ML22181A049
| ML22181A049 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/30/2022 |
| From: | Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22181A047 | List: |
| References | |
| BYRON 2022-0039 | |
| Download: ML22181A049 (16) | |
Text
CORE OPERATING LIMITS REPORT (COLR)
FOR
BYRON UNIT 1 CYCLE 25
CONSTELLATION TRACKING ID:
COLR BYRON UNIT 1 REVISION 17 COLR BYRON 1 Revision 17 Page 1 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I 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 (Fo(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNLIH)
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
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 :c: 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 BYRON 1 Revision 17 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.
680---.---------,------,--------r-------,------,--------,
24""1 psia
Q) >--
- -- \\ ---.....-.._,,_~ *------- \\
--- !'--____ \\\\
\\
580 -+----'--'---'---+-'---'----'--1---'----'--'---+----'--'----'----+--------'-----'-----Jl----'---'-----'----1 I I I I I I I I I I I I I I I I I I \\
0 0.2 0.4 G.6 Froctiori of l\\lcrninul
Figure 2.1.1: Reactor Core Limits COLR BYRON 1 Revision 17 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% 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 +2.087 x 10-5 Lik/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 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: SOL 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 1 Revision 17 Page 4 of 15
CORE OPERA TING LIMfTS 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
180
~ 160 --<~---- (100%, 161) i 140 -+------+----+--------+---------- j BANKC,---j-----,-------j---------~,
~ !
Cl)
~ 120 C:
0 E (/)
~ 100 "{-----+----+--1---
.l<:
C:
C'C!
Ill
"'C 0
c::
60
20
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 ~ P ~ 100)
Where P is defined as the core power (in percent).
COLRBYRON 1 Revision 17 Page 5 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25
2.6 Heat Flux Hot Channel Factor (Fo(Z)) (LCO 3.2.1)
2.6.1 Total Peaking Factor:
pR1P FQ(Z) ::,; _Q_xK(Z) for P::;; 0.5 0.5
pR1P FQ(Z)::;;-Q-xK(Z) forP>0.5 p
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
Fo<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
1.1 (0.0, 1.0) (6.0, 1.0) (12.0, 1.0)
1
0.9
0.8
N 0.7 0
u.
"C Cl) 0.6 (ti E
... 0.5 0
z -+-LOCA Limiting ~
N 0.4 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 17 Page 6 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 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 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, Urn, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula
[j F(J = l/ q11
- ll C
where:
Uqu = Base Fo measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS and cannot be less than i.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 I Revision 17 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 150 4000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom} 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 top} 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 l Revision 17 Page 8 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT l 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 150 4000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core 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 1000 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 (core top) 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 COLR BYRON l Revision 17 Page 9 of 15
CORE OPERA TING 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) Foc(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 burn ups.
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)
- 5 1% e::3% 2:: 1% 2:: 1%
> 1% AND :5 2% e::6% e::2% e::2%
> 2% AND :5 3% e::9% e::3% e::3%
>3% e:: 50% N/A N/A COLR BYRON I Revision 17 Page 10 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25
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 PFAH = 0.3
2.7.2 Uncertainty
The uncertainty, UF11H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN"H shall be calculated by the following formula:
where:
UFLIHm = Base FNAH measurement uncertainty= 1.04 when PDMS is inoperable (UHHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)
2.7.3 PDMS Alarms:
FN,\\H Warning Setpoint = 2% FN11H Margin FN,,H Alarm Setpoint = 0% FNL\\H 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
2.9.2 PDMS Alarms:
DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin COLR BYRON 1 Revision 17 Page 11 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25
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 0
- 0. 80
....I
<(
~
0:::
w 60
- I: Operation I-Cl w
~ 40 0:::
-0
- 20
0
-50 30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLRBYRON I Revision 17 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
100 LU c:::
2 80
...J
<(
~
c:::
LU 60
- c Operation f-Cl LU
~ 40 c:::
-0
~
20
0
-50 30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLRBYRON l Revision 17 Page 13 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25
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 Tavg 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 I psi.
2.10.4 The nominal Tav 9 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 Li T lead/lag time constant T1 shall be equal to 8 sec.
2.10. 7 The measured reactor vessel Li T lead/lag time constant T2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel Li 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 1"4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant Ts shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant T6 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 (Lil) "positive" slope shall be +3.47% /%Lil.
2.10.15 The f1 (Lil) "negative" slope shall be -2.61 % I% Lil.
COLR BYRON 1 Revision 17 Page 14 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 25
2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower il T Setpoint Parameter Values
2.11.1 The Overpower il T reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower il 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 il T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tavg.
2.11.4 The Overpower il T reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0.00245 I °F when T > T".
2.11.5 The Overpower il T reactor trip setpoint Tavg heatup coefficient Ks 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.
2.11. 7 The measured reactor vessel il T lead/lag time constant T1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel il T lead/lag time constant T2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel il 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 Ts shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant T7 shall be equal to 10 sec.
2.11.12 The fa (ill) "positive" breakpoint shall be O for all ill.
2.11.13 The fa (ill) "negative" breakpoint shall be O for all Lli.
2.11.14 The fz (ill) "positive" slope shall be O for all ill.
2.11.15 The fa (ill) "negative" slope shall be O for all ill.
COLR BYRON I Revision 17 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 (Tav 9 ) 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