ML15110A377

Cycle 19 Core Operating Limits Report

ML15110A377
Person / Time
Site:	Braidwood
Issue date:	04/20/2015
From:	Kanavos M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW150043
Download: ML15110A377 (17)

Text

ti Exelon Generation Company, Braidwood Station 35100 South Route Suite 84 Braceville, IL 60407-9619 www.exeloncom.com April 20, 2015 BW150043 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRG Docket No. STN 50-456

Subject:

Core Operating Limits Report, Braidwood Unit 1 Cycle 19 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 19 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLA)." Braidwood Unit 1 Cycle 19 COLR, Revision 12 was implemented during Braidwood Unit 1 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 1 COLR, i.e.,

Braidwood Unit 1 Cycle 18, Revision 11.

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

Mark Kanavos Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Biaidwood Unit 1 Cycle 19, Revision 12 cc: NRG Regional Administrator, Region Ill NRG Senior Resident Inspector- Braidwood Station NRG Project Manager, NRR - Braidwood and Byron Stations

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1CYCLE19 EXELON TRACKING ID:

COLR BRAIDWOOD 1 REVISION 12

COLR BRAIDWOOD 1 Revision 12 Page 1of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 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 (SOM)

LCO 3.1.3 Moderator Temperature Coefficient (MTG)

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 (F 0 (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 (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 1 Revision 12 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 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.

680 2471 psia 660 Li_

0--.

Cl>

c:.i Q.)

..__ 640

J

-+---'

0 Q) 0....

E Q) 1-- 620 Q)

Qt 0

cu

<'.(

600 580 0 0.2 OA 0.6 0.8 Frnction of ~~ominal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 1 Revision 12 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 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% 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.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% Ak/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 +1.788 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 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 12 Page 4of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 Figure 2.5.1 :

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) r ,.

220

/

v /

/

200 VcsANKB I v

-ec 180

160 v

~

v ~

(100%, 161)

'ti

.c

== 140 3:

j(O%, 162)

I L IBANKC I

/

Ill C2.

Q)

~ 120 c

/ ~

/

e 0

Ill 0 100

/' /

D.

.II:: ~ / IBANKD I c

ca ID 80 / /

'ti 0

0:: / /

60 / /

/

40 "l<O%, 4 7) I ,/

/

20

~v

,(30%.0)v 0 T 0 10 20 30 40 50 60 70 80 90 100 Relative Power {Percent)

COLR BRAIDWOOD 1 Revision 12 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 2.6 Heat Flux Hot Channel Factor <Fg@ (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) 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 1.1 (0.0 1.0) (6.0 1.0) 1 (12.C 0.924) 0.9 0.8 N' 0.7 aLL

~ 0.6 iii e o.5 0

z

~ 0.4 0.3

...,_LOCA Limiting Envelope 0.2 0.1 0

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

COLR BRAIDWOOD 1 Revision 12 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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, 5000, 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 Fe0 (z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fw0 (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 F0 (Z) shall be calculated by the following formula UFQ = uqu *U.

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:

F0 (Z) Warning Setpoint = 2% Fo(Z) Margin F0 (Z) Alarm Setpoint = 0% F0 (Z) Margin

COLR BRAIDWOOD 1 Revision 12 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 Tabla 2.6.2.a Full Cycle W(Z) versus Cora Haight for AFC Acceptable Operation Limits In Figura 2.8.1.a (Top and Bottom 8% Excluded perWCAP-10216)

Haight 150 5000 14000 20000 lfaatl MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 !core bottom\ 1.3144 1.4149 1.4538 1.4030 0.20 1.3078 1.3765 1.4277 1.3786 0.40 1.2987 1.3610 1.4100 1.3656 0.60 1.2892 1.3474 1.3933 1.3544 0.80 1.2618 1.3060 1.3693 1.3382 1.00 1.2522 1.2907 1.3536 1.3323 1.20 1.2576 1.2929 1.3263 1.3226 1.40 1.2591 1.2871 1.3099 1.3137 1.60 1.2442 1.2690 1.2907 1.3000 1.80 1.2317 1.2489 1.2747 1.2892 2.00 1.2173 1.2298 1.2638 1.2754 2.20 1.2015 1.2102 1.2512 1.2587 2.40 1.1871 1.1919 1.2399 1.2430 2.60 1.1703 1.1703 1.2249 1.2233 2.80 1.1600 1.1641 1.2159 1.2046 3.00 1.1541 1.1603 1.2081 1.1859 3.20 1.1471 1.1543 1.1979 1.1838 3.40 1.1402 1.1505 1.1887 1.1883 3.60 1.1312 1.1454 1.1776 1.1915 3.80 1.1307 1.1407 1.1699 1.1932 4.00 1.1326 1.1356 1.1653 1.1944 4.20 1.1333 1.1283 1.1591 1.1933 4.40 1.1341 1.1213 1.1530 1.1912 4.60 1.1336 1.1130 1.1449 1.1979 4.80 1.1324 1.1050 1.1373 1.2035 5.00 1.1301 1.1011 1.1346 1.2080 5.20 1.1267 1.0970 1.1367 1.2113 5.40 1.1224 1.0929 1.1381 1.2150 5.60 1.1233 1.0888 1.1467 1.2344 5.80 1.1300 1.0915 1.1631 1.2497 6.00 1.1357 1.0982 1.1768 1.2631 6.20 1.1414 1.1059 1.1884 1.2727 6.40 1.1452 1.1126 1.1971 1.2794 6.60 1.1469 1.1184 1.2028 1.2811 6.80 1.1487 1.1231 1.2066 1.2809 7.00 1.1486 1.1289 1.2085 1.2777 7.20 1.1511 1.1453 1.2064 1.2687 7.40 1.1617 1.1590 1.2023 1.2596 7.60 1.1705 1.1719 1.1954 1.2438 7.80 1.1783 1.1834 1.1865 1.2289 8.00 1.1848 1.1981 1.1747 1.2111 8.20 1.1949 1.2112 1.1600 1.1894 8.40 1.2081 1.2202 1.1502 1.1713 8.60 1.2195 1.2279 1.1403 1.1666 8.80 1.2312 1.2393 1.1414 1.1620 9.00 1.2425 1.2490 1.1444 1.1565 9.20 1.2521 1.2618 1.1441 1.1746 9.40 1.2617 1.2726 1.1490 1.2082 9.60 1.2695 1.2832 1.1890 1.2530 9.80 1.2712 1.2922 1.2230 1.2930 10.00 1.2629 1.3009 1.2540 1.3280 10.20 1.2567 1.3087 1.2820 1.3600 10.40 1.2552 1.3145 1.3050 1.3850 10.60 1.2525 1.3152 1.3230 1.4120 10.80 1.2598 1.3139 1.3380 1.4270 11.00 1.2671 1.3180 1.3480 1.4390 11.20 1.2652 1.3280 1.3490 1.4280 11.40 1.2665 1.3370 1.3290 1.4150 11.60 1.2713 1.3420 1.3060 1.3940 11.80 1.2767 1.3490 1.2841 1.3898 12.00 !core tool 1.2865 1.3670 1.2748 1.3915 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 12 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 perWCAP-10216)

Height 18000 20000 24389 (feet! MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3024 1.2621 1.2621 0.20 1.2794 1.2368 1.2368 0.40 1.2659 1.2250 1.2250 0.60 1.2576 1.2213 1.2213 0.80 1.2482 1.2181 1.2181 1.00 1.2401 1.2140 1.2140 1.20 1.2243 1.2074 1.2074 1.40 1.2136 1.2006 1.2006 1.60 1.2019 1.1901 1.1901 1.80 1.1949 1.1816 1.1816 2.00 1.1860 1.1707 1.1707 2.20 1.1742 1.1575 1.1575 2.40 1.1633 1.1449 1.1449 2.60 1.1492 1.1293 1.1293 2.80 1.1408 1.1180 1.1180 3.00 1.1422 1.1247 1.1247 3.20 1.1433 1.1323 1.1323 3.40 1.1436 1.1390 1.1390 3.60 1.1432 1.1455 1.1455 3.80 1.1461 1.1561 1.1561 4.00 1.1550 1.1682 1.1682 4.20 1.1635 1.1798 1.1798 4.40 1.1702 1.1896 1.1896 4.60 1.1752 1.1979 1.1979 4.80 1.1784 1.2035 1.2035 5.00 1.1803 1.2080 1.2080 5.20 1.1833 1.2113 1.2113 5.40 1.1863 1.2150 1.2150 5.60 1.2015 1.2344 1.2344 5.80 1.2178 1.2497 1.2497 6.00 1.2318 1.2631 1.2631 6.20 1.2425 1.2727 1.2727 6.40 1.2502 1.2794 1.2794 6.60 1.2536 1.2811 1.2811 6.80 1.2550 1.2809 1.2809 7.00 1.2537 1.2777 1.2777 7.20 1.2462 1.2687 1.2687 7.40 1.2380 1.2596 1.2596 7.60 1.2247 1.2438 1.2438 7.80 1.2109 1.2289 1.2289 8.00 1.1938 1.2111 1.2111 8.20 1.1731 1.1894 1.1894 8.40 1.1574 1.1713 1.1713 8.60 1.1493 1.1666 1.1666 8.80 1.1464 1.1620 1.1620 9.00 1.1441 1.1565 1.1565 9.20 1.1534 1.1746 1.1746 9.40 1.1743 1.2082 1.2082 9.60 1.2190 1.2530 1.2530 9.80 1.2581 1.2930 1.2930 10.00 1.2927 1.3280 1.3280 10.20 1.3243 1.3600 1.3600 10.40 1.3495 1.3850 1.3850 10.60 1.3738 1.4120 1.4120 10.80 1.3900 1.4270 1.4270 11.00 1.4016 1.4390 1.4390 11.20 1.3950 1.4280 1.4280 11.40 1.3769 1.4150 1.4150 11.60 1.3532 1.3940 1.3940 11.80 1.3394 1.3898 1.3898 12.00 (core top) 1.3344 1.3915 1.3915 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 12 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(Z) 0 1.0200 326 1.0200 677 1.0390 853 1.0455 1028 1.0480 1204 1.0484 1380 1.0461 1555 1.0428 1907 1.0345 2434 1.0205 2609 1.0200 13460 1.0200 14029 1.0235 14731 1.0200 17542 1.0200 18010 1.0214 18245 1.0215 18596 1.0212 18772 1.0200 24389 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 12 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH} (LCO 3.2.2) 2.7.1 FNc.H ~ F~~p[1.0 + PFc.H(1.0- P)]

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

F~~P = 1.70 PFc.H = 0.3

2.7.2 Uncertainty

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

where:

UF.111m = =

Base FNc.H measurement uncertainty 1.04 when PDMS is inoperable (UFc.Hm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FNc.H Warning Setpoint = 2% FNt.H Margin

=

FNc.H Alarm Setpoint 0% FNc.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 1 Revision 12 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power

{Full Cycle)

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) (+10, 00) 100 0:::

w 3:

0 80 Una cc eptabh Ope ation ) \ Una ccepta :>le 01 >eratio11 I \\

ll.

...J A ccepta :>le

i Operatic n 0::

w 60

c I-Q w

I \

....~

(-3 5, 50' (+ ~5, 51 l) 40 0

~

Cl 20 0

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

COLR BRAIDWOOD 1 Revision 12 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 120

(-10, 100) (+10, 100) 100 a:;

w

~

D. 80 Unac~eptablEI u..,

- J \ Unac ceptable UtJ <11dLIUll I

p1dLIUll a!

~

w Acee iptable Ope ration

\\

c 60

.... I \

c w

(-20, 50) +25,5 ))

....~0 40

'?/!.

20 0

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

COLR BRAIDWOOD 1 Revision 12 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 2.10 Reactor Trip System CRTS) Instrumentation (LCO 3.3.1) - Overtemperature LH Setpoint Parameter Values 2.10.1 The Overtemperature ilT reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature ilT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature ilT reactor trip setpoint pressure coefficient i<J 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 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 ilT lead/lag time constant 't 1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel ilT 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 f 1 (ill) "positive" breakpoint shall be +10% ill.

2.10.13 The f 1 (ill) "negative" breakpoint shall be -18% ill.

2.10.14 The f 1 (ill) "positive" slope shall be +3.47% I% ill.

2.10.15 The f 1 (ill) "negative" slope shall be -2.61 % I% ill.

COLR BRAIDWOOD 1 Revision 12 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 19 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 Ki 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 T avg rate/lag coefficient K5 shall be equal to 0 I °F for decreasing Tavg*

2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ka shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient Ka 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 AT lead/lag time constant 't 1 shall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant 't3 shall be less than or equal to 2 sec.

2.11.1 O The measured reactor vessel average temperature lag time constant 'ts 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 f2 (Al) "positive" breakpoint shall be 0 for all Al.

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

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

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

COLR BRAIDWOOD 1 Revision 12 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 s; 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 loom) 2.13.1 a) prior to initial criticality 1675 b) for cycle burnups ~ 0 MWD/MTU 1775 and < 16000 MWD/MTU c) for cycle burnups ~ 16000 1430 MWD/MTU 2.13.2 a) prior to initial criticality 1748 b) all other times in life 1979