BW200039, Core Operating Limits Report for Braidwood Unit 2 Cycle 22

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Core Operating Limits Report for Braidwood Unit 2 Cycle 22
ML20136A098
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Site: Braidwood Constellation icon.png
Issue date: 05/15/2020
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
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BW200039
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Text

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 22 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 13

COLR BRAIDWOOD 2 Revision 13 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 22 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 (FNt.H)

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;::: 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 2 Revision 13 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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.

2471 psia

-L L_

o>

Q) 660 c::::i Q)

L 640 0

L Q)

CL E

Q)

I- 620

<J) o>

0 L

<J)

<(

600 580 _____ ......__.__...__..__...._..._+-~-'--'--I-_,___..__.~+--..__..._~--_._ ........._.___,

0 0.2 0.4 0.6 0.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 2 Revision 13 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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% .1.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.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% .1.k/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 +2.090 x 10-5 ~k/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 ~k/k/°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 ~k/k/°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 ~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 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) 226 111 227 112 228 113 229 114

COLR BRAIDWOOD 2 Revision 13 Page 4of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 r r I/ I i I

/ I I I

/ I I / I 200 VcsANKB I I I v I

\

I I

I v

180 ~ I ~

I:

3:

ns 160 I

I i I I/ I I (100%, 161)

I

'C

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~ 140 1(0%, 162)

I IL IBANKC I i I /

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rn

,/

I

- iI Q.

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~ 120 I

/~

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0 "iii 0 100 I

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/v !BANK D 1 80

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/

60 / i

/ I

/

40 W"J(O%, 47) I

/

/ I 20 I ~v I I 1(30%.0)v 0

0 10 20 30 40 50 60 70 80 90 100 Rated Thermal Power(Percent)

COLR BRAIDWOOD 2 Revision 13 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 2.6 Heat Flux Hot Channel Factor (Fa(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) forP>0.5 p

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FQ<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 1.1 I I(o.o, 1.0) I I(6.o, 1.0) I I(12.0,0.924) I 0.9 0.8 g 0.7 0

LL "C

Q) 0.6 iii

...0E 0.5 z

t i 0.4

~

..,._LOCA Limiting Envelope -

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 2 Revision 13 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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 FCa(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWa(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.

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 = Uq,, *Ue where:

Uqu = Base Fa measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS 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 13 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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 20000

!feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 {core bottom) 1.2105 1.3465 1.2500 1.2142 0.20 1.1958 1.3171 1.2272 1.1940 0.40 1.1879 1.3047 1.2166 1.1862 0.60 1.1826 1.2922 1.2053 1.1804 0.80 1.1707 1.2294 1.1777 1.1704 1.00 1.1634 1.2142 1.1732 1.1579 1.20 1.1518 1.2014 1.1692 1.1520 1.40 1.1469 1.2026 1.1651 1.1474 1.60 1.1459 1.1934 1.1593 1.1401 1.80 1.1478 1.1813 1.1542 1.1333 2.00 1.1473 1.1699 1.1484 1.1256 2.20 1.1400 1.1571 1.1410 1.1152 2.40 1.1380 1.1429 1.1342 1.1050 2.60 1.1340 1.1318 1.1258 1.0931 2.80 1.1310 1.1309 1.1229 1.0896 3.00 1.1270 1.1290 1.1203 1.0871 3.20 1.1221 1.1262 1.1176 1.0933 3.40 1.1171 1.1233 1.1150 1.1038 3.60 1.1145 1.1184 1.1175 1.1152 3.80 1.1175 1.1145 1.1251 1.1245 4.00 1.1212 1.1097 1.1327 1.1390 4.20 1.1237 1.1074 1.1398 1.1544 4.40 1.1255 1.1073 1.1449 1.1681 4.60 1.1261 1.1054 1.1489 1.1803 4.80 1.1267 1.1042 1.1520 1.1914 5.00 1.1271 1.1025 1.1547 1.1995 5.20 1.1265 1.0994 1.1566 1.2055 5.40 1.1248 1.0968 1.1574 1.2094 5.60 1.1213 1.0939 1.1645 1.2222 5.80 1.1176 1.0910 1.1806 1.2412 6.00 1.1224 1.0940 1.1938 1.2573 6.20 1.1289 1.1024 1.2048 1.2694 6.40 1.1343 1.1099 1.2130 1.2795 6.60 1.1380 1.1165 1.2185 1.2847 6.80 1.1415 1.1236 1.2220 1.2881 7.00 1.1432 1.1306 1.2226 1.2885 7.20 1.1468 1.1376 1.2194 1.2832 7.40 1.1499 1.1447 1.2153 1.2769 7.60 1.1510 1.1513 1.2063 1.2658 7.80 1.1515 1.1590 1.1975 1.2529 8.00 1.1514 1.1652 1.1858 1.2372 8.20 1.1582 1.1704 1.1713 1.2166 8.40 1.1636 1.1756 1.1661 1.1981 8.60 1.1706 1.1787 1.1667 1.1766 8.80 1.1745 1.1823 1.1681 1.1727 9.00 1.1780 1.1932 1.1682 1.1780 9.20 1.1815 1.2030 1.1662 1.1807 9.40 1.1830 1.2131 1.1661 1.2180 9.60 1.1825 1.2233 1.2020 1.2660 9.80 1.1836 1.2410 1.2390 1.3080 10.00 1.1882 1.2578 1.2730 1.3460 10.20 1.2025 1.2744 1.3030 1.3790 10.40 1.2153 1.2888 1.3310 1.4080 10.60 1.2349 1.3019 1.3530 1.4310 10.80 1.2402 1.3104 1.3710 1.4510 11.00 1.2480 1.3184 1.3770 1.4703 11.20 1.2569 1.3201 1.3630 1.4712 11.40 1.2633 1.3316 1.3373 1.4770 11.60 1.2630 1.3343 1.3243 1.4609 11.80 1.2677 1.3390 1.3152 1.4509 12.00 lcore tool 1.2784 1.3524 1.3120 1.4477 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 2 Revision 13 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 !core bottom) 1.3687 1.5187 1.4044 1.3284 0.20 1.3500 1.4804 1.3764 1.3077 0.40 1.3401 1.4656 1.3634 1.2992 0.60 1.3323 1.4519 1.3502 1.2922 0.80 1.3086 1.3749 1.3166 1.2862 1.00 1.2968 1.3553 1.2957 1.2845 1.20 1.2911 1.3406 1.2734 1.2750 1.40 1.2783 1.3387 1.2595 1.2687 1.60 1.2725 1.3241 1.2468 1.2580 1.80 1.2726 1.3064 1.2329 1.2490 2.00 1.2648 1.2877 1.2221 1.2389 2.20 1.2481 1.2671 1.2119 1.2246 2.40 1.2333 1.2435 1.2029 1.2116 2.60 1.2157 1.2170 1.1915 1.1954 2.80 1.1999 1.1966 1.1813 1.1799 3.00 1.1856 1.1870 1.1710 1.1642 3.20 1.1736 1.1795 1.1645 1.1524 3.40 1.1665 1.1745 1.1605 1.1580 3.60 1.1582 1.1673 1.1602 1.1626 3.80 1.1537 1.1617 1.1596 1.1661 4.00 1.1482 1.1546 1.1580 1.1695 4.20 1.1418 1.1454 1.1551 1.1709 4.40 1.1353 1.1373 1.1515 1.1733 4.60 1.1297 1.1271 1.1525 1.1844 4.80 1.1302 1.1175 1.1546 1.1944 5.00 1.1297 1.1078 1.1547 1.2013 5.20 1.1283 1.0994 1.1566 1.2061 5.40 1.1259 1.0968 1.1574 1.2094 5.60 1.1216 1.0939 1.1645 1.2222 5.80 1.1176 1.0910 1.1806 1.2412 6.00 1.1224 1.0940 1.1938 1.2573 6.20 1.1289 1.1024 1.2048 1.2694 6.40 1.1343 1.1099 1.2130 1.2795 6.60 1.1380 1.1165 1.2185 1.2847 6.80 1.1415 1.1236 1.2220 1.2881 7.00 1.1432 1.1306 1.2226 1.2885 7.20 1.1468 1.1376 1.2194 1.2832 7.40 1.1499 1.1447 1.2153 1.2769 7.60 1.1510 1.1513 1.2063 1.2658 7.80 1.1515 1.1590 1.1975 1.2529 8.00 1.1514 1.1652 1.1858 1.2372 8.20 1.1582 1.1704 1.1713 1.2166 8.40 1.1636 1.1756 1.1661 1.1981 8.60 1.1706 1.1787 1.1667 1.1766 8.80 1.1745 1.1823 1.1681 1.1727 9.00 1.1780 1.1932 1.1682 1.1780 9.20 1.1815 1.2030 1.1662 1.1807 9.40 1.1830 1.2131 1.1661 1.2180 9.60 1.1825 1.2233 1.2020 1.2660 9.80 1.1836 1.2410 1.2390 1.3080 10.00 1.1882 1.2578 1.2730 1.3460 10.20 1.2025 1.2744 1.3030 1.3790 10.40 1.2153 1.2888 1.3310 1.4080 10.60 1.2349 1.3019 1.3530 1.4310 10.80 1.2402 1.3104 1.3710 1.4510 11.00 1.2480 1.3184 1.3770 1.4703 11.20 1.2569 1.3201 1.3630 1.4712 11.40 1.2633 1.3316 1.3373 1.4770 11.60 1.2630 1.3343 1.3243 1.4609 11.80 1.2677 1.3390 1.3152 1.4509 12.00 (core tool 1.2784 1.3524 1.3120 1.4477 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 2 Revision 13 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) Fco(z) 0 1.0200 150 1.0290 310 1.0375 480 1.0440 830 1.0549 1030 1.0549 1380 1.0465 2080 1.0315 2780 1.0260 3130 1.0215 3300 1.0200 9950 1.0200 10100 1.0307 11000 1.0281 11700 1.0280 12230 1.0288 13100 1.0260 13625 1.0240 14500 1.0210 14675 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.

COLR BRAIDWOOD 2 Revision 13 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN,.,H) (LCO 3.2.2) where: P =the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F§~P = 1.70 PFllH = 0.3

2.7.2 Uncertainty

The uncertainty, UF,.,H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN"'H shall be calculated by the following formula:

where:

UFtJHm = Base FN"'H measurement uncertainty = 1.04 when PDMS is inoperable (UF"'Hm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN"'H Warning Setpoint = 2% FN"'H Margin FN"'H Alarm Setpoint = 0% FN"'H 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. 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.

2.9 Departure from Nucleate Boiling Ratio CDNBR) (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 13 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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, 100) I I (+10, 100) 1 100

\

r:x:

w s0

0. 80 Una cceptab e I Ur )accept< ble 1bperatic n I \\

0 ieration

<(

2 r:x: Acce1 otable w 60

c I-cw I Oper ation

\

!:( 40 I I r:x:

....0 I (-20, 5oJ I I (+25, 50) I

?ft.

20 0 '

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 13 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 I (-15, 100) I I (+10, 100) I 100 c:::

LIJ s

0 Una cceptab e J I \ u accept< ble c.. 80 o,

I \\

..... ~eration Jperatic n

<(

~

c::: Acee >table LIJ 60

c I-cLIJ / Ope1 at ion

!;: 40 Il (-35 50) Il I I I (+25, 50) I c::: I

....0

~

20 0

-50 -40 -30 -20 -10 0 10 20 30 40 so AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 13 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature 6 T Setpoint Parameter Values 2.10.1 The Overtemperature 6 T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature 6 T reactor trip setpoint Tavg coefficient Kz shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature 6 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 6 T lead/lag time constant -r1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel 6 T lead/lag time constant -r2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel 6 T 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 {61) "positive" breakpoint shall be +10% 61.

2.10.13 The f1 (61) "negative" breakpoint shall be -18% 61.

2.10.14 The f1 {61) "positive" slope shall be +3.4 7% I % 61.

2.10.15 The f1 (61) "negative" slope shall be -2.61 % I% 61.

COLR BRAIDWOOD 2 Revision 13 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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 Tavg rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing Tavg.

2.11.3 The Overpower~T 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 Tavg heatup coefficient KB shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower~ T reactor trip setpoint Tavg heatup coefficient KB shall be equal to 0 I °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 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 t6 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 fz (~I) "positive" breakpoint shall be 0 for all ~I.

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

2.11.14 The fz (~I) "positive" slope shall be 0 for all ~I.

2.11.15 The fz (~I) "negative" slope shall be 0 for all ~I.

COLR BRAIDWOOD 2 Revision 13 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 22 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 Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1724 b) for cycle burnups;::: 0 MWD/MTU 1820 and < 16000 MWD/MTU c) for cycle burnups;::: 16,000 MWD/MTU 1395 2.13.2 a) prior to initial criticality 1768 b) for cycle burnups;::: 0 MWD/MTU and< 2022 16000 MWD/MTU c) for cycle burnups;::: 16000 MWD/MTU 1520

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