BYRON 2022-0028, Cycle 24 Core Operating Limits Report

Cycle 24 Core Operating Limits Report

ML22118A363
Person / Time
Site:	Byron
Issue date:	04/28/2022
From:	Kowalski J Constellation Energy Generation
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2022-0028, BYRON 2022-0028
Download: ML22118A363 (17)

Text

Constellation Energy Generation. LLC (CEG)

Byron Station Constellation 4450 N German Church Road Byron. IL 61010-9794 www constellat1onenergy com April 28, 2022 LTR: BYRON 2022-0028 File: 2.01 .0300 (5A.101) 1.10.0101 (1D.101)

United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 Byron Station Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket No. STN 50-455

Subject:

Byron Station Unit 2 Cycle 24 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting the Unit 2 COLR, Revision 13, for Cycle 24.

Should you have any questions concerning this report, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully,

µi-John J. Kowalski Site Vice President Byron Generating Station

Attachment:

Byron Station Unit 2 Cycle 24, COLR, Revision 13 JJK/ZC/sg cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector- Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 24 CONSTELLATION TRACKING ID:

COLR BYRON 2 REVISION 13

COLRBYRON 2 Revision 13 Page I of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron 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 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 :2:: 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)

COLRBYRON2 Revision 13 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON 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 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.

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COLRBYRON2 Revision 13 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 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% ~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% 6k/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 +2.275 x 1o- 5 ~k/k/°F.

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

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

2.3.4 The EOUARO/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) 231 115

COLRBYRON 2 Revision 13 Page 4 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power (26.52%, 224) (76.96%, 224)

I I 220 V V 200 ,/ /

180

~

I BANKS I

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.-160 -

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.v 40 _ (0%, 47) II ~

20

. (30%.ov*

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).

COLRBYRON 2 Revision 13 Page 5 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 2.6 Heat Flux Hot Channel Factor (Fa(Z}) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FRTP F0 (Z) ~-0-xK(Z) for P ~0.5 0.5 FRTP Fq(Z) ~-0-xK(Z) forP >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 F0 (Z) as a Function of Core Height (0 .0 ' 1 0) (6.0, 1.0) (12010) 1.1 1

0.9 0.8 N 0.7 a

LL

,:, 0.6 GI

-~ns E 0.5 z

0 N 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

COLRBYRON 2 Revision 13 Page 6 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON 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 FCa(z) penalty factors that are greater than 2% per the allowable surveillance frequency. 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 U,..,J =Uq,,*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:

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

COLRBYRON 2 Revision 13 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 Table 2.6.2.a W(Z) versus Core Height for Nonna! AFD Acceptable Operation Limits In Figure 2.8.1.a (Top and Bottom 8% Excluded per Byron SR 3.2.1.2 Bases)

Height 160 4000 14000 20000 lfeetl MWD/MTU MWD/MTU MWD/MTU MWD/MTU o.oo (core bottom) 1.2747 1.3654 1.2041 1.2007 0.20 1.2676 1.3542 1.1974 1.1925 0.40 1.2677 1.3499 1.2024 1.1942 0.60 1.2717 1.3495 1.2085 1.2016 0.80 1.2801 1.3523 1.2210 1.2156 1.00 1.2791 1.3449 1.2246 1.2203 1.20 1.2694 1.3298 1.2188 1.2145 1.40 1.2555 1.3106 1.2095 1.2049 1.60 1.2412 1.2902 1.2003 1.1957 1.80 1.2256 1.2682 1.1906 1.1860 2.00 1.2086 1.2447 1.1799 1.1752 2.20 1.1904 1.2203 1.1686 1.1637 2.40 1.1724 1.1956 1.1573 1.1520 2.60 1.1580 1.1711 1.1470 1.1403 2.80 1.1433 1.1510 1.1398 1.1279 3.00 1.1321 1.1395 1.1326 1.1190 3.20 1.1284 1.1339 1.1287 1.1200 3.40 1.1281 1.1297 1.1302 1.1310 3.60 1.1275 1.1288 1.1352 1.1411 3.80 1.1266 1.1286 1.1402 1.1507 4.00 1.1251 1.1279 1.1447 1.1598 4.20 1.1232 1.1267 1.1487 1.1684 4.40 1.1208 1.1250 1.1521 1.1771 4.60 1.1195 1.1227 1.1546 1.1848 4.80 1.1187 1.1198 1.1562 1.1909 5.00 1.1185 1.1163 1.1568 1.1959 5.20 1.1187 1.1121 1.1562 1.2005 5.40 1.1181 1.1075 1.1544 1.2043 5.60 1.1197 1.1058 1.1522 1.2063 5.80 1.1243 1.1081 1.1518 1.2114 6.00 1.1331 1.1132 1.1553 1.2218 6.20 1.1476 1.1199 1.1669 1.2336 6.40 1.1609 1.1250 1.1767 1.2430 6.60 1.1729 1.1292 1.1865 1.2514 6.80 1.1835 1.1325 1.1949 1.2576 7.00 1.1925 1.1382 1.2012 1.2609 7.20 1.1996 1.1473 1.2056 1.2616 7.40 1.2048 1.1558 1.2078 1.2596 7.60 1.2080 1.1631 1.2078 1.2547 7.80 1.2080 1.1672 1.2058 1.2474 8.00 1.2092 1.1741 1.2007 1.2365 8.20 1.2160 1.1866 1.1951 1.2248 8.40 1.2209 1.1979 1.1946 1.2182 8.60 1.2285 1.2124 1.1937 1.2149 8.80 1.2365 1.2293 1.1970 1.2196 9.00 1.2445 1.2510 1.2085 1.2340 9.20 1.2522 1.2764 1.2232 1.2443 9.40 1.2609 1.2963 1.2390 1.2501 9.60 1.2911 1.3167 1.2501 1.2547 9.80 1.3272 1.3314 1.2602 1.2625 10.00 1.3586 1.3488 1.2675 1.2752 10.20 1.3886 1.3796 1.2694 1.2900 10.40 1.4156 1.4099 1.2743 1.3018 10.60 1.4398 1.4374 1.2802 1.3114 10.80 1.4580 1.4608 1.2837 1.3171 11 .00 1.4737 1.4803 1.2858 1.3216 11 .20 1.4883 1.4967 1.2849 1.3230 11 .40 1.4904 1.5047 1.2719 1.3092 11 .60 1.4871 1.5053 1.2595 1.2913 11 .80 1.4859 1.5109 1.2590 1.2790 12.00 /core top) 1.4842 1.5185 1.2583 1.2615 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

COLRBYRON 2 Revision 13 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON 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 (Too and Bottom 8% Excluded oer Bvron SR 3.2.1.2 Bases\

Height 160 4000 14000 20000 lfeetl MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3754 1.5023 1.3159 1.3129 0.20 1.3663 1.4886 1.3093 1.3029 0.40 1.3659 1.4823 1.3114 1.3035 0.60 1.3675 1.4804 1.3183 1.3102 0.80 1.3748 1.4815 1.3306 1.3240 1.00 1.3717 1.4714 1.3328 1.3274 1.20 1.3594 1.4532 1.3250 1.3196 1.40 1.3429 1.4304 1.3132 1.3076 1.60 1.3265 1.4061 1.3010 1.2958 1.80 1.3088 1.3798 1.2876 1.2831 2.00 1.2894 1.3515 1.2728 1.2690 2 .20 1.2691 1.3221 1.2568 1.2538 2.40 1.2483 1.2922 1.2403 1.2380 2.60 1.2275 1.2624 1.2237 1.2218 2.80 1.2091 1.2330 1.2054 1.2051 3.00 1.1977 1.2059 1.1943 1.1892 3.20 1.1917 1.1899 1.1911 1.1814 3.40 1.1860 1.1879 1.1880 1.1812 3.60 1.1805 1.1840 1.1845 1.1820 3.80 1.1771 1.1790 1.1800 1.1858 4 .00 1.1741 1.1738 1.1766 1.1933 4.20 1.1700 1.1686 1.1757 1.2013 4 .40 1.1654 1.1632 1.1753 1.2079 4 .60 1.1601 1.1570 1.1738 1.2130 4 .80 1.1540 1.1501 1.1712 1.2164 5.00 1.1472 1.1424 1.1677 1.2181 5.20 1.1396 1.1350 1.1642 1.2175 5.40 1.1313 1.1277 1.1606 1.2150 5.60 1.1230 1.1196 1.1551 1.2170 5.80 1.1233 1.1122 1.1570 1.2252 6.00 1.1336 1.1125 1.1687 1.2389 6.20 1.1475 1.1201 1.1820 1.2520 6.40 1.1607 1.1250 1.1929 1.2620 6 .60 1.1727 1.1290 1.2018 1.2692 6 .80 1.1832 1.1326 1.2086 1.2736 7.00 1.1920 1.1385 1.2131 1.2749 7.20 1.1990 1.1474 1.2151 1.2731 7.40 1.2041 1.1555 1.2148 1.2682 7 .60 1.2073 1.1627 1.2122 1.2605 7.80 1.2071 1.1668 1.2058 1.2483 8.00 1.2083 1.1738 1.2020 1.2381 8.20 1.2151 1.1863 1.2019 1.2326 8.40 1.2200 1.1976 1.2013 1.2252 8.60 1.2277 1.2121 1.2028 1.2255 8.80 1.2360 1.2294 1.2106 1.2285 9.00 1.2442 1.2515 1.2246 1.2303 9.20 1.2521 1.2768 1.2397 1.2312 9.40 1.2617 1.2967 1.2496 1.2308 9 .60 1.2919 1.3170 1.2595 1.2336 9.80 1.3277 1.3317 1.2660 1.2476 10.00 1.3589 1.3490 1.2697 1.2678 10.20 1.3888 1.3795 1.2743 1.2846 10.40 1.4155 1.4097 1.2781 1.2992 10.60 1.4394 1.4370 1.2816 1.3113 10.80 1.4574 1.4602 1.2880 1.3210 11 .00 1.4728 1.4795 1.2949 1.3256 11 .20 1.4872 1.4957 1.2959 1.3237 11 .40 1.4890 1.5035 1.2870 1.3117 11 .60 1.4855 1.5039 1.2730 1.2933 11 .80 1.4841 1.5093 1.2657 1.2861 12.00 /core too\ 1.4821 1.5165 1.2698 1.2757 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 BYRON 2 Revision 13 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 Table 2.6.2.c Penalty Factors in Excess of 2%

Cycle Burnup Penalty Factor

{MWD/MTU) Fca{z) 0 1.0200 150 1.0780 371 1.0890 592 1.0900 842 1.0890 1254 1.0770 1695 1.0600 1916 1.0500 2137 1.0400 2578 1.0200 5448 1.0200 6753 1.0540 7215 1.0500 7676 1.0370 8319 1.0200 8981 1.0200 9202 1.0240 9422 1.0230 9643 1.0220 9864 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c (9864 MWD/MTU and over) shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLRBYRON2 Revision 13 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN 4H) (LCO 3.2.2) 2.7.1 FN6H :s; F~i!iP[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, LiF6H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN6H shall be calculated by the following formula:

where:

UF'1Hm = 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 BYRON2 Revision 13 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON 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 120 I (-10, 10oi I I(+10, 1ooi I 100 er:

w

~

0 Q. 80 -

J \

I \\

..I Una ~ceptab e Unaccepta ble

<(

E 01 Beration Operation er:

w

c I-60 ..

I AcceI table

-\

C Oper ation w

...~er:

0 40 I (-20, SO) I I(+2s, soi I

~

20 0 I

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

COLR BYRON 2 Revision 13 Page 12 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 I(-1s, 100) I I(+10, 100) I 100 IX LU 3:

I \

0 80 I I \\

CL.

_, Unac eptable U1, accept, ble

< peratic n

E Op1 ration IX LU 60 '

J:

I-C LU I Acee *>table Oper ation

...~

0 40 I (-35, SO) I I(+25, SO) I

?fl.

20 0

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

COLR BYRON 2 Revision 13 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 2.1 O 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 set point Tavg coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient KJ shall be equal to 0.00135 / 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 ,5 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 (Al) "positive" breakpoint shall be +10% Al.

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 % / % Al.

COLR BYRON 2 Revision 13 Page 14 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower ll. T Setpoint Parameter Values 2.11 .1 The Overpower t:i,.T reactor trip setpoint K4 shall be equal to 1.072.

2.11 .2 The Overpower ll.T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 I °F for increasing Tavg.

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

2.11.4 The Overpower /l.T reactor trip setpoint Tavg heat up coefficient Ke shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower ll.T reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0 / °F when Ts T".

2.11.6 The nominal T avg at RTP (indicated) T" shall be less than or equal to 583.5 °F.

2.11 .7 The measured reactor vessel t:i,.T lead/lag time constant t1 shall be equal to 8 sec.

2.11 .8 The measured reactor vessel t:i,.T lead/lag time constant t2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel t:i,. 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 te shall be less than or equal to 2 sec.

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

2.11 .12 The fa (ll.l) "positive" breakpoint shall be O for all /l.l .

2.11 .13 The fa (/l.l) "negative" breakpoint shall be Ofor all /l.l.

2.11 .14 The fa (/l.l) "positive" slope shall be Ofor all ll.l.

2.11 .15 The f2 (Al) "negative" slope shall be Ofor all ll.l.

COLR BYRON 2 Revision 13 Page 15 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON 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 (Tavg) 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 8 .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 Boron Concentration Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1748 b) for cycle burnups ~ 0 MWD/MTU 1880 and < 16000 MWD/MTU c) for cycle burnups <?: 16,000 MWD/MTU 1436 2.13.2 a) prior to initial criticality 1826 b) for cycle burnups ~ 0 MWD/MTU and< 2090 16000 MWD/MTU c) for cycle burnups ~ 16000 MWD/MTU 1561