BYRON 2019-0015, Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report

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Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report
ML19066A201
Person / Time
Site: Byron  Constellation icon.png
Issue date: 03/07/2019
From: Kanavos M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2019-0015
Download: ML19066A201 (33)
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Text

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Byron Generating Station Exe[on Genera t on © 445ONorthGerrnanChurch Rd www.exebncorp.com March 7, 2019 LTR: BYRON 2019-0015 File: 1.10.0101 (1D.101) 2.01 .0300 (5A101)

United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

Byron Station Unit 1 Cycle 23 Core Operating Limits Report and Byron Station Unit 2 Cycle 21 Core Operating Limits Report In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR),

we are submitting the Unit 1 COLR, Revision 14, for Cycle 23, and the Unit 2 COLR, Revision 10, for Cycle 21 Core Operating Limits Report.

The COLRs for Byron Units 1 and 2 were updated for consistency with the Byron Technical Specification Amendment 205 that was approved via NRC Safety Evaluation, Issuance of Amendments Regarding Axial Flux Difference Technical Specifications, dated December 12, 2018.

Should you have any questions concerning this report, please contact Mr. Gary Contrady, acting Regulatory Assurance Manager, at (815) 406-2496.

Respectfully, Mark E. Kanavos Site Vice President Byron Generating Station Attachments: 1 Byron Station Unit 1 Cycle 23, COLR, Revision 14

2. Byron Station Unit 2 Cycle 21 COLR, Revision 10 MEK/GC/rm cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Generating Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT I CYCLE 23 EXELON TRACKING ID:

COLR BYRON UNIT I REVISION 14

COLR BYRON 1 Revision 14 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit I Cycle 23 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 (FNAH)

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 (5DM) MODE I and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (5DM) MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)

COLR BYRON 1 Revision 14 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 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 (SL5) (SL 2.1.1) 2.1.1 In MODES I 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.

D1.. C.6 0.8 Ftac:ioti o [\Jcrrinci Povet Figure 2.1 .1 1 Reactor Core Limits

COLR BYRON I Revision 14 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.2 SHUTDOWN MARGIN (5DM)

The 5DM limit for MODES , 2, 3, and 4 is:

2.2.1 The 5DM 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 5DM limit for MODE 5 is:

2.2.2 5DM 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 BOLIARO/HZP-MTC upper limit shall be +1 .81 3 x I O AkIkI°F.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x i04 Ak/k/°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x io AkIkI°F.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x I O 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) 228 113

COLRBYRON I Revision 14 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.5.1:

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

  • ##_)_2*;p 200 I 80 160

/

(0%, 1 62)

(100%, 161)

I 7

140 Co C) 2_ 120

/

0 CO D

NKD CC 0

tk 60

/

4ZL

//____

40 20 0

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

The bank position is given as follows:

Control Bank 0: (161/70) (P-100) + 161 (for 30 P 100)

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

COLR BYRON I Revision 14 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.6 Heat Flux Hot Channel Factor (F.) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

RTP F

FQ(Z) 2xK(Z) forPO.5 RTP F

FQ(Z) 9-xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTP= 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 L20:.L21 (6I.0jJ I

[j.00.924)I 0.9 0.8 Ri 0.7 a

LI a

N E

I._

0 z

LOCA Limiting

- 0.4 Envelope 0.3 0.2 0.1 0

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

COLR BYRON 1 Revision 14 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 23 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (PDMS) is OPERABLE, W(Z) = I .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 2.8.1a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 2.8.1b. The Expanded normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 FCQ(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F0(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 UFQ Uqu

  • Ue where:

Uqu Base F0 measurement uncertainty = I .05 when PDMS is inoperable (Uqu 5 defined by PDMS when OPERABLE.)

Ue Engineering uncertainty factor = I .03 2.6.4 PDMS Alarms:

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

COLR BYRON 1 Revision 14 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Table 2.6.2.a W(Z) versus Core Heightfor Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-J 0216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWDIMTU MWDIMTU 0.00 (core bottom) 1.1505 1.3370 1.3325 1.2559 0.20 1.1435 1.2986 1.2977 1.2280 0.40 1.1394 1.2821 1.2821 1.2128 0.60 1.1348 1.2661 1.2664 1.1961 0.80 1.1333 1.2266 1.2468 1.1850 1.00 1.1296 1.2041 1.2335 1.1822 1.20 1.1237 1.2131 1.2096 1.1778 1.40 1.1199 1.2066 1.2006 1.1730 1.60 1.1140 1.1891 1.1937 1.1656 1.80 1.1093 1.1736 1.1878 1.1592 2.00 1.1072 1.1591 1.1809 1.1524 2.20 1.1068 1.1421 1.1730 1.1434 2.40 1.1065 1.1276 1.1651 1.1352 2.60 1.1046 1.1111 1.1579 1.1246 2.80 1.1023 1.0971 1.1539 1.1154 3.00 1.0994 1.0908 1.1500 1.1184 3.20 1.0963 1.0897 1.1441 1.1226 3.40 1.0934 1.0894 1.1381 1.1287 3.60 1.0907 1.0885 1.1312 1.1429 3.80 1.0956 1.0893 1.1263 1.1571 4.00 1.0995 1.0892 1.1314 1.1702 4.20 1.1036 1.0891 1.1352 1.1818 4.40 1.1065 1.0888 1.1382 1.1916 4.60 1.1086 1.0868 1.1388 1.2001 4.80 1.1107 1.0855 1.1384 1.2065 5.00 1.1119 1.0834 1.1396 1.2110 5.20 1.1112 1.0811 1.1408 1.2143 5.40 1.1167 1.0785 1.1421 1.2160 5.60 1.1251 1.0849 1.1497 1.2344 5.80 1.1319 1.0926 1.1650 1.2497 6.00 1.1386 1.1003 1.1776 1.2630 6.20 1.1433 1.1070 1.1882 1.2717 6.40 1.1471 1.1128 1.1969 1.2784 6.60 1.1498 1.1176 1.2026 1.2801 6.80 1.1516 1.1218 1.2064 1.2799 7.00 1.1514 1.1277 1.2072 1.2757 7.20 1.1503 1.1369 1.2051 1.2676 7.40 1.1535 1.1466 1.2010 1.2576 7.60 1.1627 1.1558 1.1931 1.2427 7.80 1.1701 1.1709 1.1832 1.2279 8.00 1.1770 1.1886 1.1715 1.2101 8.20 1.1820 1.2037 1.1567 1.1884 8.40 1.1886 1.2189 1.1402 1.1667 8.60 1.1965 1.2314 1.1366 1.1548 8.80 1.2032 1.2380 1.1371 1.1473 9.00 1.2091 1.2436 1.1407 1.1415 9.20 1.2140 1.2554 1.1458 1.1704 9.40 1.2236 1.2575 1.1520 1.2080 9.60 1.2298 1.2603 1.1920 1.2540 9.80 1.2297 1.2603 1.2250 1.2940 10.00 1.2258 1.2588 1.2550 1.3290 10.20 1.2232 1.2596 1.2830 1.3600 10.40 1.2197 1.2634 1.3050 1.3860 10.60 1.2225 1.2669 1.3230 1.4130 10.80 1.2277 1.2754 1.3300 1.4283 11.00 1.2349 1.2857 1.3340 1.4431 11.20 1.2465 1.2914 1.3290 1.4270 11.40 1.2523 1.3088 1.3260 1.4130 11.60 1.2586 1.3162 1.2900 1.3810 11.80 1.2659 1.3239 1.2700 1.3728 12.00(coretop) 1.2767 1.3418 1.2567 1.3785 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 1 Revision 14 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 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 WCAP-10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWDIMTU MWDIMTU MWDIMTU 0.00 (core bottom) 1.2947 1.4548 1.4510 1.3553 0.20 1.2795 1.4106 1.4110 1.3288 0.40 1.2703 1.3931 1.3930 1.3163 0.60 1.2588 1.3758 1.3750 1.3068 0.80 1.2444 1.3330 1.3520 1.3016 1.00 1.2349 1.3097 1.3360 1.2976 1.20 1.2281 1.3155 1.3090 1.2907 1.40 1.2315 1.3066 1.2940 1.2838 1.60 1.2255 1.2847 1.2760 1.2739 1.80 1.2197 1.2662 1.2610 1.2650 2.00 1.2138 1.2469 1.2460 1.2551 2.20 1.2042 1.2240 1.2290 1.2412 2.40 1.1944 1.2037 1.2165 1.2293 2.60 1.1801 1.1809 1.2108 1.2135 2.80 1.1682 1.1723 1.2053 1.1996 3.00 1.1603 1.1675 1.1987 1.1837 3.20 1.1524 1.1607 1.1899 1.1812 3.40 1.1475 1.1569 1.1819 1.1860 3.60 1.1380 1.1509 1.1744 1.1900 3.80 1.1331 1.1459 1.1710 1.1932 4.00 1.1330 1.1401 1.1665 1.1944 4.20 1.1346 1.1318 1.1606 1.1942 4.40 1.1352 1.1240 1.1541 1.1932 4.60 1.1347 1.1147 1.1462 1.2001 4.80 1.1343 1.1064 1.1384 1.2065 5.00 1.1327 1.0972 1.1396 1.2110 5.20 1.1293 1.0928 1.1408 1.2143 5.40 1.1257 1.0887 1.1421 1.2160 5.60 1.1251 1.0849 1.1497 1.2344 5.80 1.1319 1.0926 1.1650 1.2497 6.00 1.1386 1.1003 1.1776 1.2630 6.20 1.1433 1.1070 1.1882 1.2717 6.40 1.1471 1.1128 1.1969 1.2784 6.60 1.1498 1.1176 1.2026 1.2801 6.80 1.1516 1.1218 1.2064 1.2799 7.00 1.1514 1.1277 1.2072 1.2757 7.20 1.1503 1.1369 1.2051 1.2676 7.40 1.1535 1.1466 1.2010 1.2576 7.60 1.1627 1.1558 1.1931 1.2427 7.80 1.1701 1.1709 1.1832 1.2279 8.00 1.1770 1.1886 1.1715 1.2101 8.20 1.1820 1.2037 1.1567 1.1884 8.40 1.1886 1.2189 1.1402 1.1667 8.60 1.1965 1.2314 1.1366 1.1548 8.80 1.2032 1.2380 1.1371 1.1473 9.00 1.2091 1.2436 1.1407 1.1415 9.20 1.2140 1.2554 1.1458 1.1704 9.40 1.2236 1.2575 1.1520 1.2080 9.60 1.2298 1.2603 1.1920 1.2540 9.80 1.2297 1.2603 1.2250 1.2940 10.00 1.2258 1.2588 1.2550 1.3290 10.20 1.2232 1.2596 1.2830 1.3600 10.40 1.2197 1.2634 1.3050 1.3860 10.60 1.2225 1.2669 1.3230 1.4130 10.80 1.2277 1.2754 1.3300 1.4283 11.00 1.2349 1.2857 1.3340 1.4431 11.20 1.2465 1.2914 1.3290 1.4270 11.40 1.2523 1.3088 1.3260 1.4130 11.60 1.2586 1.3162 1.2900 1.3810 11.80 1.2659 1.3239 1.2700 1.3728 12.00(coretop) 1.2767 1.3418 1.2567 1.3785 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 1 Revision 14 Page9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(Z) 150 1.0200 1028 1.0550 1203 1.0560 1730 1.0540 2800 1.0330 3200 1.0250 3500 1.0210 3600 1.0200 12400 1.0200 12700 1.0205 12800 1.0210 12965 1.0220 13141 1.0235 13317 1.0245 13600 1.0264 14050 1.0264 14200 1.0260 14500 1.0240 15200 1.0205 16000 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 BYRON 1 Revision 14 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN, (LCO 3.2.2) 2.7.1 FNAH F[1 .0 + PFAH(I .0 P)]

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

RTP TAH PFH 0.3

2.7.2 Uncertainty

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

UFAH UFAHm where:

UFHm Base FH measurement uncertainty = I .04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FH Warning Setpoint = 2% FAH Margin FNAH Alarm Setpoint = 0% FH 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 BYRON 1 Revision 14 Page 11 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 120 100 H°°°) H°°°)

LU 0

0

-I 80 naJaT Ope raon

\ ZntJ I

le 60 LU r

I-0 40 1

(20:5O) j(+25,50) 20 ..

9... V..,,

0

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

COLR BYRON I Revision 14 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 100 LU 0

- 80

-I 60 I-LU 40 I

0 20 0

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

COLR BYRON 1 Revision 14 Page 13 ofl5 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.1 0.1 The Overtemperature AT reactor trip setpoint K shall be equal to I 325.

2.1 0.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 00297 I °F.

2.10.3 The Overtemperature AT reactortrp setpoint pressure coefficientK3 shall be equal to 0.00135 I psi.

2.10.4 The nominal Tavgat RTP (indicated) T shall be less than or equalto 588.0 °F.

210.5 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 t1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel AT 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 t4shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant t5shall be equal to 4 sec.

2.1 0. 1 1 The measured reactor vessel average temperature lag time constant r6 shall be less than or equal to 2 sec.

2.10.12 The 1 (Al) positive breakpoint shall be +10% z\l.

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 1 Revision 14 Page 14 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.1 1 Reactor Trip System (RTS) Instrumentation (LCO 3.31) Overpower z\T Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to I .072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing Tavg.

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

2.1 1 .4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / °F when T > T.

2.11.5 The Overpower AT 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.

2.1 1 .7 The measured reactor vessel AT lead/lag time constant r 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.

2.1 1 .9 The measured reactor vessel AT lag time constant t3 shall be less than or equal to 2 sec.

2. 1 1 I 0

. The measured reactor vessel average temperature lag time constant r6 shall be less than or equal to 2 sec.

2.11 .11 The measured reactor vessel average temperature rate/lag time constant r7 shall be equalto 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 BYRON 1 Revision 14 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 23 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 2.1 3.1 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 1679 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 1799 c) for cycle burnups 16000 MWD/MTU 1438

2. 1 3.2 a) prior to initial criticality 740 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2009 c) for cycle burnups 16000 MWD/MTU 1578

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 21 EXELON TRACKING ID:

COLR BYRON 2 REVISION 10

COLRBYRON2 Revision 10 Page 1 of 15 CORE OPERATING LIMITS REPORT (COER) for BYRON UNIT 2 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 21 has been prepared in accordance with the requirements of Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCO5) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (5DM)

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 (FNAH)

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 (5DM) MODE I and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (5DM) MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)

COLR BYRON 2 Revision 10 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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 I 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.

2%7 1 Pi 5tO*

2.250pia

) I S60:Sii 1) c.y

.: I I ,

4 .

Ftac:ion j: t\jcr {rBJ I ()ve r.*

Figure 2.1 .1 : Reactor Core Limits

COLRBYRON2 Revision 10 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.2 SHUTDOWN MARGIN (5DM)

The 5DM limit for MODES I 2, 3, and 4 is:

2.2.1 The 5DM 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, 3.1.1, 3.1.h, and 3.1.j).

The 5DM limit for MODE 5 is:

2.2.2 5DM 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 ÷2.155 x 10 AkJk/°F.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 1O Ak/k/°F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i04 AkIkI°F.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1O z\kIkI°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:

I Park Position (step) Overlap Limit (step)

L 228 113

COLR BYRON 2 Revision 10 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure %5i:

Control Bank Insertion Limits Versus Percent Rated Thermal Power (27% 224) (77% 224) 220 200 180 160 (100%, 161) 140 0

I 120 100 0

C 80 0

60 40 20 0

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

COLR BYRON 2 Revision 10 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.6 Heat Flux Hot Channel FactorLFj)j (LCO 3.21) 2.6.1 Total Peaking Factor:

F FQ(Z) 9-xK(Z) forP0.5 F

FQ (Z) 9-xK(Z) for P > 0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FgTP 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)

(12. 0.924) 0.9 0.8 RI 0.7 a

U-0.6 0.5 LOCA Limiting 0.4 Envelope I

0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 101112 BOTTOM Core Height (ft) TOP

COLR BYRON 2 Revision 10 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (PDMS) is OPERABLE, W(Z) = I .00000 for all axial points.

b) When PDMS is inoperable, W(Z) is provided as:

1) Table 26.2.a are the normal operation W(Z) values that correspond to the NORMAL AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 28.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 FCQ(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWQ(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 UFQ Uqu

  • U where:

Uqu Base FQ measurement uncertainty = 1 .05 when PDMS is inoperable (Uqu 5 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

COLRBYRON2 Revision 10 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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 WCAP- 10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2208 1.3471 1.2396 1.22 18 0.20 1.2141 1.3171 1.2179 1.1946 0.40 1.2097 1.3005 1.2150 1.1830 0.60 1.2000 1.2868 1.2044 1.1817 0.80 1.1670 1.2581 1.1882 1.1804 1.00 1.1582 1.2253 1.1766 1.1775 1.20 1.1665 1.2300 1.1600 1.1729 1.40 1.1627 1.2178 1.1494 1.1666 1.60 1.1529 1.2072 1.1446 1.1574 1.80 1.1430 1.1904 1.1425 1.1490 2.00 1.1388 1.1759 1.1385 1.1399 2.20 1.1339 1.1608 1.1358 1.1278 2.40 1.1295 1.1465 1.1311 1.1160 2.60 1.1281 1.1318 1.1247 1.1074 2.80 1.1267 1.1185 1.1183 1.1114 3.00 1.1249 1.1167 1.1117 1.1180 3.20 1.1220 1.1151 1.1060 1.1238 3.40 1.1189 1.1127 1.1120 1.1286 3.60 1.1148 1.1094 1.1183 1.1428 3.80 1.1123 1.1073 1.1247 1.1579 4.00 1.1146 1.1077 1.1289 1.1720 4.20 1.1169 1.1068 1.1329 1.1849 4.40 1.1182 1.1059 1.1360 1.1957 4.60 1.1183 1.1038 1.1376 1.2044 4.80 1.1185 1.1018 1.1388 1.2118 5.00 1.1181 1.0994 1.1411 1.2163 5.20 1.1164 1.0961 1.1426 1.2194 5.40 1.1146 1.0920 1.1442 1.2218 5.60 1.1107 1.0895 1.1511 1.2384 5.80 1.1103 1.0919 1.1657 1.2550 6.00 1.1163 1.1003 1.1798 1.2686 6.20 1.1217 1.1075 1.1907 1.2782 6.40 1.1267 1.1150 1.1995 1.2849 6.60 1.1307 1.1205 1.2053 1.2866 6.80 1.1346 1.1251 1.2092 1.2874 7.00 1.1364 1.1302 1.2113 1.2842 7.20 1.1373 1.1353 1.2096 1.2762 7.40 1.1398 1.1413 1.2067 1.2665 7.60 1.1436 1.1463 1.2016 1.2528 7.80 1.1464 1.1508 1.1975 1.2371 8.00 1.1512 1.1568 1.1925 1.2193 8.20 1.1545 1.1630 1.1846 1.1976 8.40 1.1586 1.1659 1.1804 1.1845 8.60 1.1616 1.1756 1.1789 1.1810 8.80 1.1667 1.1838 1.1753 1.1759 9.00 1.1738 1.1904 1.1701 1.1695 9.20 1.1799 1.2023 1.1729 1.1677 9.40 1.1912 1.2130 1.1765 1.2010 9.60 1.2059 1.2286 1.1867 1.2453 9.80 1.2119 1.2462 1.2155 1.2835 10.00 1.2123 1.2595 1.2402 1.3172 10.20 1.2154 1.2712 1.2669 1.3492 10.40 1.2185 1.2823 1.2806 1.3796 10.60 1.2183 1.2956 1.2954 1.4120 10.80 1.2226 1.3067 1.3087 1.4265 11.00 1.2359 1.3168 1.3189 1.4363 11.20 1.2474 1.3221 1.3195 1.4312 11.40 1.2571 1.3390 1.3192 1.4171 11.60 1.2549 1.3403 1.2933 1.4001 11.80 1.2561 1.3435 1.2812 1.3860 12.00(coretop) 1.2672 1.3578 1.2729 1.3738 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 BYRON 2 Revision 10 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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 WCAP-10216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU O.OO(coreboftom) 1.3857 1.4842 1.3979 1.3238 0.20 1.3757 1.4485 1.3709 1.3178 0.40 1.3698 1.4276 1.3663 1.3154 0.60 1.3574 1.4136 1.3534 1.3138 0.80 1.3121 1.3805 1.3323 1.3099 1.00 1.2982 1.3443 1.3178 1.3050 1.20 1.3119 1.3467 1.2975 1.2976 1.40 1.3061 1.3312 1.2841 1.2893 1.60 1.2925 1.3174 1.2662 1.2765 1.80 1.2799 1.2954 1.2527 1.2655 2.00 1.2677 1.2758 1.2379 1.2539 2.20 1.2516 1.2542 1.2228 1.2378 2.40 1.2352 1.2351 1.2161 1.2223 2.60 1.2170 1.2162 1.2073 1.2043 2.80 1.2008 1.1992 1.1988 1.1902 3.00 1.1850 1.1860 1.1904 1.1779 3.20 1.1763 1.1795 1.1817 1.1691 3.40 1.1720 1.1738 1.1738 1.1704 3.60 1.1662 1.1686 1.1636 1.1739 3.80 1.1608 1.1632 1.1571 1.1763 4.00 1.1549 1.1572 1.1535 1.1786 4.20 1.1472 1.1486 1.1480 1.1849 4.40 1.1398 1.1411 1.1427 1.1957 4.60 1.1305 1.1315 1.1376 1.2044 4.80 1.1222 1.1224 1.1388 1.2118 5.00 1.1181 1.1124 1.1411 1.2163 5.20 1.1164 1.1013 1.1426 1.2194 5.40 1.1146 1.0920 1.1442 1.2218 5.60 1.1107 1.0895 1.1511 1.2384 5.80 1.1103 1.0919 1.1657 1.2550 6.00 1.1163 1.1003 1.1798 1.2686 6.20 1.1217 1.1075 1.1907 1.2782 6.40 1.1267 1.1150 1.1995 1.2849 6.60 1.1307 1.1205 1.2053 1.2866 6.80 1.1346 1.1251 1.2092 1.2874 7.00 1.1364 1.1302 1.2113 1.2842 7.20 1.1373 1.1353 1.2096 1.2762 7.40 1.1398 1.1413 1.2067 1.2665 7.60 1.1436 1.1463 1.2016 1.2528 7.80 1.1464 1.1508 1.1975 1.2371 8.00 1.1512 1.1568 1.1925 1.2193 8.20 1.1545 1.1630 1.1846 1.1976 8.40 1.1586 1.1659 1.1804 1.1845 8.60 1.1616 1.1756 1.1789 1.1810 8.80 1.1667 1.1838 1.1753 1.1759 9.00 1.1738 1.1904 1.1701 1.1695 9.20 1.1799 1.2023 1.1729 1.1677 9.40 1.1912 1.2130 1.1765 1.2010 9.60 1.2059 1.2286 1.1867 1.2453 9.80 1.2119 1.2462 1.2155 1.2835 10.00 1.2123 1.2595 1.2402 1.3172 10.20 1.2154 1.2712 1.2669 1.3492 10.40 1.2185 1.2823 1.2806 1.3796 10.60 1.2183 1.2956 1.2954 1.4120 10.80 1.2226 1.3067 1.3087 1.4265 11.00 1.2359 1.3168 1.3189 1.4363 11.20 1.2474 1.3221 1.3195 1.4312 11.40 1.2571 1.3390 1.3192 1.4171 11.60 1.2549 1.3403 1.2933 1.4001 11.80 1.2561 1.3435 1.2812 1.3860 12.00 (core top) 1.2672 1.3578 1.2729 1.3738 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 BYRON 2 Revision 10 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDIMTU) F Q(Z) 0 1.0205 677 1.0510 853 1.0568 1029 1.0600 1380 1.0528 2259 1.0250 2610 1.0200 9999 1.0200 13330 1.0200 14033 1.0246 14911 1.0235 15790 1.0240 16669 1.0252 17723 1.0264 18074 1.0260 18602 1.0270 18777 1.0262 19129 1.0242 19480 1.0220 19656 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 BYRON 2 Revision 10 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.7 Nuclear Enthalry Rise Hot Channel Factor (FN (LCO 3.22) 2.7.1 FNAH F![1.O + PFAH(l.O P)]

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

RTP TH PFAH 0.3

2.7.2 Uncertainty

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

UFAH UFHm where:

UFgm Ease FH measurement uncertainty = I .04 when PDMS is inoperable (UFHm 5 defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FH Warning Setpoint = 2% FNAH Margin FNAH Alarm Setpoint = 0% FNAH 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 I .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 10 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 120 100 I (-10,100) (+10,100)

LU C UnaccepgIe UnacceptaHe

a. 80 .. fl,.

-I LU 60 r

I-0 40 1

20 1 (20, 50)

(+25, 50)

[

1 0

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

COLR BYRON 2 Revision 10 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 100 LU 0

0 80

-J 60 I-LU 40 I

0 20 0

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

COLR BYRON 2 Revision 10 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.10 Reactor Trip System (RTS) Instrumentation (LCO 331) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactortrip setpoint K shall be equalto 1325.

2.1 0.2 The Overtemperature AT reactor trip setpoint Tavg coefficient 1(2 shall be equal to 0.0297 1 °F.

2.1 0.3 The Overtemperature AT reactor trip setpoint pressure coefficient K shall be equal to 0.00135 I psi.

2.1 04 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 t1 shall be equal to 8 sec.

2.1 0.7 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel \T lag time constant t3shall be less than or equal to 2 sec.

2.1 0.9 The measured reactor vessel average temperature lead/lag time constant t4 shall be equal to 33 sec.

2.1 0.1 0 The measured reactor vessel average temperature lead/lag time constant r5 shall be equal to 4 sec.

2.1 0. 1 1 The measured reactor vessel average temperature lag time constant t6 shall be less than or equal to 2 sec.

2.1 0.12 The f (Al) positive breakpoint shall be +1 0% Al.

2.10.13 The f (Al) negative breakpoint shall be -18% Al.

2.10.14 The f1 (Al) positive slope shall be +3.47% I % Al.

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

COLR BYRON 2 Revision 10 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21

2. 1 1 Reactor Trip System (RTS) Instrumentation (LCQ 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactortrip setpoint K4 shall be equal to 1.072.

2.1 1 .2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K shall be equal to 0.02 / °F for increasing Tavg.

2.1 1 .3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / °F for decreasing Tavg.

2.1 1 .4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / °F when T > V.

2.1 1 .5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 1 °F when T T.

2.1 1 .6 The nominal Tavg at RTP (indicated) T shall be less than or equal to 583.5 °F 2.1 1 .7 The measured reactor vessel AT lead/lag time constant t1 shall be equal to 8 sec.

2.1 1 .8 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.

2.1 1 .9 The measured reactor vessel AT 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 t6 shall be less than or equal to 2 sec.

2.1 1 I I

. The measured reactor vessel average temperature rate/lag time constant r7 shall be equal to 10 sec.

2.1 1 .12 The f2 (Al) positive breakpoint shall be 0 for all Al.

2.1 1 .1 3 The f2 (Al) negative breakpoint shall be 0 for all Al.

2.1 1 .14 The f2 (Al) positive slope shall be 0 for all Al.

2.11.15 The f2(Al) negative slope shall be 0 forall Al.

COLR BYRON 2 Revision 10 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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.

2.1 3.2 To maintain keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or5 (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. 1 3. 1 a) prior to initial criticality I 714 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU - 829 c) for cycle burnups 16000 MWD/MTU 1443 2.13.2 a) priorto initial criticality 1789 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2056 c) for cycle burnups 16000 MWD/MTU 1585
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