 MWD/MTU and < 16000 MWD/MTU 2126 c) for cycle burnups 2: 16000 1609 MWD/MTU