Text

Core Operating Limits Report, Cycle 19
	ML15295A029
Person / Time
Site:	Braidwood
Issue date:	10/22/2015
From:	Kanavos M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BW150100
	Download: ML15295A029 (17)
	v • d • e

Exelon Generation October 22, 2015 BW150100 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457 Exelon Generation Company, LLC Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 www.exeloncoro.com

Subject:

Core Operating Limits Report, Braidwood Unit 2 Cycle 19 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 19 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 2 Cycle 19 COLR, Revision 9 was implemented during Braidwood Unit 2 Refueling Outage 18 in support of Cycle 19 operation. Note that the revision number is based on a numbering convention that continues from the previous revision of the Unit 2 COLR, i.e.,

Braidwood Unit 2 Cycle 18, Revision 8.

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

Mark Kanavos Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 19, Revision 9 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 2 CYCLE 19 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 9

COLR BRAIDWOOD 2 Revision 9 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 19 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 (FQ(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN 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 (BDPS)

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 2 Revision 9 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 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 NRC-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.

Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 2 Revision 9 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 2.2 SHUTDOWN MARGIN (SDM)

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% 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 SDM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to 1.3% k/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 BOL/ARO/HZP-MTC upper limit shall be +2.296 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 9 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 0

20 40 60 80 100 120 140 160 180 200 220 0

10 20 30 40 50 60 70 80 90 100 Rod Bank Position (Steps Withdrawn)

R e l a t i v e P o w e r ( P e r c e n t )

Figure 2.5.1:

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

(77%, 224)

(100%, 161)

BANK B BANK C BANK D (0%, 162)

(0%, 47)

(30%, 0) 224

COLR BRAIDWOOD 2 Revision 9 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 2.6 Heat Flux Hot Channel Factor (FQ(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FQ RTP = 2.60 K(Z) is provided in Figure 2.6.1.

0.5 P

for

)

(

0.5 F

(Z)

F RTP Q

Q

Z xK 0.5 P

for

)

(

P F

(Z)

F RTP Q

Q

Z xK (0.0, 1.0)

(6.0, 1.0)

(12.0,0.924) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

1.1 0

1 2

3 4

5 6

7 8

9 10 11 12 K(Z) Normalized FQ(Z)

BOTTOM Core Height (ft) TOP Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height LOCA Limiting Envelope (0.0, 1.0)

(6.0, 1.0)

(12.0,0.924) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

1.1 0

1 2

3 4

5 6

7 8

9 10 11 12 K(Z) Normalized FQ(Z)

BOTTOM Core Height (ft) TOP Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height LOCA Limiting Envelope

COLR BRAIDWOOD 2 Revision 9 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 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 for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.

2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOL-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c shows the FC Q(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FW Q(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, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula U

U U

FQ qu e

=

where:

Uqu = Base FQ 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:

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

COLR BRAIDWOOD 2 Revision 9 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-10216)

Height 150 6000 14000 20000 (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3070 1.4779 1.4125 1.4005 0.20 1.2935 1.4452 1.3942 1.3797 0.40 1.2866 1.4387 1.4003 1.3715 0.60 1.2789 1.4258 1.3878 1.3623 0.80 1.2742 1.4024 1.3646 1.3449 1.00 1.2638 1.3684 1.3483 1.3311 1.20 1.2501 1.3528 1.3202 1.3130 1.40 1.2397 1.3367 1.3048 1.2982 1.60 1.2438 1.3242 1.2865 1.2795 1.80 1.2425 1.3042 1.2711 1.2624 2.00 1.2284 1.2825 1.2548 1.2443 2.20 1.2115 1.2573 1.2396 1.2270 2.40 1.1963 1.2339 1.2243 1.2150 2.60 1.1794 1.2075 1.2133 1.2004 2.80 1.1672 1.1882 1.2038 1.1865 3.00 1.1609 1.1836 1.1968 1.1718 3.20 1.1538 1.1770 1.1883 1.1761 3.40 1.1463 1.1725 1.1802 1.1822 3.60 1.1412 1.1664 1.1697 1.1862 3.80 1.1367 1.1619 1.1650 1.1901 4.00 1.1321 1.1553 1.1599 1.1921 4.20 1.1346 1.1477 1.1544 1.1926 4.40 1.1355 1.1402 1.1478 1.2017 4.60 1.1351 1.1306 1.1411 1.2094 4.80 1.1348 1.1220 1.1417 1.2150 5.00 1.1334 1.1124 1.1431 1.2185 5.20 1.1302 1.1018 1.1439 1.2205 5.40 1.1267 1.0927 1.1452 1.2221 5.60 1.1254 1.0908 1.1508 1.2395 5.80 1.1332 1.0972 1.1662 1.2549 6.00 1.1407 1.1030 1.1798 1.2662 6.20 1.1464 1.1106 1.1913 1.2747 6.40 1.1522 1.1173 1.1999 1.2794 6.60 1.1549 1.1229 1.2065 1.2801 6.80 1.1577 1.1276 1.2103 1.2799 7.00 1.1585 1.1327 1.2121 1.2748 7.20 1.1574 1.1384 1.2081 1.2657 7.40 1.1599 1.1447 1.2040 1.2547 7.60 1.1690 1.1490 1.1961 1.2388 7.80 1.1777 1.1532 1.1862 1.2229 8.00 1.1851 1.1565 1.1764 1.2056 8.20 1.1905 1.1633 1.1626 1.1877 8.40 1.1955 1.1713 1.1528 1.1799 8.60 1.1982 1.1780 1.1481 1.1714 8.80 1.2016 1.1883 1.1480 1.1664 9.00 1.2064 1.1979 1.1471 1.1610 9.20 1.2170 1.2118 1.1425 1.1673 9.40 1.2189 1.2195 1.1455 1.1990 9.60 1.2227 1.2279 1.1850 1.2440 9.80 1.2215 1.2326 1.2210 1.2820 10.00 1.2160 1.2352 1.2540 1.3170 10.20 1.2176 1.2445 1.2840 1.3470 10.40 1.2255 1.2551 1.3040 1.3720 10.60 1.2354 1.2641 1.3150 1.3950 10.80 1.2467 1.2737 1.3190 1.4130 11.00 1.2540 1.2816 1.3150 1.4240 11.20 1.2527 1.2903 1.2830 1.4130 11.40 1.2473 1.3007 1.2910 1.4010 11.60 1.2493 1.3055 1.2570 1.3842 11.80 1.2512 1.3107 1.2381 1.3762 12.00 (core top) 1.2567 1.3258 1.2269 1.3719 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 9 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 Table 2.6.2.b EOL-only W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-10216)

Height 18000 20000 25104 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2413 1.2338 1.2338 0.20 1.2270 1.2184 1.2184 0.40 1.2268 1.2119 1.2119 0.60 1.2189 1.2055 1.2055 0.80 1.2037 1.1927 1.1927 1.00 1.1933 1.1820 1.1820 1.20 1.1748 1.1688 1.1688 1.40 1.1635 1.1572 1.1572 1.60 1.1531 1.1437 1.1437 1.80 1.1457 1.1343 1.1343 2.00 1.1395 1.1269 1.1269 2.20 1.1313 1.1179 1.1179 2.40 1.1257 1.1089 1.1089 2.60 1.1260 1.1096 1.1096 2.80 1.1246 1.1098 1.1098 3.00 1.1239 1.1129 1.1129 3.20 1.1244 1.1191 1.1191 3.40 1.1265 1.1249 1.1249 3.60 1.1354 1.1415 1.1415 3.80 1.1462 1.1571 1.1571 4.00 1.1562 1.1707 1.1707 4.20 1.1659 1.1842 1.1842 4.40 1.1739 1.1957 1.1957 4.60 1.1803 1.2052 1.2052 4.80 1.1851 1.2127 1.2127 5.00 1.1891 1.2181 1.2181 5.20 1.1913 1.2205 1.2205 5.40 1.1931 1.2221 1.2221 5.60 1.2061 1.2395 1.2395 5.80 1.2222 1.2549 1.2549 6.00 1.2352 1.2662 1.2662 6.20 1.2453 1.2747 1.2747 6.40 1.2518 1.2794 1.2794 6.60 1.2551 1.2801 1.2801 6.80 1.2566 1.2799 1.2799 7.00 1.2542 1.2748 1.2748 7.20 1.2465 1.2657 1.2657 7.40 1.2376 1.2547 1.2547 7.60 1.2242 1.2388 1.2388 7.80 1.2098 1.2229 1.2229 8.00 1.1947 1.2056 1.2056 8.20 1.1769 1.1877 1.1877 8.40 1.1668 1.1799 1.1799 8.60 1.1590 1.1714 1.1714 8.80 1.1552 1.1664 1.1664 9.00 1.1509 1.1610 1.1610 9.20 1.1509 1.1673 1.1673 9.40 1.1697 1.1990 1.1990 9.60 1.2148 1.2440 1.2440 9.80 1.2545 1.2820 1.2820 10.00 1.2910 1.3170 1.3170 10.20 1.3226 1.3470 1.3470 10.40 1.3462 1.3720 1.3720 10.60 1.3642 1.3950 1.3950 10.80 1.3756 1.4130 1.4130 11.00 1.3791 1.4240 1.4240 11.20 1.3556 1.4130 1.4130 11.40 1.3520 1.4010 1.4010 11.60 1.3246 1.3842 1.3842 11.80 1.3099 1.3762 1.3762 12.00 (core top) 1.3004 1.3719 1.3719 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 9 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup (MWD/MTU)

Penalty Factor FC Q(z) 0 1.0200 490 1.0208 830 1.0400 1030 1.0450 1206 1.0470 1382 1.0480 1557 1.0478 1980 1.0465 3250 1.0218 3300 1.0200 13521 1.0200 13697 1.0204 13873 1.0236 14048 1.0237 14224 1.0232 14400 1.0226 14576 1.0220 14752 1.0213 14928 1.0205 15104 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 9 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN H) (LCO 3.2.2) 2.7.1 FN H FH RTP[1.0 + PFH(1.0 - P)]

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

FH RTP = 1.70 PFH = 0.3

2.7.2 Uncertainty

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

UFH = UFHm where:

UFHm = Base FN H measurement uncertainty = 1.04 when PDMS is inoperable (UFHm 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 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.

2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.

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 2 Revision 9 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)

(-35, 50)

(-15, 100)

Acceptable Operation

(+10, 100)

(+25, 50)

Unacceptable Operation Unacceptable Operation 0

20 40 60 80 100 120

-50

-40

-30

-20

-10 0

10 20 30 40 50

% of RATED THERMAL POWER AXIAL FLUX DIFFERENCE (%)

Axial Flux Difference Limits with PDMS Inoperable

COLR BRAIDWOOD 2 Revision 9 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup 18000 MWD/MTU)

Axial Flux Difference Limits with PDMS Inoperable 0

20 40 60 80 100 120

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

% of RATED THERMAL POWER Unacceptable Operation Unacceptable Operation Acceptable Operation

(-20, 50)

(-10, 100)

(+10, 100)

(+25, 50)

COLR BRAIDWOOD 2 Revision 9 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 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 5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant 6 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 2 Revision 9 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 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 K5 shall be equal to 0.02 / °F for increasing Tavg.

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

2.11.4 The Overpower T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / °F when T > T.

2.11.5 The Overpower T reactor trip setpoint Tavg heatup coefficient K6 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 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 7 shall be equal to 10 sec.

2.11.12 The f2 (I) positive breakpoint shall be 0 for all I.

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

2.11.14 The f2 (I) positive slope shall be 0 for all I.

2.11.15 The f2 (I) negative slope shall be 0 for all I.

COLR BRAIDWOOD 2 Revision 9 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 19 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 (Tavg) 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 values given in the Table below.

COLR Section Conditions Boron Concentration (ppm) 2.13.1 a) prior to initial criticality 1671 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 1809 c) for cycle burnups 16,000 MWD/MTU 1452 2.13.2 a) prior to initial criticality 1738 b) all other times in life 1995