BW240061, Core Operating Limits Report, Cycle 25, Revision 17

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Core Operating Limits Report, Cycle 25, Revision 17
ML24291A002
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Site: Braidwood Constellation icon.png
Issue date: 10/17/2024
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Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
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Text

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 25 CONSTELLATION TRACKING ID:

COLR BRAIDWOOD 2 REVISION 17

COLR BRAIDWOOD 2 Revision 17 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 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 (Fo(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN8H)

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.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 2 Revision 17 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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

~--.

~

cu 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.

2-r' 1 p,;,ia

- 2250 p-;ia

~

2000 pc;ia

~ ------

I-

-~---.

1860 p,;,ia I-I-

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COLR BRAIDWOOD 2 Revision 17 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 2.2 SHUTDOWN MARGIN (SDM) 2.3 2.4 The SDM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SDM shall be greater than or equal to 1.3% L\\.k/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 SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% L\\.k/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 BOUARO/HZP-MTC upper limit shall be +3.233 x 10-5 L\\.k/k/°F.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10-4 L\\.k/k/°F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 L\\.k/k/°F.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 L\\.k/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.

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) 231 115

COLR BRAIDWOOD 2 Revision 17 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224)

(77%, 224) 220 200 180 c

3 160 I'!,,

.c -

~ 140 Ill Q.

Cl) -

~ 120 C

0

.:i "iii 0 100 ll.

.x:

C ca DJ 80 0

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60 40 20

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VcsANKB

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-*-*---- ----*-- --~~ -

/

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V V !BANK D I

/

/

V

/

/

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, r1 (0%, 47) I

~

~v 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 Pis defined as the core power (in percent).

(100%, 161)

2.6 COLR BRAIDWOOD 2 Revision 17 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Heat Flux Hot Channel Factor {Fa(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

1.1 pRTP FQ (Z) s _Q_xK(Z) for P s 0.5 0.5 pRTP FQ (Z) s _Q_xK(Z) for P > 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 --------------:------------*

0.9

  • 0.8
  • N ao.1, LL Cl)

-~ 0.6, nl E

o 0.5, z

N

~0.4' 0.3,

0.2,

0.1,

I ~LOCA Limiting I Envelope 0 +----------.----....------------.---..

0 1

2 3

4 BOTTOM 5

6 7

Core Height (ft) 8 9

10 11 12 TOP

COLR BRAIDWOOD 2 Revision 17 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 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 FaC(Z) penalty factors that are greater than 2% per the allowable surveillance frequency. These values shall be used to increase the FaW(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 UFQ =Ugu*U, where:

U9u = Base Fa measurement uncertainty = 1.05 when PDMS is inoperable (U9u 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 2 Revision 17 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Table 2.6.2.a W(Z) versus Core Height for Nonnal 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 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2395 1.3520 1.2243 0.20 1.2336 1.3428 1.2181 0.40 1.2353 1.3412 1.2204 0.60 1.2413 1.3416 1.2275 0.80 1.2526 1.3464 1.2403 1.00 1.2541 1.3401 1.2431 1.20 1.2458 1.3254 1.2361 1.40 1.2334 1.3063 1.2250 1.60 1.2207 1.2861 1.2136 1.80 1.2069 1.2643 1.2013 2.00 1.1918 1.2409 1.1876 2.20 1.1753 1.2166 1.1729 2.40 1.1590 1.1920 1.1579 2.60 1.1474 1.1675 1.1452 2.80 1.1402 1.1484 1.1409 3.00 1.1336 1.1366 1.1400 3.20 1.1284 1.1307 1.1384 3.40 1.1269 1.1274 1.1366 3.60 1.1244 1.1240 1.1344 3.80 1.1245 1.1202 1.1338 4.00 1.1259 1.1162 1.1351 4.20 1.1263 1.1111 1.1385 4.40 1.1265 1.1061 1.1409 4.60 1.1262 1.1061 1.1428 4.80 1.1254 1.1078 1.1438 5.00 1.1242 1.1091 1.1444 5.20 1.1220 1.1098 1.1452 5.40 1.1194 1.1099 1.1457 5.60 1.1207 1.1102 1.1448 5.80 1.1252 1.1139 1.1454 6.00 1.1322 1.1199 1.1499 6.20 1.1405 1.1251 1.1606 6.40 1.1485 1.1292 1.1685 6.60 1.1561 1.1348 1.1765 6.80 1.1637 1.1427 1.1834 7.00 1.1719 1.1525 1.1881 7.20 1.1800 1.1631 1.1909 7.40 1.1866 1.1724 1.1917 7.60 1.1916 1.1804 1.1903 7.80 1.1951 1.1870 1.1869 8.00 1.1969 1.1920 1.1809 8.20 1.1970 1.1957 1.1743 8.40 1.1955 1.1980 1.1720 8.60 1.1920 1.1981 1.1698 8.80 1.1903 1.2008 1.1701 9.00 1.1936 1.2045 1.1758 9.20 1.2110 1.2143 1.1898 9.40 1.2347 1.2494 1.2145 9.60 1.2591 1.2865 1.2404 9.80 1.2829 1.3221 1.2649 10.00 1.3060 1.3574 1.2876 10.20 1.3265 1.3911 1.3081 10.40 1.3433 1.4278 1.3299 10.60 1.3599 1.4646 1.3510 10.80 1.3793 1.4794 1.3566 11.00 1.4040 1.4883 1.3584 11.20 1.4150 1.5028 1.3627 11.40 1.3537 1.4572 1.3307 11.60 1.3020 1.4192 1.2943 11.80 1.2944 1.4250 1.2945 12.00 (core top) 1.2838 1.4332 1.2862 Note: W(Z) values at 22000 MWD/MTU may be applied to cycle burnups greater than 22000 MWD/MTU to prevent W(Z) function extrapolation 22000 MWD/MTU 1.1972 1.1874 1.1885 1.1959 1.2112 1.2170 1.2113 1.2016 1.1923 1.1825 1.1716 1.1599 1.1480 1.1361 1.1244 1.1118 1.1067 1.1116 1.1252 1.1391 1.1522 1.1648 1.1762 1.1864 1.1951 1.2021 1.2072 1.2103 1.2143 1.2195 1.2283 1.2396 1.2480 1.2551 1.2600 1.2620 1.2613 1.2578 1.2514 1.2425 1.2303 1.2169 1.2085 1.2085 1.2159 1.2285 1.2371 1.2483 1.2540 1.2633 1.2792 1.2943 1.3060 1.3151 1.3230 1.3301 1.3270 1.2892 1.2482 1.2429 1.2285

COLR BRAIDWOOD 2 Revision 17 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 6000 14000 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3659 1.4670 1.3126 0.20 1.3583 1.4567 1.3057 0.40 1.3588 1.4546 1.3077 0.60 1.3637 1.4544 1.3148 0.80 1.3741 1.4588 1.3278 1.00 1.3730 1.4510 1.3301 1.20 1.3618 1.4344 1.3220 1.40 1.3459 1.4131 1.3096 1.60 1.3293 1.3903 1.2967 1.80 1.3111 1.3656 1.2827 2.00 1.2911 1.3390 1.2669 2.20 1.2697 1.3110 1.2502 2.40 1.2477 1.2827 1.2326 2.60 1.2270 1.2545 1.2143 2.80 1.2079 1.2262 1.2045 3.00 1.1925 1.2019 1.1995 3.20 1.1832 1.1860 1.1943 3.40 1.1787 1.1787 1.1886 3.60 1.1745 1.1762 1.1824 3.80 1.1699 1.1736 1.1765 4.00 1.1644 1.1702 1.1739 4.20 1.1591 1.1664 1.1735 4.40 1.1552 1.1619 1.1718 4.60 1.1506 1.1567 1.1694 4.80 1.1452 1.1509 1.1659 5.00 1.1393 1.1442 1.1621 5.20 1.1326 1.1370 1.1588 5.40 1.1258 1.1288 1.1544 5.60 1.1229 1.1189 1.1471 5.80 1.1257 1.1172 1.1517 6.00 1.1347 1.1198 1.1647 6.20 1.1439 1.1254 1.1763 6.40 1.1517 1.1304 1.1861 6.60 1.1591 1.1386 1.1955 6.80 1.1664 1.1473 1.2036 7.00 1.1743 1.1565 1.2095 7.20 1.1821 1.1667 1.2132 7.40 1.1884 1.1757 1.2147 7.60 1.1931 1.1833 1.2138 7.80 1.1962 1.1894 1.2108 8.00 1.1976 1.1940 1.2047 8.20 1.1974 1.1971 1.1979 8.40 1.1956 1.1988 1.1958 8.60 1.1916 1.1983 1.1929 8.80 1.1904 1.2003 1.1958 9.00 1.1943 1.2042 1.2065 9.20 1.2118 1.2151 1.2209 9.40 1.2355 1.2502 1.2366 9.60 1.2597 1.2870 1.2494 9.80 1.2835 1.3226 1.2660 10.00 1.3064 1.3576 1.2855 10.20 1.3267 1.3911 1.3015 10.40 1.3434 1.4275 1.3193 10.60 1.3598 1.4640 1.3366 10.80 1.3790 1.4786 1.3388 11.00 1.4035 1.4872 1.3378 11.20 1.4143 1.5014 1.3391 11.40 1.3529 1.4555 1.3053 11.60 1.3011 1.4174 1.2656 11.80 1.2934 1.4230 1.2644 12.00 (core tool 1.2826 1.4308 1.2535 Note: W(Z) values at 22000 MWD/MTU may be applied to cycle bumups greater than 22000 MWD/MTU to prevent W(Z) function extrapolation 22000 MWD/MTU 1.2877 1.2642 1.2614 1.2637 1.2809 1.2836 1.2778 1.2678 1.2556 1.2441 1.2343 1.2250 1.2153 1.2056 1.1963 1.1854 1.1796 1.1818 1.1911 1.2003 1.2085 1.2157 1.2216 1.2259 1.2284 1.2291 1.2276 1.2254 1.2278 1.2349 1.2434 1.2505 1.2554 1.2584 1.2619 1.2644 1.2638 1.2607 1.2551 1.2470 1.2368 1.2244 1.2103 1.2007 1.1971 1.1946 1.1921 1.1992 1.2184 1.2397 1.2581 1.2745 1.2876 1.2987 1.3083 1.3157 1.3124 1.2768 1.2370 1.2323 1.2188

COLR BRAIDWOOD 2 Revision 17 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Table 2.6.2.c Penalty Factors in Excess of 2%

Cycle Burnup Penalty Factor (MWD/MTU)

Foc(Z) 150 1.0200 1050 1.0400 2140 1.0600 2500 1.0650 3000 1.0650 3500 1.0510 4000 1.0410 4850 1.0200 6500 1.0200 6900 1.0260 7250 1.0340 7700 1.0340 7950 1.0300 8200 1.0280 8450 1.0240 8600 1.0200 20500 1.0200 20800 1.0270 21800 1.0270 22400 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 Margin Improvement Reduction (% RTP)

Reduction (% AFD)

Reduction (% AFD) s 1%

-
3%
,; 1%
,; 1%

> 1% AND s 2%

-
6%
-
2%
-
2%

> 2%AND s 3%

-
9%
-
3%
-
3%

>3%

-
so%

N/A N/A

2.7 COLR BRAIDWOOD 2 Revision 17 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Nuclear Enthalpy Rise Hot Channel Factor (FN11.H) (LCO 3.2.2) where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F~~P = 1.70 PF11.H = 0.3

2.7.2 Uncertainty

The uncertainty, UF11.H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN11.H shall be calculated by the following formula:

where:

UFAHm = Base FN11.H measurement uncertainty= 1.04 when PDMS is inoperable (UF11.Hm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)

2.7.3 PDMS Alarms:

FN11.H Warning Setpoint = 2% FN11.H Margin FN11.H Alarm Setpoint = 0% FN11.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 2 Revision 17 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power r-------------- --------- ---- --- -- -- - - - -

--*s--*--*----- -------

1 Normal Axial Flux Difference Limits I

120 I

1 1 :BT 1 I

1 1

I I

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' L ' '

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I j_ _____ 7L ________ J__

(-10, 100) I (+10, 100) I

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i ffi I

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l i

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~ 80 ~-- JJ~e!a_~,~------- !------- _________ !------~--

uiaccep~~ble O,i>eration/

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  • 1 r ~;:t:~:~+

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. Ti (*20, SO),_,.

  • - ~*t (+25, SO)

- l 20 }--+--Jl __ j I

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100

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 17 Page 12 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power 1-*-------

Expanded Axial Flux Difference Limits i

a:

w 3:

120 100

~ 80

...I

<C

~

a:

w 60

c I-C w

~ 40 a: -

I II I

  • _____ Unafceptab!e____

. l

--~~~-l-r~~=-----i I

O~erationi i

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. *1*'"*--------*7--------------,--. ----+ ~---+----+-------!

1 i Operiation i I

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T-----._,_(-_3_s_, s_o_)~ ----+--------1--------*-1-**---- !-- ----- (+2s, so) 0

~

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i 20 r------1------+-1---+----+1- __

j __________ L

_______________.I*-----------------+--- -

. --~

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-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

i

' '----* ~--*****-----**---

-*-*--*-------*--*-*-------------------------------------------- _____ J

COLR BRAIDWOOD 2 Revision 17 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature L\\ T Setpoint Parameter Values 2.10.1 The Overtemperature L\\ T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature L\\ T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / °F.

2.10.3 The Overtemperature L\\ T 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 583.5 °F.

2.10.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.

2.10.6 The measured reactor vessel L\\ T lead/lag time constant 11 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel L\\ T lead/lag time constant 12 shall be equal to 3 sec.

2.10.8 The measured reactor vessel L\\ T lag time constant 13 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant 14 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant 1s shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 1s shall be less than or equal to 2 sec.

2.10.12 The f1 (L\\I) "positive" breakpoint shall be +10% L\\I.

2.10.13 The f1 (L\\I) "negative" breakpoint shall be -18% L\\I.

2.10.14 The f1 (L\\I) "positive" slope shall be +3.47% / % L\\I.

2.10.15 The f1 (L\\I) "negative" slope shall be -2.61 % I% L\\I.

COLR BRAIDWOOD 2 Revision 17 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 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 T avg.

2.11.4 The Overpower £\\ T reactor trip setpoint T avg heatup coefficient Ks shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ks 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 583.5 °F.

2.11.7 The measured reactor vessel £\\T lead/lag time constanh-1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT 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,s shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant,1 shall be equal to 10 sec.

2.11.12 The fa (Al) "positive" breakpoint shall be 0 for all £\\I.

2.11.13 The fa (£\\I) "negative" breakpoint shall be 0 for all £\\I.

2.11.14 The fa (£\\I) "positive" slope shall be 0 for all £\\I.

2.11.15 The fa (£\\I) "negative" slope shall be 0 for all £\\I.

COLR BRAIDWOOD 2 Revision 17 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 25 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 588.6 °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 values given in the Table below.

COLR Boron Concentration Section Conditions (ppm) 2.13.1 a) prior to initial criticality 1746 b) for cycle burnups ~ 0 MWD/MTU 1898 and < 16000 MWD/MTU c) for cycle burnups ~ 16,000 MWD/MTU 1522 2.13.2 a) prior to initial criticality 1813 b) for cycle burnups ~ 0 MWD/MTU and<

2122 16000 MWD/MTU c) for cycle burnups ~ 16000 MWD/MTU 1658

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