BYRON 2024-0046, Cycle 27 Core Operating Limits Report
| ML24263A019 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/19/2024 |
| From: | Welt H Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| BYRON 2024-0046, 5A.101, 1D.101 | |
| Download: ML24263A019 (1) | |
Text
Constellation Energy Generation. LLC (CEG)
Byron Station Constellation 4450 N German Church Road Byron. IL 61010-9794
vvww constellat,onenergy com
September 19, 2024
L TR: BYRON 2024-0046 File: 5A.101 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 27 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 19, for Cycle 27.
Should you have any questions concerning this report, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (779) 231-6606.
Respectfully,
Harris Welt Site Vice President Byron Generating Station
Attachment:
Byron Station Unit 1 Cycle 27, COLR, Revision 19
HW/DG/hh
cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Byron Station CORE OPERATING LIMITS REPORT (COLR)
FOR
BYRON UNIT 1 CYCLE 27
CONSTELLATION TRACKING ID:
COLR BYRON UNIT 1 REVISION 19 COLR BYRON 1 Revision 19 Page 1 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
1.0 CORE OPERATING LIMITS REPORT
This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 27 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 (MTG)
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 (FN.1H)
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.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 19 Page 2 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 27
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.
<C
\\.
- I F1,J,_j I" I I_ 1,, i 11 u I I',_.
Figure 2.1.1: Reactor Core Limits COLRBYRON I Revision 19 Page 3 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
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% 6k/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.f, 3.1.h, and 3.1.j).
The SOM limit for MODE 5 is:
2.2.2 SOM shall be greater than or equal to 1.3% 6k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.915 x 10-5 6k/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 4 6k/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1Q-4 6k/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 6k/k/°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power
2.4 Shutdown Bank Insertion Limits (LCO 3.1.5)
2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6)
2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Limit (step) 231 115 COLRBYRON 1 Revision 19 Page 4 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 27
Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power
224 (27%, 224) (77%, 224) 220 r --, -
I 200 -- --+
I 180 -r-- t----+--
C: I I __ -- [_ - ---- (100%, 161) 3: 160 J res I
... r--
"C I I
.c
- I
~ 140 --- - +-
(/)
a.
Q)
!!?, 120 -
C:
0
- E (/) 100 ---,-----
- a. 0 IBANK DI i
.lii: C: ! I CD T ro 80 ---
"C 0:::: 60 ---0
40 ------ - ----
20
0 0 10 20 30 40 50 60 70 80 90 100
Relative Po we r (Percent)
The bank position is given as follows:
Control Bank D: (161/70) * (P-100) + 161 (for 30 :5 P :5 100)
Where P is defined as the core power (in percent).
COLR BYRON 1 Revision 19 Page 5 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT l CYCLE 27
2.6 Heat Flux Hot Channel Factor (Fo(Z)) (LCO 3.2.1)
2.6.1 Total Peaking Factor:
FRTP F0 (Z)::=;- 00.5 -xK(Z) forP::=;0.5
FRTP F0 (Z) ::=;-0-xK(Z) forP>0.5 p
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
F8TP = 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, ~L -- ~ _ -- ---- (6.0, 1.0) ~---- --~- _ ~-~O~OJ
1.....
'W'
0.9
0.8
- N 0.7
- a LL "C 0.6
- Q) --~I __ _
iii E [..-LOCA Limiting Envelope !
... 0.5 0 I z
N 0.4.
I
~
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 COLRBYRON 1 Revision 19 Page 6 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
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 8.1 and 8.2.
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 FQ = uqu. Uc
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 I Revision 19 Page 7 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
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 5000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2833 1.3976 1.2316 1.1912 0.20 1.2751 1.3849 1.2254 1.1823 0.40 1.2746 1.3794 1.2312 1.1881 0.60 1.2786 1.3783 1.2381 1.1952 0.80 1.2877 1.3808 1.2520 1.2111 1.00 1.2866 1.3723 1.2558 1.2172 1.20 1.2762 1.3559 1.2494 1.2118 1.40 1.2615 1.3351 1.2390 1.2024 1.60 1.2462 1.3130 1.2284 1.1933 1.80 1.2297 1.2891 1.2168 1.1837 2.00 1.2117 1.2636 1.2038 1.1729 2.20 1.1926 1.2371 1.1896 1.1613 2.40 1.1734 1.2105 1.1753 1.1493 2.60 1.1544 1.1843 1.1630 1.1374 2.80 1.1345 1.1584 1.1522 1.1255 3.00 1.1218 1.1360 1.1405 1.1140 3.20 1.1189 1.1234 1.1335 1.1099 3.40 11188 1.1214 1.1335 1.1139 3.60 1.1191 1.1201 1.1385 1.1269 3.80 1.1190 1.1183 1.1436 1.1405 4.00 1.1182 1.1162 1.1482 1.1531 4.20 1.1178 1.1134 1.1524 1.1653 4.40 1.1190 1.1102 1.1560 1.1764 4.60 11195 1.1081 1.1589 1.1863 4.80 1.1196 1.1088 1.1607 1.1947 5.00 1.1190 1.1103 1.1616 1.2016 5.20 1.1192 11108 1.1612 1.2064 5.40 1.1217 1.1107 1.1596 1.2094 5.60 1.1244 1.1097 1.1577 1.2128 5.80 1.1265 1.1119 1.1575 1.2197 6.00 1.1353 1.1176 1.1615 1.2321 6.20 1.1512 1.1226 1.1732 1.2470 6.40 1.1650 1.1265 1.1826 1.2584 6.60 1.1775 1.1300 1.1920 1.2670 6.80 1.1886 1.1387 1.2001 1.2728 7.00 1.1979 1.1507 1.2057 1.2756 7.20 1.2054 1.1613 1.2094 1.2753 7.40 1.2109 1.1703 1.2107 1.2719 7.60 1.2144 1.1779 1.2099 1.2657 7.80 1.2145 1.1821 1.2066 1.2549 8.00 1.2159 1.1888 1.2013 1.2459 8.20 1.2229 1.2011 1.1961 1.2418 8.40 1.2279 1.2119 1.1927 1.2358 8.60 1.2355 1.2256 1.1895 1.2329 8.80 1.2440 1.2409 1.1922 1.2280 9.00 1.2552 1.2586 1.2014 1.2250 9.20 1.2681 1.2775 1.2138 12308 9.40 1.2750 1.2909 1.2279 1.2410 9.60 1.2900 1.3066 1.2376 1.2592 9.80 1.3144 1.3323 1.2458 1.2809 1000 1.3415 1.3660 1.2536 1.3011 10.20 1.3664 1.3998 1.2606 1.3190 10.40 1.3895 1.4286 1.2687 1.3338 10.60 1.4111 1.4531 1.2750 1.3460 10.80 1.4210 1.4756 1.2770 1.3534 11.00 1.4258 1.5003 1.2779 1.3587 11.20 1.4152 1.5140 1.2767 1.3604 11.40 1.3548 1.4683 1.2616 1.3454 11.60 1.3054 1.4215 1.2422 1.3247 11.80 1.3000 1.4141 1.2380 1.3109 12.00 (core top) 1.2924 1.4036 1.2282 1.2912 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 19 Page 8 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 27
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 5000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU O 00 (core bottom) 1.3681 1.4883 1.3373 1.3325 0.20 1.3589 1.4741 1.3295 1.2909 0.40 1.3589 1.4675 1.3346 1.2834 0.60 1.3612 1.4657 1.3408 1.2860 0.80 1.3699 1.4671 1.3544 1.3038 1.00 1.3677 1.4571 1.3570 1.3053 1.20 1.3558 1.4389 1.3488 1.3000 1.40 1.3392 1.4161 1.3362 1.2902 1.60 1.3219 1.3917 1.3231 1.2773 1.80 1.3030 1.3654 1.3087 1.2619 2.00 1.2823 1.3372 1.2927 1.2457 2.20 1.2604 1.3078 1.2752 1.2300 2.40 1.2379 1.2782 1.2571 1.2151 2.60 1.2152 1.2489 1.2387 1.1997 2.80 1.1952 1.2191 1.2194 1.1846 3.00 1.1855 1.1959 1.2034 1.1808 3.20 1.1831 1.1809 1.1923 1.1821 3.40 1.1788 1.1704 1.1859 1.1827 3.60 1.1741 1.1663 1.1863 1.1841 3.80 1.1689 1.1617 1.1878 1.1911 4.00 1.1626 1.1575 1.1891 1.1999 4.20 1.1563 1.1547 1.1897 1.2069 4.40 1.1518 1.1509 1.1895 1.2129 4.60 1.1481 1.1466 1.1883 1.2174 4.80 1.1439 1.1416 1.1860 1.2200 5.00 1.1390 1.1358 1.1823 1.2225 5.20 1.1333 1.1294 1.1775 1.2245 5.40 1.1275 1.1222 1.1712 1.2242 5.60 1.1257 1.1131 1.1622 1.2254 5.80 1.1278 1.1123 1.1662 1.2364 6.00 1.1347 1.1178 1.1800 1.2525 6.20 1.1433 1.1226 1.1935 1.2662 6.40 1.1523 1.1263 1.2047 1.2769 6.60 1.1609 1.1335 1.2136 1.2846 6.80 1.1694 1.1417 1.2202 1.2891 7.00 1.1785 1.1507 1.2243 1.2903 7.20 1.1875 1.1607 1.2257 1.2882 7.40 1.1948 1.1697 1.2246 1.2829 7.60 1.2007 1.1771 1.2211 1.2746 7.80 1.2049 1.1820 1.2134 1.2615 8.00 1.2073 1.1891 1.2077 1.2503 8.20 1.2081 1.2004 1.2073 1.2440 8.40 1.2072 1.2113 1.2052 1.2357 8.60 1.2035 1.2251 1.2058 1.2309 8.80 1.2036 1.2407 1.2107 1.2230 9.00 1.2127 1.2588 1.2234 1.2202 9.20 1.2315 1.2777 1.2376 1.2300 9.40 1.2569 1.2912 1.2468 1.2396 9.60 1.2815 1.3069 1.2560 1.2564 9.80 1.3041 1.3325 1.2623 1.2772 1000 1.3252 1.3664 1.2651 1.2969 10.20 1.3440 1.3999 1.2698 1.3142 10.40 1.3608 1.4285 1.2810 1.3285 10.60 1.3761 1.4528 1.2930 1.3402 10.80 1.3796 1.4751 1.3021 1.3472 11.00 1.3815 1.4996 1.3084 1.3522 11.20 1.3738 1.5131 1.3103 1.3536 11.40 1.3169 1.4671 1.2998 1.3383 11.60 1.2704 1.4202 1.2829 1.3175 11.80 1.2666 1.4126 1.2717 1.3034 12.00 (core top) 1.2614 1.4018 1.2559 1.2835 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 I Revision 19 Page 9 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWD/MTU) Foc(Z) 0 1.0200 150 1.0650 700 1.0950 1100 1.0950 2500 1.0500 3475 1.0300 4140 1.0200 6135 1.0200 6350 1.0300 6900 1.0400 7500 1.0390 7900 1.0350 8574 1.0200 9460 1.0200 9650 1.0230 10125 1.0200 18770 1.0200 19300 1.0275 20000 1.0260 24160 1.0260
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::; 2% 2: 6% 2: 2% 2: 2%
> 2% AND::; 3% 2: 9% 2: 3% 2:3%
>3% 2: 50% NIA N/A COLR BYRON I Revision 19 Page 10 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN,H) (LCO 3.2.2)
2.7.1 FN"H::: rn~P[1.o + PF,,H(1.o-P)J
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
F~~P = 1.70 PF1,H = 0.3
2.7.2 Uncertainty
The uncertainty, UF1,H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN1H shall be calculated by the following formula:
where:
UF1Hm = Base FN1H measurement uncertainty= 1.04 when PDMS is inoperable (UF1Hm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)
2.7.3 PDMS Alarms:
FN1H Warning Setpoint = 2% FN.,H Margin FN.,H Alarm Setpoint = 0% FN1H 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 I Revision 19 Page 11 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 27
Figure 2.8.1.a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power
Normal Axial Flux Difference Limits
120
1 (-10, 100) 1 1 (+10, 100) I 100 ex::
w
$ Unacceptable Unacceptable
~ 80 Operation
....I Operation
<(
~ ex::
w 60.L\\cc~pta g(e.
- c Operation l-o w
!=i: 40 ex:: 1 (-20, 50) 1 (+25, 50) 1
-0
~
20
0
-50 -40 -30 -20 -10 0 10 20 30 40 so AXIAL FLUX DIFFERENCE(%)
COLRBYRON 1 Revision 19 Page 12 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
Figure 2.8.1.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power
Expanded Axial Flux Difference Limits
120
1 (-ls, 100) 1 100 0:::
LU
$ Unacceptable 0 80 Unacceptable
- a. Operation
...I Operation
<(
~
0::: Accepta"bl~
LU 60
- I: Operation I-0 LU
!:i: 0::: 40 I (-35, SO) I (+25, SO) I
-0
- 20
0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE(%)
COLR BYRON I Revision 19 Page 13 of 15
CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT l CYCLE 27
2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature 1H Setpoint Parameter Values
2.10.1 The Overtemperature ii T reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature ii T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.
2.10.3 The Overtemperature ii T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.
2.10.4 The nominal Tavg 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 ii T lead/lag time constant T1 shall be equal to 8 sec.
2.10. 7 The measured reactor vessel ii T lead/lag time constant T2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel ii 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 T4 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 (iii) "positive" breakpoint shall be +10% iii.
2.10.13 The f1 (iii) "negative" breakpoint shall be -18% iii.
2.10.14 The f1 (iii) "positive" slope shall be +3.47% /%iii.
2.10.15 The f1 (iii) "negative" slope shall be -2.61 % / % 61.
COLR BYRON 1 Revision 19 Page 14 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 27
2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower 6 T Setpoint Parameter Values
2.11.1 The Overpower 6 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 I °F for increasing Tavg.
2.11. 3 The Overpower 6 T reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0 I °F for decreasing T avg.
2.11.4 The Overpower 6 T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 I °F when T > T".
2.11. 5 The Overpower 6 T reactor trip setpoint Tavg heat up coefficient K6 shall be equal to O / °F when T:,; T".
2.11.6 The nominal T avg at RTP (indicated) T" shall be less than or equal to 588.0 °F.
2.11.7 The measured reactor vessel ts 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 ts T lag time constant,3 shall be less than or equal to 2 sec.
2.11.1 O The measured reactor vessel average temperature lag time constant,5 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 f2 (61) "positive" breakpoint shall be 0 for all 61.
2.11.13 The fa (61) "negative" breakpoint shall be 0 for all 61.
2.11.14 The f2 (61) "positive" slope shall be 0 for all 61.
2.11.15 The fa (61) "negative" slope shall be 0 for all 61.
COLR BYRON 1 Revision 19 Page 15 of 15
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 27
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 (ppm)
2.13.1 a) prior to initial criticality 1726
b) for cycle burnups :o: 0 MWD/MTU 1885 and < 16000 MWD/MTU
c) for cycle burnups :o: 16000 1475 MWD/MTU
2.13.2 a) prior to initial criticality 1775
b) for cycle burnups :o: 0 MWD/MTU 2104 and < 16000 MWD/MTU
c) for cycle burnups :o: 16000 1597 MWD/MTU