BYRON 2022-0039, Core Operating Limits Report (COLR) for Byron Unit 2 Cycle 24

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Core Operating Limits Report (COLR) for Byron Unit 2 Cycle 24
ML22181A050
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Site: Byron Constellation icon.png
Issue date: 06/30/2022
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Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
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ML22181A047 List:
References
BYRON 2022-0039
Download: ML22181A050 (16)
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Text

CORE OPERATING LIMITS REPORT (COLR)

FOR

BYRON UNIT 2 CYCLE 24

CONSTELLATION TRACKING ID:

COLR BYRON 2 REVISION 14 COLRBYRON 2 Revision 14 Page l 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 (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 :::o: 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 BYRON2 Revision 14 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 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.

seo--.-------.-------,--------,-----.......... -----,--------.

- 24 71 psia

- ---------~----------------- -

- 2250 psia

2000 p,ia -------....____________ --"'-

- -*----~ - \\_ ---------- -------------- \\\\

,_ 1860 p,ia ---- ---...... __________ ---------.________________ \\,

L - - - ---- \\

- - ----- '\\ ------------ ----------- I"- \\

<T

().2 0.4 0.6 0.8 F r1Jction of f\\J inCJI r)oVVf:r

Figure 2.1.1: Reactor Core Limits COLR BYRON2 Revision 14 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% Lik/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% Lik/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 +2.275 x 10-5 Lik/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 1Q-4 Lik/k/°F.

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

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 Lik/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 COLR BYRON 2 Revision 14 Page4ofl5

CORE OPERATING 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)

-160

~

"O E 140 --1-------***-**0 *****"** ---~---***********..;---

~

tll 0..

.S 120 +****---*****+*****--****--c********--*.. **,

~

C

  • ..:; 0

'iji 100 *l******--******)............... +**#

a.. 0

.:.:: C

~ 80 "O

0::: 0

60

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 s; P s; 100)

Where P is defined as the core power (in percent).

COLR BYRON2 Revision 14 Page 5 of 15

CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24

2.6 Heat Flux Hot Channel Factor (Fo(Z)) (LCO 3.2.1)

2.6.1 Total Peaking Factor:

pRTP 0

F0 (Z) :s:-0.5 -xK(Z) forP:S:0.5

F0 (Z) :S:--xK(Z) forP >0.5 F;rr 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 Fa(Z) as a Function of Core Height

(0.0, 1.0) (6.0, 1.0) (12.0, 1.0) 1.1

  • l - ! ---,--- -- ~--- ------------------ 7

I, I I I I

! I

' I i I I I I I i.l

I 0.9. -- ----- -, _______ ---- - - __I I ! I I ' --

I

i I 0.8 N 0.7 ~-- '---------- --- ____ _, I i ------

I 0

LL "C 0.6 I I -

(1)

-~ I I Ill I I I E 0.5 0 I z

N 0.4 !...,_LOCA Limiting ~~

S2"" l Envelope 0.3 ' i ! i i I I

0.2 I :

0.1 I i

0 I I i l I - -

0 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP COLR BYRON 2 Revision 14 Page 6 of 15

CORE OPERATING 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 Foc(Z) penalty factors that are greater than 2% per the allowable surveillance frequency. These values shall be used to increase the Fow(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.

Table 2.6.2.d contains the required operating space reduction values for THERMAL POWER and AXIAL FLUX DIFFERENCE (AFD) when Fow(Z) is not within its limits. These values are used in conjunction with Technical Specification LCO 3.2.1 Required Actions B.1 and B.2.

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

=U *U CJII C

where:

Uqu = Base Fo measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS and cannot be less than 1.05 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 BYRON 2 Revision 14 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 Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per Byron SR 3.2.1.2 Bases)

Height 150 4000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (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 burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation COLR BYRON2 Revision 14 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 (Top and Bottom 8% Excluded per Bvron SR 3.2.1.2 Bases)

Height 150 4000 14000 20000 (feet) 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 top) 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 COLRBYRON 2 Revision 14 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) Foc(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 shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

Table 2.6.2.d Required Operating Space Reduction When Fow(Z) Exceeds Its Limits

Required Fow(Z) THERMAL POWER Negative AFD Band Positive AFD Band Margin Improvement Reduction(% RTP) Reduction (% AFD) Reduction (% AFD)

1% 2
3% 2: 1% 2: 1%

> 1% AND :s 2% 2: 6% 2: 2% 2: 2%

> 2% AND :s 3% 2: 9% 2: 3% 2: 3%

>3% e: 50% NIA NIA COLR BYRON 2 Revision 14 Page 10 of 15

CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN11H) (LCO 3.2.2)

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

F~~P = 1.70 PF11H = 0.3

2.7.2 Uncertainty

The uncertainty, UFL\\H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN11H shall be calculated by the following formula:

where:

UF'1Hm = Base FN:iH measurement uncertainty = 1.04 when PDMS is inoperable (UF:iHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)

2.7.3 PDMS Alarms:

FN:iH Warning Setpoint = 2% FN11H Margin FN/\\H Alarm Setpoint = 0% FN11H 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. These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken. 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. These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken.

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 BYRON 2 Revision 14 Page 11 of 15

CORE OPERATING 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

100 0:::

w s

0 80 0.

-I

<(

?;

0:::

w 60

c I-Acceptable 0 Operation w

~ 40 0:::

-0 I (-20, 50) 1 {+25, 50) 1

~

20

0

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

COLRBYRON 2 Revision 14 Page 12 of 15

CORE OPERATING 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

100

w c:::

s I 0 80 --~ "' '-~~--j a..

...J ble

<(

~

c:::

w 60

I:

I-Cl w

!:i: 40 c:::

-0

~

20

0

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

COLRBYRON 2 Revision 14 Page 13 of 15

CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24

2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature Li T Setpoint Parameter Values

2.10.1 The Overtemperature Li T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature Li T reactor trip setpoint Tav 9 coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature Li T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 / psi.

2.10.4 The nominal Tav 9 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 Li T lead/lag time constant,1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel Li T lead/lag time constant 12 shall be equal to 3 sec.

2.10.8 The measured reactor vessel Li T lag time constant n 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 15 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 (Lil) "positive" breakpoint shall be +10% Lil.

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

2.10.14 The f1 (i'il) "positive" slope shall be +3.47% I% Lii.

2.10.15 The f1 (Lil) "negative" slope shall be -2.61 % /%Lil.

COLRBYRON2 Revision 14 Page 14 of 15

CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 24

2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower Ii T Setpoint Parameter Values

2.11.1 The Overpower Ii T reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower Ii 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 Ii T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg

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

2.11.5 The Overpower Ii T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / °F when T :c: 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 Ii T lead/lag time constant,1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel Ii T lead/lag time constant,2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel Ii 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 fa (Lil) "positive" breakpoint shall be 0 for all Lil.

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

2.11.14 The fa (iii) "positive" slope shail be 0 for all Lil.

2.11.15 The f2 (Lil) "negative" slope shall be O for all Lil.

COLRBYRON 2 Revision 14 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 (Tav 9 ) 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 s; 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 Section Conditions (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

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