ML19304A137

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Core Operating Limits Report, Cycle 22
ML19304A137
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 10/31/2019
From: Marchionda-Palmer M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW190100
Download: ML19304A137 (17)
v • d • e


Text

ti Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407,9619 www,exeloncoro,com October 31, 2019 BW190100 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRC Docket No. STN 50-456

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 22 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 22 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 1 Cycle 22 COLR, Revision 16 was implemented during Braidwood Unit 1 Refueling Outage 21 in support of Cycle 22 operation. Note that the revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLR, i.e., Braidwood Unit 1 Cycle 21, Revision 15.

If you have any questions regarding this matter, please contact Mr. Kevin Lueshen, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely, Marri Marchionda-Palmer Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 22, Revision 16 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Braidwood Station NRC Project Manager, NRR - Braidwood and Byron Stations

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1 CYCLE 22 EXELON TRACKING ID:

COLR BRAIDWOOD 1 REVISION 16

COLR BRAIDWOOD 1 Revision 16 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 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 (SDM)

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 (FNL\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 (SDM) - MODE 1 and MODE 2 with keff;;:: 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) - 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 16 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 660

~

w_

CJ"l QJ c::i 2250psia Cl)

'"-- 640

2000 psia

~

0 1860 psia E

f--

Cl)

Q) 620 ----

01 0

Q)

<::(

600 0 0.2 0.4 0.6 Q.8 Fraction of f~orninal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 1 Revision 16 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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% Llk/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% Llk/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 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 +1.649 x 10-5 Llk/k/°F.

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

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

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 Llk/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 1 Revision 16 Page 4of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 Figure 2.5.1:

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

I /

r I

I / /

200

~ANKB I I

I v I v

~ ~

180

./1 I

'2 I i I (100%, 161)

== 160 E

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I I IL I I

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I/

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~ 120 I

I i

IBANKC I II 1/1 v

I I

/~

c I 0 I

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v I / I

~

D.

.:.:: IBANKD I m

c ns

/ I I

I I

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80

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v I I

i I

/

v I II v

I 60

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  • ~l(o%, 47) I II 40 / I I

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iI I I I I I 20 I 1(30%.0)VI  !

I 0

I I I 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BRAIDWOOD 1 Revision 16 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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) forP:::;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 F6ffP = 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 1.1 (0.0 1.0) (6.0 1.0) 1 (12.C 0.924) 0.9 0.8 r::r 0.7 0

u.

"C Q) 0.6 iii

... 0.5 E

0 z

ti

~

0.4 0.3

....... LOCA Limiting Envelope -

0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP

COLR BRAIDWOOD 1 Revision 16 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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, UFa, to be applied to-the Heat Flux Hot*Channel Factor Fa(Z) shall be calculated by the following formula UFQ = uqu *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 1 Revision 16 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 perWCAP-10216)

Height 150 5000 14000 20000 Ifeet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 rcore bottom\ 1.1807 1.3027 1.2923 1.2216 0.20 1.1694 1.2788 1.2708 1.2028 0.40 1.1647 1.2698 1.2625 1.1943 0.60 1.1580 1.2592 1.2525 1.1800 0.80 1.1515 1.2041 1.2184 1.1750 1.00 1.1482 1.1901 1.2061 1.1739 1.20 1.1461 1.2046 1.1815 1.1697 1.40 1.1454 1.1979 1.1774 1.1658 1.60 1.1353 1.1821 1.1737 1.1586 1.80 1.1310 1.1682 1.1718 1.1521 2.00 1.1267 1.1542 1.1680 1.1455 2.20 1.1209 1.1356 1.1633 1.1368 2.40 1.1158 1.1216 1.1585 1.1287 2.60 1.1122 1.1107 1.1508 1.1190 2.80 1.1096 1.1057 1.1441 1.1115 3.00 1.1060 1.1031 1.1373 1.1109 3.20 1.1008 1.1046 1.1296 1.1184 3.40 1.1007 1.1055 1.1250 1.1319 3.60 1.1046 1.1051 1.1200 1.1444 3.80 1.1095 1.1057 1.1205 1.1556 4.00 1.1133 1.1054 1.1256 1.1649 4.20 1.1172 1.1047 1.1296 1.1755 4.40 1.1200 1.1039 1.1325 1.1853 4.60 1.1229 1.1014 1.1342 1.1939 4.80 1.1237 1.0995 1.1348 I 1.2012 5.00 1.1245 1.0967 1.1343 1.2060 5.20 1.1244 1.0938 1.1358 1.2107 5.40 1.1222 1.0903 1.1385 1.2125 5.60 1.1201 1.0860 1.1464 1.2323 5.80 1.1159 1.0858 1.1622 1.2481 6.00 1.1229 1.0956 1.1760 1.2619 6.20 1.1297 1.1055 1.1878 1.2717 6.40 1.1356 1.1133 1.1967 1.2785 6.60 1.1395 1.1202 1.2036 1.2814 6.80 1.1424 1.1271 1.2075 1.2813 7.00 1.1443 1.1339 1.2094 1.2782 7.20 1.1445 1.1415 1.2084 1.2702 7.40 1.1484 1.1494 1.2054 1.2602 7.60 1.1514 1.1558 1.1964 1.2452 7.80 1.1543 1.1622 1.1885 1.2303 8.00 1.1607 1.1676 1.1785 1.2124 8.20 1.1661 1.1770 1.1647 1.1905 8.40 1.1705 1.1860 1.1587 1.1759 8.60 1.1739 1.1943 1.1537 1.1705 8.80 1.1768 1.1988 1.1563 1.1666 9.00 1.1826 1.2118 1.1579 1.1617 9.20 1.1817 1.2263 1.1633 1.1630 9.40 1.1871 1.2416 1.1708 1.2110 9.60 1.1943 1.2566 1.2010 1.2570 9.80 1.1997 1.2696 1.2380 1.2980 10.00 1.2058 1.2795 1.2730 1.3330 10.20 1.2113 1.2852 1.3030 1.3650 10.40 1.2177 1.2932 1.3310 1.3910 10.60 1.2272 1.2999 1.3440 1.4220 10.80 1.2391 1.3083 1.3540 1.4440 11.00 1.2497 1.3200 1.3590 1.4620 11.20 1.2566 1.3267 1.3440 1.4482 11.40 1.2663 1.3432 1.3314 1.4540 11.60 1.2669 1.3461 1.3134 1.4331 11.80 1.2679 1.3491 1.2993 1.4180 12.00 lcore too\ 1.2758 1.3623 1.2911 1.4077 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BRAIDWOOD 1 Revision 16 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 perWCAP-10216)

Height 150 5000 14000 20000 Ifeet I MWD/MTU MWD/MTU MWDIMTU MWD/MTU 0.00 {core bottom\ 1.3380 1.4449 1.4310 1.3183 0.20 1.3229 1.4164 1.4050 1.3034 0.40 1.3163 1.4060 1.3950 1.2981 0.60 1.3078 1.3956 1.3830 1.2941 0.80 1.2868 1.3321 1.3430 1.2924 1.00 1.2765 1.3159 1.3280 1.2885 1.20 1.2673 1.3311 1.2990 1.2817 1.40 1.2843 1.3218 1.2850 1.2759 1.60 1.2693 1.3019 1.2680 1.2661 1.80 1.2560 1.2848 1.2550 1.2572 2.00 1.2418 1.2658 1.2420 1.2474 2.20 1.2257 1.2410 1.2300 1.2346 2.40 1.2105 1.2209 1.2170 1.2228 2.60 1.1935 1.1981 1.2060 1.2081 2.80 1.1804 1.1842 1.1960 1.1943 3.00 1.1670 1.1792 1.1872 1.1825 3.20 1.1579 1.1732 1.1786 1.1752 3.40 1.1512 1.1687 1.1714 1.1807 3.60 1.1430 1.1626 1.1644 1.1848 3.80 1.1376 1.1581 1.1606 1.1880 4.00 1.1325 1.1516 1.1569 1.1903 4.20 1.1266 1.1435 1.1508 1.1903 4.40 1.1282 1.1365 1.1450 1.1893 4.60 1.1297 1.1270 1.1374 1.1939 4.80 1.1295 1.1179 1.1348 1.2012 5.00 1.1289 1.1089 1.1343 1.2060 5.20 1.1273 1.0979 1.1358 1.2107 5.40 1.1241 1.0903 1.1385 1.2125 5.60 1.1205 1.0860 1.1464 1.2323 5.80 1.1159 1.0858 1.1622 1.2481 6.00 1.1229 1.0956 1.1760 1.2619 6.20 1.1297 1.1055 1.1878 1.2717 6.40 1.1356 1.1133 1.1967 1.2785 6.60 1.1395 1.1202 1.2036 1.2814 6.80 1.1424 1.1271 1.2075 1.2813 7.00 1.1443 1.1339 1.2094 1.2782 7.20 1.1445 1.1415 1.2084 1.2702 7.40 1.1484 1.1494 1.2054 1.2602 7.60 1.1514 1.1558 1.1964 1.2452 7.80 1.1543 1.1622 1.1885 1.2303 8.00 1.1607 1.1676 1.1785 1.2124 8.20 1.1661 1.1770 1.1647 1.1905 8.40 1.1705 1.1860 1.1587 1.1759 8.60 1.1739 1.1943 1.1537 1.1705 8.80 1.1768 1.1988 1.1563 1.1666 9.00 1.1826 1.2118 1.1579 1.1617 9.20 1.1817 1.2263 1.1633 1.1630 9.40 1.1871 1.2416 1.1708 1.2110 9.60 1.1943 1.2566 1.2010 1.2570 9.80 1.1997 1.2696 1.2380 1.2980 10.00 1.2058 1.2795 1.2730 1.3330 10.20 1.2113 1.2852 1.3030 1.3650 10.40 1.2177 1.2932 1.3310 1.3910 10.60 1.2272 1.2999 1.3440 1.4220 10.80 1.2391 1.3083 1.3540 1.4440 11.00 1.2497 1.3200 1.3590 1.4620 11.20 1.2566 1.3267 1.3440 1.4482 11.40 1.2663 1.3432 1.3314 1.4540 11.60 1.2669 1.3461 1.3134 1.4331 11.80 1.2679 1.3491 1.2993 1.4180 12.00 (core tool 1.2758 1.3623 1.2911 1.4077 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 16 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) Fca(z) 0 1.0200 150 1.0350 325 1.0365 851 1.0370 1027 1.0380 1202 1.0415 1377 1.0425 1553 1.0425 1728 1.0417 2955 1.0200 9969 1,0200 10320 1.0267 11021 1.0265 11728 1.0278 12248 1.0280 12424 1.0279 14878 1.0200 21717 1.0200 21892 1.0218 22243 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 1 Revision 16 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN6H) (LCO 3.2.2) 2.7.1 FN6H::; F§~P[1.0 + PF6H(1.0- P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F§~P = 1.70 PF6H = 0.3

2. 7 .2 Uncertainty:

The uncertainty, UF6H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN6H shall be calculated by the following formula:

where:

UFLJHm = Base FN6H measurement uncertainty= 1.04 when PDMS is inoperable (UF6Hm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN6H Warning Setpoint = 2% FN6H Margin FN6H Alarm Setpoint = 0% FN6H 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 (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 1 Revision 16 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 1 (-10, 10oi 1 I (+10, 10oi 1 100

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ex::

J w

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0 Una cceptab e U1 accept< ble

a. 80 1Jperat1c n

..... 0 >>eration

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ex::

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c I-60 I

I Acee >table Ope1 ation

\\

\

c w

~ 40 I I ex:: I (-20, SO) I I (+2S, SO) I 0

'*- 20 0

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

COLR BRAIDWOOD 1 Revision 16 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 1 (-1s, 100) 1 I(+10, 100) I 100 w

cc:

3:

0 Una ~ceptab e J I \ U1 )accept< ble Q.

80 o, >eration LJperatic n

<(

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cc:

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c 60 I Acee >table

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I-cw I

/ Ope1 ation

\

~ II II

- 40 (-3S I SO) I I cc: I (+2S, SO) I 0

20 0

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

COLR BRAIDWOOD 1 Revision 16 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 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 Tav9 coefficient Kz shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature ~T 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 ~T lead/lag time constant t1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel ~T lead/lag time constant t2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel~ 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 te 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% ~I.

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

COLR BRAIDWOOD 1 Revision 16 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 22 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower Ll T Setpoint Parameter Values 2.11.1 The Overpower tlT reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower LlT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.021°F for increasing Tavg.

2.11.3 The Overpower LlT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I °F for decreasing Tavg.

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

2.11.5 The Overpower tlT 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 588.0 °F.

2.11. 7 The measured reactor vessel tlT lead/lag time constant 1'1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel tlT lead/lag time constant 1'2 shall be equal to 3 sec.

2.11. 9 The measured reactor vessel LlT lag time constant 1'3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant cB shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant 1'7 shall be equal to 10 sec.

2.11.12 The fa (Lll) "positive" breakpoint shall be 0 for all Lll.

2.11.13 The fa (Lll) "negative" breakpoint shall be 0 for all Lll.

2.11.14 The fa (Lll) "positive" slope shall be 0 for all Lll.

2.11.15 The fa (Lll) "negative" slope shall be 0 for all Lll.

COLR BRAIDWOOD 1 Revision 16 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 (T av 9) 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 1737 b) for cycle burnups;?: 0 MWD/MTU 1843 and < 16000 MWD/MTU c) for cycle burnups;?: 16000 MWD/MTU 1472 2.13.2 a) prior to initial criticality 1793 b) for cycle burnups;?: 0 MWD/MTU and < 16000 MWD/MTU 2054 c) for cycle burnups;?: 16000 1611 MWD/MTU

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