BW230027, Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 24, Rev. 16

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Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 24, Rev. 16
ML23130A008
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Site: Braidwood Constellation icon.png
Issue date: 05/10/2023
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Text

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 24 CONSTELLATION TRACKING ID:

COLR BRAIDWOOD 2 REVISION 16

COLR BRAIDWOOD 2 Revision 16 Page 1 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 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.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 16 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 L,_

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.

- 2r 1 p,1a

--~.....__

.. -------~--------------

- 22~0p,ia 2

')'1~:

2000 p,ia

--~

c,.:

c:,_

~

C;)

f--

(j_';

c*:

__ 1860 psia

~

~

~

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..,,,... 1 o.a Frucion :/ r,k,rr*inol l\\,1wcr Figure 2.1.1: Reactor Core Limits

2.2 2.3 2.4 2.5 COLR BRAIDWOOD 2 Revision 16 Page 3 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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.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 +2.729 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

'2 3::

ns...

'C

.c -

§:

1/)

C.

a, -

~

C:

0 E 1/)

0 a..

.lil:

C:

ns m

'C 0

0:::

COLR BRAIDWOOD 2 Revision 16 Page 4 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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

~~"*~7= ~~=="=cmmcTusc~so=*zo* =,,,~~c*n~~,,,~.,~,?*

V

/

/

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1(0%, 162) I L

/I

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IBANKC I

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i

/

V V IBANKD I

/

/ V

/

/

/

/

  • -'"l(o%, 47) I

/

~/

1(30%.. 0)v T

(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 SP S 100)

Where P is defined as the core power (in percent).

2.6 COLR BRAIDWOOD 2 Revision 16 Page 5 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 Heat Flux Hot Channel Factor (F a(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

1.1 1

0.9

  • 0.8 N

a0.7 *

11.

1J Cl)

~ 0.6 cu E

0 0.5 '

z N

~0.4 0.3,

0.2 0.1

  • 0 0

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 FcfTP = 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)

(6.0, 1.0)

(12.0, 1.0)

~

I ~LOCA Limiting I Envelope 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM Core Height (ft)

TOP

COLR BRAIDWOOD 2 Revision 16 Page 6 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 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 Faw(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, UFO, to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula U FQ = U qu

  • Ue where:

Uqu = Base Fa 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:

Fa(Z) Warning Setpoint = 2% Fa(Z) Margin Fa(Z) Alarm Setpoint = 0% Fa(Z) Margin

COLR BRAIDWOOD 2 Revision 16 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 4000 14000 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2817 1.3928 1.2334 0.20 1.2741 1.3815 1.2258 0.40 1.2744 1.3773 1.2315 0.60 1.2790 1.3771 1.2385 0.80 1.2887 1.3803 1.2533 1.00 1.2879 1.3718 1.2577 1.20 1.2774 1.3550 1.2514 1.40 1.2626 1.3338 1.2410 1.60 1.2473 1.3111 1.2305 1.80 1.2305 1.2867 1.2191 2.00 1.2134 1.2605 1.2062 2.20 1.1959 1.2334 1.1923 2.40 1.1780 1.2062 1.1781 2.60 1.1603 1.1795 1.1639 2.80 1.1421 1.1528 1.1490 3.00 1.1286 1.1316 1.1377 3.20 1.1224 1.1190 1.1327 3.40 1.1209 1.1135 1.1318 3.60 1.1210 1.1123 1.1313 3.80 1.1209 1.1111 1.1316 4.00 1.1206 1.1090 1.1341 4.20 1.1198 1.1071 1.1395 4.40 1.1186 1.1063 1.1438 4.60 1.1170 1.1062 1.1473 4.80 1.1145 1.1058 1.1501 5.00 1.1130 1.1050 1.1518 5.20 1.1127 1.1035 1.1524 5.40 1.1119 1.1015 1.1518 5.60 1.1134 1.1017 1.1505 5.80 1.1175 1.1042 1.1505 6.00 1.1242 1.1079 1.1546 6.20 1.1345 1.1116 1.1670 6.40 1.1477 1.1141 1.1779 6.60 1.1599 1.1143 1.1869 6.80 1.1716 1.1237 1.1939 7.00 1.1826 1.1382 1.1988 7.20 1.1918 1.1498 1.2014 7.40 1.1993 1.1607 1.2017 7.60 1.2049 1.1701 1.1999 7.80 1.2088 1.1783 1.1945 8.00 1.2096 1.1842 1.1915 8.20 1.2099 1.1900 1.1920 8.40 1.2153 1.2015 1.1921 8.60 1.2198 1.2124 1.1956 8.80 1.2264 1.2283 1.2022 9.00 1.2441 1.2548 1.2142 9.20 1.2709 1.2870 1.2296 9.40 1.2917 1.3141 1.2395 9.60 1.3120 1.3414 1.2493 9.80 1.3318 1.3653 1.2560 10.00 1.3571 1.3861 1.2601 10.20 1.3904 1.4071 1.2648 10.40 1.4184 1.4257 1.2684 10.60 1.4423 1.4436 1.2765 10.80 1.4642 1.4621 1.2847 11.00 1.4863 1.4852 1.2920 11.20 1.4888 1.4985 1.2909 11.40 1.4303 1.4722 1.2688 11.60 1.3857 1.4430 1.2419 11.80 1.3848 1.4402 1.2180 12.00 (core top) 1.3836 1.4300 1.1843 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 1.1912 1.1821 1.1841 1.1926 1.2091 1.2157 1.2103 1.2007 1.1917 1.1822 1.1714 1.1598 1.1479 1.1361 1.1236 1.1151 1.1164 1.1264 1.1358 1.1446 1.1544 1.1646 1.1738 1.1819 1.1884 1.1940 1.1992 1.2035 1.2054 1.2109 1.2215 1.2335 1.2429 1.2512 1.2572 1.2603 1.2607 1.2584 1.2533 1.2457 1.2347 1.2229 1.2164 1.2142 1.2200 1.2352 1.2463 1.2529 1.2598 1.2623 1.2674 1.2820 1.2929 1.3009 1.3076 1.3131 1.3078 1.2819 1.2527 1.2288 1.1950

COLR BRAIDWOOD 2 Revision 16 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 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) 1.3447 1.4555 1.2958 0.20 1.3364 1.4434 1.2887 0.40 1.3362 1.4386 1.2913 0.60 1.3406 1.4380 1.2994 0.80 1.3501 1.4407 1.3140 1.00 1.3483 1.4312 1.3177 1.20 1.3368 1.4131 1.3102 1.40 1.3206 1.3904 1.2984 1.60 1.3037 1.3661 1.2864 1.80 1.2853 1.3398 1.2732 2.00 1.2653 1.3117 1.2585 2.20 1.2441 1.2824 1.2425 2.40 1.2226 1.2529 1.2259 2.60 1.2014 1.2238 1.2091 2.80 1.1792 1.1950 1.1919 3.00 1.1653 1.1696 1.1765 3.20 1.1612 1.1549 1.1665 3.40 1.1590 1.1529 1.1624 3.60 1.1562 1.1510 1.1595 3.80 1.1529 1.1485 1.1570 4.00 1.1488 1.1458 1.1580 4.20 1.1446 1.1431 1.1614 4.40 1.1411 1.1405 1.1634 4.60 1.1372 1.1371 1.1647 4.80 1.1333 1.1331 1.1650 5.00 1.1292 1.1284 1.1641 5.20 1.1242 1.1231 1.1620 5.40 1.1187 1.1169 1.1587 5.60 1.1148 1.1095 1.1547 5.80 1.1173 1.1070 1.1556 6.00 1.1245 1.1077 1.1621 6.20 1.1345 1.1116 1.1767 6.40 1.1477 1.1139 1.1880 6.60 1.1597 1.1178 1.1972 6.80 1.1714 1.1258 1.2044 7.00 1.1822 1.1373 1.2093 7.20 1.1913 1.1495 1.2118 7.40 1.1988 1.1603 1.2119 7.60 1.2043 1.1696 1.2098 7.80 1.2081 1.1779 1.2040 8.00 1.2089 1.1837 1.2005 8.20 1.2092 1.1896 1.2006 8.40 1.2147 1.2012 1.2004 8.60 1.2189 1.2120 1.2028 8.80 1.2265 1.2283 1.2113 9.00 1.2451 1.2552 1.2259 9.20 1.2718 1.2874 1.2419 9.40 1.2925 1.3145 1.2525 9.60 1.3127 1.3417 1.2630 9.80 1.3323 1.3656 1.2702 10.00 1.3572 1.3864 1.2748 10.20 1.3903 1.4073 1.2799 10.40 1.4180 1.4258 1.2837 10.60 1.4416 1.4435 1.2926 10.80 1.4633 1.4620 1.3013 11.00 1.4851 1.4849 1.3087 11.20 1.4873 1.4981 1.3077 11.40 1.4287 1.4717 1.2854 11.60 1.3839 1.4424 1.2583 11.80 1.3829 1.4395 1.2341 12.00 (core top) 1.3814 1.4292 1.2000 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 1.2275 1.2179 1.2196 1.2279 1.2445 1.2506 1.2445 1.2341 1.2242 1.2134 1.2026 1.1926 1.1828 1.1733 1.1646 1.1591 1.1570 1.1567 1.1641 1.1742 1.1840 1.1928 1.2005 1.2069 1.2115 1.2145 1.2152 1.2141 1.2163 1.2254 1.2395 1.2537 1.2645 1.2725 1.2773 1.2791 1.2777 1.2731 1.2658 1.2538 1.2438 1.2390 1.2322 1.2290 1.2238 1.2216 1.2296 1.2410 1.2554 1.2741 1.2941 1.3110 1.3251 1.3368 1.3435 1.3499 1.3487 1.3218 1.2916 1.2655 1.2286

COLR BRAIDWOOD 2 Revision 16 Page 9 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 Table 2.6.2.c Penalty Factors in Excess of 2%

Cycle Burnup Penalty Factor (MWD/MTU)

Foc(Z) 0 1.0200 150 1.0800 370 1.0900 900 1.0900 1500 1.0700 1980 1.0450 2200 1.0330 2817 1.0200 6151 1.0200 6900 1.0350 7100 1.0350 8500 1.0200 8800 1.0200 9000 1.0280 9100 1.0280 10374 1.0200 18821 1.0200 19500 1.0340 19900 1.0380 24260 1.0380 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:S2%

~6%

~2%

~2%

> 2% AND :S 3%

~9%

~3%

~3%

>3%

~50%

N/A N/A

2.7 COLR BRAIDWOOD 2 Revision 16 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F§~P = 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:

UFLJHm = Base FNAH measurement uncertainty= 1.04 when PDMS is inoperable (UFAHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)

2.7.3 PDMS Alarms:

FNAH Warning Setpoint = 2% FNAH Margin FNAH Alarm Setpoint = 0% FNAH 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 ~ 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsL) is applicable with THERMAL POWER

~ 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 16 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 Figure 2.8.1.a:

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

-- -- - l -- __,._ I -

-- *-1 ------- I----------------- 1* -- ----T ----- -

I I

I I

120

"' 100 11 (-10,. 1001 111 (+10,.1001 I

~ --I ---1 w

I I

I I

~ 80 __

u_n-fa~_c_e,_pt_a_b1-e_.. ______ " ____, _______ +*... *----------+-------------

U ~accept ble

...1 O.. eration perati n

<C

~

ffi 60 Acee table

~

Operlation 0

1 I

w I

~ 40 ---~---1-1 (-20, 50) r- ------. -- -- ------ --

(+25, 50) ---- -

'o I

I

'?I?.

20 0 -<---------------,----------,.. -*---------"--<------ J_ _ J__ _ _ _ _1 ___ LJ__j

-50

-40

-30

-20

-10 0

10 20 30 40 so AXIAL FLUX DIFFERENCE (%}

COLR BRAIDWOOD 2 Revision 16 Page 12 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 Figure 2.8.1.b:

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

1 Expanded Axial Flux Difference Limits

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 16 Page 13 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 T avg 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 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 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,e shall be less than or equal to 2 sec.

2.10.12 The f1 (Al) "positive" breakpoint shall be +10% M 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 % I% Al.

COLR BRAIDWOOD 2 Revision 16 Page 14 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 24 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 Tav9 heatup coefficient KB shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower~ T reactor trip setpoint Tav9 heatup coefficient KB shall be equal to 0 / °F when T :<,; T".

2.11.6 The nominal Tav9 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 constant t1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel ~ T lead/lag time constant t2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel~ T 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 tB shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant t1 shall be equal to 10 sec.

2.11.12 The fz (~I) "positive" breakpoint shall be O for all ~I.

2.11.13 The f2 (~I) "negative" breakpoint shall be 0 for all ~I.

2.11.14 The fz (~I) "positive" slope shall be O for all ~I.

2.11.15 The f2 (~I) "negative" slope shall be 0 for all M

COLR BRAIDWOOD 2 Revision 16 Page 15 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 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 1753 b) for cycle burnups;;:: 0 MWD/MTU 1889 and < 16000 MWD/MTU c) for cycle burnups ~ 16000 MWD/MTU 1465 2.13.2 a) prior to initial criticality 1837 b) for cycle burnups;;:: 0 MWD/MTU and<

2117 16000 MWD/MTU c) for cycle burnups;;:: 16000 MWD/MTU 1592

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