BYRON 2021-0064, Cycle 25 Core Operating Limits Report

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Cycle 25 Core Operating Limits Report
ML21271A055
Person / Time
Site: Byron Constellation icon.png
Issue date: 09/28/2021
From: Kowalski J
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2021-0064
Download: ML21271A055 (17)
v • d • e


Text

Byron Generating Station Exelon Generation 4450 North German Church Rd Byron. IL 61010-9794 www.exeloncorp.com September 28, 2021 LTR: BYRON 2021-0064 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 1 Renewed Facility Operating License No. NPF-37 NRC Docket No. STN 50-454

Subject:

Byron Station Unit 1 Cycle 25 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 16, for Cycle 25.

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

Respectfully, John J. Kowalski Site Vice President Byron Generating Station

Attachment:

Byron Station Unit 1 Cycle 25, COLR, Revision 16 JJK/LZ/mf cc: Regional Administrator- NRC Region Ill NRC Senior Resident Inspector - Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 25 EXELON TRACKING ID:

COLR BYRON UNIT 1 REVISION 16

COLRBYRON 1 Revision 16 Page 1 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 25 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 (Fa(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN6H)

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)

COLRBYRON 1 Revision 16 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 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.

08c-.----------------------------.--------

.:!-t71 psia 56C u....

~

(J)

~

' --~

(1) 6~G I....

n;,.._

(1) c....

E (1) f-- 6/0 cc;......

C (1)

<(

fiCC sec-+-_..........._ _.__-+-........-'--....__-+-...........-..._...._-+-........-..._.........-+-............._...___._--+_..._.....__...~

\J 0.2  :.l./4 G.6 0.8 Fracion of Ncrrinol Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 1 Revision 16 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 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% ~k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.087 x 10-5 ~k/k/°F.

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

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

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 ~k/k/°F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank 0. 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 1 Revision 16 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 Figure 2.5.1:

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

/

V /

/

200 180 ~

VcsANKB I ~

/

c

= 160 / / (100%, 161) 1L I!!

I "CJ

.c

~

3: 140 1(0%, 162)

IBANKC I

/

s Q.

~ 120 / ,/

/'

C

.2 Q.

"'0 100

/ V

/ IBANKD I

.II:

C ca m 80 / /

V "CJ 0

0:: /

60 / /

40

/

,r1co%, 47) I

~

V 20

~/

(30%.0)v 0

0 10 20 30 40 50 60 70 80 90 100 Relative 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 1 Revision 16 Page 5 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 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 F0 (Z) ~ 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 Fa(Z) as a Function of Core Height (0 .0 ' 1 0) (6 .0, 1.0) . ' .

(12010) 1.1 1

0.9 0.8 0.7 aN LL "C 0.6

-~ii

...0 E 0.5

~

z -+-LOCA Limiting 0.4

c:

Envelope 0.3 0.2 0.1 0

0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP

COLR BYRON 1 Revision 16 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 25 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, UFO, to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula uFQ = 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 1 Revision 16 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 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 160 4000 14000 20000 lfeetl MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 /core bottoml 1.2638 1.3837 1.2311 1.2018 0.20 1.2570 1.3723 1.2249 1.1946 0.40 1.2571 1.3673 1.2299 1.1968 0.60 1.2611 1.3664 1.2360 1.2045 0.80 1.2698 1.3685 1.2484 1.2188 1.00 1.2691 1.3604 1.2515 1.2239 1.20 1.2598 1.3447 1.2450 1.2183 1.40 1.2464 1.3248 1.2348 1.2089 1.60 1.2325 1.3035 1.2245 1.1999 1.80 1.2174 1.2806 1.2133 1.1903 2.00 1.2010 1.2562 1.2008 1.1796 2.20 1.1836 1.2307 1.1875 1.1681 2.40 1.1659 1.2050 1.1739 1.1563 2.60 1.1485 1.1797 1.1604 1.1445 2.80 1.1314 1.1554 1.1477 1.1332 3.00 1.1262 1.1363 1.1371 1.1199 3.20 1.1259 1.1275 1.1315 1.1136 3.40 1.1253 1.1273 1.1314 1.1175 3.60 1.1243 1.1258 1.1303 1.1288 3.80 1.1230 1.1238 1.1302 1.1411 4.00 1.1207 1.1214 1.1335 1.1531 4.20 1.1191 1.1183 1.1385 1.1644 4.40 1.1194 1.1147 1.1424 1.1747 4.60 1.1198 1.1109 1.1457 1.1838 4.80 1.1203 1.1103 1.1481 1.1914 5.00 1.1215 1.1106 1.1496 1.1974 5.20 1.1223 1.1104 1.1499 1.2017 5.40 1.1226 1.1097 1.1496 1.2040 5.60 1.1259 1.1092 1.1496 1.2049 5.80 1.1310 1.1106 1.1497 1.2119 6.00 1.1396 1.1147 1.1533 1.2251 6.20 1.1526 1.1194 1.1646 1.2394 6.40 1.1662 1.1227 1.1736 1.2505 6.60 1.1784 1.1239 1.1827 1.2590 6.80 1.1891 1.1327 1.1905 1.2647 7.00 1.1981 1.1456 1.1961 1.2675 7.20 1.2051 1.1555 1.1998 1.2674 7.40 1.2102 1.1642 1.2014 1.2642 7.60 1.2132 1.1715 1.2008 1.2583 7.80 1.2124 1.1755 1.1980 1.2479 8.00 1.2138 1.1821 1.1928 1.2393 8.20 1.2202 1.1942 1.1873 1.2357 8.40 1.2246 1.2050 1.1856 1.2302 8.60 1.2315 1.2185 1.1835 1.2291 8.80 1.2391 1.2354 1.1854 1.2284 9.00 1.2497 1.2590 1.1940 1.2248 9.20 1.2615 1.2879 1.2069 1.2232 9.40 1.2675 1.3114 1.2209 1.2334 9.60 1.2964 1.3347 1.2343 1.2481 9.80 1.3326 1.3555 1.2492 1.2666 10.00 1.3638 1.3717 1.2648 1.2866 10.20 1.3932 1.3901 1.2778 1.3038 10.40 1.4172 1.4183 1.2879 1.3184 10.60 1.4372 1.4435 1.2954 1.3301 10.80 1.4557 1.4666 1.3001 1.3400 11.00 1.4785 1.4937 1.3060 1.3474 11.20 1.4840 1.5027 1.3022 1.3409 11.40 1.4158 1.4480 1.2604 1.3002 11.60 1.3527 1.4091 1.2170 1.2545 11.80 1.3468 1.4067 1.1938 1.2328 12.00 (core tool 1.3258 1.4033 1.2043 1.2568 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 1 Revision 16 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 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 Byron SR 3.2.1.2 Bases)

Height 160 4000 14000 20000 lfeetl MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 lcore bottom! 1.3688 1.4875 1.3086 1.3096 0.20 1.3603 1.4742 1.3026 1.3005 0.40 1.3603 1.4679 1.3048 1.3014 0.60 1.3623 1.4660 1.3117 1.3083 0.80 1.3701 1.4670 1.3239 1.3221 1.00 1.3675 1.4571 1.3261 1.3257 1.20 1.3559 1.4393 1.3183 1.3180 1.40 1.3398 1.4169 1.3064 1.3060 1.60 1.3229 1.3931 1.2942 1.2942 1.80 1.3045 1.3674 1.2808 1.2814 2.00 1.2843 1.3398 1.2657 1.2672 2.20 1.2629 1.3111 1.2498 1.2519 2.40 1.2410 1.2820 1.2329 1.2359 2.60 1.2196 1.2531 1.2154 1.2194 2.80 1.2001 1.2257 1.2053 1.2034 3.00 1.1904 1.2005 1.2005 1.1841 3.20 1.1877 1.1827 1.1964 1.1762 3.40 1.1829 1.1755 1.1917 1.1834 3.60 1.1777 1.1704 1.1865 1.1908 3.80 1.1721 1.1652 1.1802 1.1972 4.00 1.1651 1.1613 1.1781 1.2034 4.20 1.1589 1.1582 1.1784 1.2084 4.40 1.1555 1.1541 1.1775 1.2122 4.60 1.1514 1.1494 1.1757 1.2147 4.80 1.1464 1.1440 1.1730 1.2151 5.00 1.1411 1.1379 1.1690 1.2156 5.20 1.1347 1.1311 1.1641 1.2157 5.40 1.1284 1.1235 1.1588 1.2139 5.60 1.1284 1.1151 1.1556 1.2154 5.80 1.1301 1.1131 1.1591 1.2250 6.00 1.1386 1.1147 1.1709 1.2391 6.20 1.1535 1.1194 1.1831 1.2519 6.40 1.1675 1.1232 1.1931 1.2617 6.60 1.1801 1.1304 1.2027 1.2687 6.80 1.1913 1.1382 1.2109 1.2727 7.00 1.2007 1.1464 1.2167 1.2737 7.20 1.2082 1.1557 1.2204 1.2715 7.40 1.2137 1.1638 1.2217 1.2663 7.60 1.2171 1.1709 1.2206 1.2582 7.80 1.2172 1.1755 1.2174 1.2456 8.00 1.2185 1.1823 1.2109 1.2350 8.20 1.2253 1.1937 1.2039 1.2291 8.40 1.2301 1.2046 1.2021 . 1.2213 8.60 1.2377 1.2181 1.1993 1.2222 8.80 1.2447 1.2354 1.2024 1.2267 9.00 1.2487 1.2597 1.2127 1.2310 9.20 1.2513 1.2885 1.2227 1.2334 9.40 1.2575 1.3119 1.2345 1.2315 9.60 1.2827 1.3353 1.2418 1.2374 9.80 1.3130 1.3559 1.2479 1.2542 10.00 1.3399 1.3721 1.2522 1.2740 10.20 1.3653 1.3903 1.2527 1.2909 10.40 1.3859 1.4182 1.2575 1.3050 10.60 1.4026 1.4433 1.2681 1.3164 10.80 1.4202 1.4661 1.2781 1.3259 11.00 1.4384 1.4930 1.2867 1.3330 11.20 1.4364 1.5018 1.2839 1.3264 11.40 1.3747 1.4469 1.2473 1.2859 11.60 1.3203 1.4078 1.2075 1.2405 11.80 1.3191 1.4053 1.1890 1.2190 12.00 lcore tool 1.3059 1.4016 1.2081 1.2424 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 1 Revision 16 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 Table 2.6.2.c Penalty Factors in Excess of 2%

Cycle Burnup Penalty Factor (MWD/MTU) Fco(z) 0 1.0200 150 1.0750 371 1.0820 592 1.0830 842 1.0800 1033 1.0760 2137 1.0290 2578 1.0200 6111 1.0200 6532 1.0280 7214 1.0345 7656 1.0320 8098 1.0200 8981 1.0200 9201 1.0225 9643 1.0209 10084 1.0200 10747 1.0200 11188 1.0210 11409 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c (11409 MWD/MTU and over) shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLR BYRON 1 Revision 16 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN6H} (LCO 3.2.2) where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F§i!f = 1.70 PF6H = 0.3

2.7.2 Uncertainty

The uncertainty, UF6H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN6H shall be calculated by the following formula:

where:

UFtJHm = Base FN6H measurement uncertainty = 1.04 when PDMS is inoperable (UF6Hm is defined by PDMS and cannot be less than 1.04 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 BYRON l Revision 16 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT l CYCLE 25 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 1 (-10, 1aai 1 1{+la, 10ai 1 100 -

er::

w

~ u~ ~ceptab ~ -

! I Unacceptable

0. 80

....I oieration' Operation

<C I

E ffi 60 +---+---+---~-, - - - ' ~ Accep-=

ta=b~le'--+--- *

~ Ope~ation C

!~ 40 ____ __._~1,*I. (-20, so~ JI - (+2s, so) - -

1

20  ;---+-----+--- _ --L.__

0 -t----

i i -

r I

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

COLRBYRON 1 Revision 16 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 -,-- --.-- - ~ - - -- ..----.---- ,-----,----i- * * - -

1 I I I(-15, 100) I I(+10, 100) I I 100 + - - - + - - + - - - + - - - - -......- -k-- - + - - ~- --+------1 Ij

a. 80 Unacceotab

+ - --+-~ -

01oeration/

e

+ --

)'-+---- I \

\l I ulac,eptible

- r - - - - + - - - - - 1 , - - -, ---,------+--'---; -- - -

Operatii n w 60 *>--- >----,~- - - ---+- A_c_ce....,.>_ta_b_le_____ r\,.\__--+-_ _ ,, _ _

~ / ,

1 Oper,ation  !

~ 40 - - . (-3s, 50) 1

! - --1(+25, 50) I -** -- -

....0 I

';ft.

20 +--- --+- - + - - - - + - - - + - - - - + - -- -t-----+------1---.;.--*** --

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

COLRBYRON 1 Revision 16 Page 13 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature I). T Setpoint Parameter Values 2.10.1 The Overtemperature I).T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature l).T reactor trip setpoint Tav9 coefficient K2 shall be equal to 0.0297 / °F.

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

2.10.4 The nominal Tav9 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 I). T lead/lag time constant t1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel I).T 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 *4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant -rs 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 (1).1) "positive" breakpoint shall be +10% 1).1 .

2.10.13 The f1 (!).I) "negative" breakpoint shall be -18% 1).1.

2.10.14 The f1 (!).I) "positive" slope shall be +3.47% / % 1).1.

2.10.15 The f1 (!).I) "negative" slope shall be -2.61 % I% 1).1.

COLRBYRON 1 Revision 16 Page 14 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25 2.11 Reactor Trip System CRTS) Instrumentation (LCO 3.3.1) - Overpower ll T Setpoint Parameter Values 2.11 .1 The Overpower~T reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower 6.T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 / °F for increasing Tavg.

2.11.3 The Overpower 6.T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing T avg.

2.11.4 The Overpower llT reactor trip setpoint Tavg heatup coefficient Ke shall be equal to 0.00245 / °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 T :5 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 ll T lead/lag time constant ,1 shall be equal to 8 sec.

2.11 .8 The measured reactor vessel 6.T lead/lag time constant ,2 shall be equal to 3 sec.

2.11 .9 The measured reactor vessel ll 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 te 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 fz (Ill) "positive" breakpoint shall be 0 for all Ill.

2 .11.13 The fz (Ill) "negative" breakpoint shall be 0 for all Ill.

2.11 .14 The fz (Ill) "positive" slope shall be 0 for all Ill.

2.11 .15 The fz (Ill) "negative" slope shall be 0 for all Ill.

COLRBYRON I Revision 16 Page 15 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 25 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 (T avg) 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 (oom) 2.13.1 a) prior to initial criticality 1753 b) for cycle burnups;:: 0 MWD/MTU 1895 and < 16000 MWD/MTU c) for cycle burnups;:: 16000 1491 MWD/MTU 2.13.2 a) prior to initial criticality 1821 b) for cycle burnups;:: 0 MWD/MTU 2117 and < 16000 MWD/MTU c) for cycle burnups;:: 16000 1621 MWD/MTU

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