BYRON 2023-0050, Cycle 25 Core Operating Limits Report
| ML23292A032 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/19/2023 |
| From: | Welt H Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| BYRON 2023-0050 | |
| Download: ML23292A032 (1) | |
Text
Constellation, October 19, 2023 L TR:
BYRON 2023-0050 File:
5A.101 1 D.101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket No. STN 50-455 Constellation Energy Generation, LLC (CEG)
Byron Station 4450 N. German Church Road Byron, IL 61010-9794 www.constellationenergy.com
Subject:
Byron Station Unit 2 Cycle 25 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"
we are submitting the Unit 2 COLR, Revision 15, for Cycle 25.
Should you have any questions concerning this report, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Harris Welt Site Vice President Byron Generating Station
Attachment:
Byron Station Unit 2 Cycle 25, COLR, Revision 15 HW/DG/hh cc:
Regional Administrator-NRC Region Ill NRC Senior Resident Inspector-Byron Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 25 CONSTELLATION TRACKING ID:
COLR BYRON 2 REVISION 15
COLRBYRON2 Revision 15 Page 1 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 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 LCO 3.1.1 LCO 3.1.3 LCO 3.1.4 LCO 3.1.5 LCO 3.1.6 LCO 3.1.8 LCO 3.2.1 LCO 3.2.2 LCO 3.2.3 LCO 3.2.5 LCO 3.3.1 LCO 3.3.9 LCO 3.4.1 Reactor Core Safety Limits (SLs)
SHUTDOWN MARGIN (SOM)
Moderator Temperature Coefficient (MTC)
Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits PHYSICS TESTS Exceptions - MODE 2 Heat Flux Hot Channel Factor (Fo(Z))
Nuclear Enthalpy Rise Hot Channel Factor (FN"'H)
AXIAL FLUX DIFFERENCE (AFD)
Departure from Nucleate Boiling Ratio (DNBR)
Reactor Trip System (RTS) Instrumentation Boron Dilution Protection System (BOPS)
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 TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.i TRM TLCO 3.1.j TRM TLCO 3.1.k Boration Flow Paths - Operating Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SOM) - MODE 1 and MODE 2 with keff ~ 1.0 Shutdown Margin (SOM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)
COLR BYRON 2 Revision 15 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 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.
Fru ~ion ir1ul f)
- 1-; r Figure 2.1.1: Reactor Core Limits
2.2 2.3 COLRBYRON 2 Revision 15 Page 3 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 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.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).
Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOUARO/HZP-MTC upper limit shall be +2.485 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 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
COLRBYRON2 Revision 15 Page 4 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power (27%, 224) 220 200 180 160 C:
(0%, 162) 3:
~
"Cl 140
..c:
~
V,
- a.
(lJ -
120
~
C:
0
- .;:; 100
'vi 0
c..
C:
'1l 80 r:a "Cl 0
0::
60 40 (0%, 47) 20 (30%, 0) 0 0
10 20 30 40 50 60 70 Rated Thermal Power (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).
(77%, 224) 80 90 (100%, 161) 100
2.6
~
0 LL "C
(I) iu E
0 z N
~
COLRBYRON2 Revision 15 Page 5 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Heat Flux Hot Channel Factor (Fa(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
1.1 1
0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0
pRTP Fq (Z) ::;-Q-xK(Z) for P::; 0.5 0.5 pRTP Fq (Z) ::; _Q_xK(Z) for P > 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 Fa(Z) as a Function of Core Height (0.0, 1.0)
(6.0, 1.0)
(12.0, 1.0)
~
I-+LOCA Limiting Envelope I 0
2 3
4 5
6 7
8 9
10 11 12 BOTTOM Core Height (ft)
COLRBYRON 2 Revision 15 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 UFQ = u,,,,. U, 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
COLRBYRON2 Revision 15 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 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 (feet)
MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2883 1.3799 1.2247 0.20 1.2814 1.3687 1.2180 0.40 1.2821 1.3646 1.2229 0.60 1.2867 1.3644 1.2289 0.80 1.2960 1.3676 1.2412 1.00 1.2955 1.3602 1.2438 1.20 1.2859 1.3450 1.2368 1.40 1.2722 1.3256 1.2261 1.60 1.2579 1.3050 1.2150 1.80 1.2424 1.2828 1.2030 2.00 1.2254 1.2591 1.1897 2.20 1.2074 1.2345 1.1755 2.40 1.1888 1.2108 1.1609 2.60 1.1702 1.1891 1.1462 2.80 1.1548 1.1677 1.1348 3.00 1.1428 1.1479 1.1321 3.20 1.1365 1.1356 1.1328 3.40 1.1365 1.1331 1.1328 3.60 1.1360 1.1317 1.1328 3.80 1.1352 1.1300 1.1339 4.00 1.1340 1.1276 1.1370 4.20 1.1323 1.1250 1.1404 4.40 1.1301 1.1230 1.1431 4.60 1.1274 1.1207 1.1452 4.80 1.1245 1.1182 1.1463 5.00 1.1215 1.1156 1.1468 5.20 1.1187 1.1124 1.1475 5.40 1.1167 1.1090 1.1480 5.60 1.1176 1.1096 1.1474 5.80 1.1210 1.1118 1.1482 6.00 1.1286 1.1152 1.1529 6.20 1.1420 1.1190 1.1638 6.40 1.1540 1.1237 1.1719 6.60 1.1648 1.1279 1.1801 6.80 1.1743 1.1308 1.1871 7.00 1.1821 1.1370 1.1919 7.20 1.1883 1.1471 1.1948 7.40 1.1926 1.1552 1.1957 7.60 1.1951 1.1619 1.1943 7.80 1.1941 1.1656 1.1911 8.00 1.1954 1.1721 1.1849 8.20 1.2020 1.1841 1.1781 8.40 1.2068 1.1949 1.1762 8.60 1.2146 1.2090 1.1739 8,80 1.2232 1.2250 1.1749 9.00 1.2335 1.2434 1.1813 9.20 1.2440 1.2632 1.1955 9.40 1.2484 1.2777 1.2216 9.60 1.2628 1.2896 1.2477 9.80 1.2872 1.3107 1.2718 10.00 1.3137 1.3422 1.2946 10.20 1.3369 1.3751 1.3148 10.40 1.3563 1.4042 1.3316 10.60 1.3728 1.4301 1.3454 10.80 1.3863 1.4530 1.3566 11.00 1.4023 1.4761 1.3681 11.20 1.4056 1.4865 1.3672 11.40 1.3553 1.4566 1.3272 11.60 1.3082 1.4249 1.2851 11.80 1.2999 1.4213 1.2662 12.00 (core top) 1.2796 1.4096 1.2936 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 20000 MWD/MTU 1.2078 1.2000 1.2021 1.2099 1.2244 1.2293 1.2235 1.2138 1.2044 1.1944 1.1833 1.1714 1.1591 1.1468 1.1350 1.1212 1.1143 1.1176 1.1270 1.1386 1.1505 1.1614 1.1715 1.1803 1.1878 1.1937 1.1976 1.1999 1.2007 1.2067 1.2195 1.2339 1.2452 1.2539 1.2599 1.2632 1.2635 1.2609 1.2556 1.2458 1.2380 1.2351 1.2303 1.2285 1.2257 1.2233 1.2251 1.2369 1.2433 1.2535 1.2710 1.2883 1.3028 1.3145 1.3245 1.3326 1.3265 1.2838 1.2387 1.2204 1.1938
COLRBYRON2 Revision 15 Page 8 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 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 (feet)
MWD/MTU MWD/MTU MWD/MTU 0.00 /core bottom) 1.3811 1.4919 1.3146 0.20 1.3726 1.4784 1.3082 0.40 1.3721 1.4725 1.3105 0.60 1.3758 1.4710 1.3174 0.80 1.3843 1.4727 1.3298 1.00 1.3821 1.4630 1.3318 1.20 1.3705 1.4451 1.3237 1.40 1.3544 1.4227 1.3115 1.60 1.3376 1.3989 1.2989 1.80 1.3193 1.3733 1.2851 2.00 1.2991 1.3458 1.2698 2.20 1.2779 1.3172 1.2532 2.40 1.2558 1.2884 1.2362 2.60 1.2330 1.2600 1.2190 2.80 1.2200 1.2305 1.2007 3.00 1.2096 1.2100 1.1906 3.20 1.1990 1.2000 1.1881 3.40 1.1922 1.1922 1.1843 3.60 1.1850 1.1847 1.1801 3.80 1.1765 1.1778 1.1770 4.00 1.1697 1.1727 1.1760 4.20 1.1654 1.1683 1.1754 4.40 1.1612 1.1630 1.1740 4.60 1.1563 1.1571 1.1717 4.80 1.1507 1.1504 1.1683 5.00 1.1444 1.1430 1.1645 5.20 1.1374 1.1347 1.1608 5.40 1.1297 1.1265 1.1565 5.60 1.1210 1.1183 1.1515 5.80 1.1198 1.1149 1.1556 6.00 1.1291 1.1150 1.1678 6.20 1.1420 1.1191 1.1798 6.40 1.1539 1.1237 1.1897 6.60 1.1647 1.1275 1.1993 6.80 1.1740 1.1322 1.2074 7.00 1.1818 1.1393 1.2134 7.20 1.1878 1.1476 1.2172 7.40 1.1920 1.1548 1.2188 7.60 1.1945 1.1615 1.2179 7.80 1.1934 1.1652 1.2150 8.00 1.1947 1.1717 1.2088 8.20 1.2013 1.1837 1.2020 8.40 1.2061 1.1946 1.2001 8.60 1.2139 1.2087 1.1978 8.80 1.2229 1.2249 1.2008 9.00 1.2337 1.2436 1.2128 9.20 1.2441 1.2634 1.2275 9.40 1.2486 1.2779 1.2435 9.60 1.2632 1.2898 1.2552 9.80 1.2876 1.3109 1.2647 10.00 1.3139 1.3424 1.2753 10.20 1.3369 1.3752 1.2872 10.40 1.3560 1.4040 1.2978 10.60 1.3724 1.4297 1.3061 10.80 1.3857 1.4525 1.3110 11.00 1.4014 1.4754 1.3176 11.20 1.4045 1.4856 1.3146 11.40 1.3541 1.4556 1.2707 11.60 1.3068 1.4238 1.2265 11.80 1.2984 1.4200 1.2049 12.00 /core tool 1.2778 1.4080 1.2274 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burn ups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation 20000 MWD/MTU 1.3053 1.2958 1.2970 1.3042 1.3183 1.3219 1.3143 1.3024 1.2905 1.2778 1.2635 1.2481 1.2320 1.2155 1.2002 1.1876 1.1788 1.1752 1.1786 1.1855 1.1936 1.2003 1.2061 1.2104 1.2130 1.2140 1.2129 1.2099 1.2113 1.2192 1.2325 1.2446 1.2540 1.2625 1.2686 1.2717 1.2720 1.2694 1.2639 1.2559 1.2443 1.2318 1.2244 1.2208 1.2258 1.2410 1.2521 1.2587 1.2655 1.2681 1.2709 1.2811 1.2920 1.3016 1.3101 1.3164 1.3088 1.2660 1.2204 1.2013 1.1736
COLRBYRON2 Revision 15 Page 9 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWD/MTU)
Fac(z) 0 1.0200 150 1.0600 371 1.0650 592 1.0750 813 1.0825 1034 1.0825 1697 1.0650 2140 1.0500 2582 1.0375 3245 1.0200 5676 1.0200 6119 1.0275 6561 1.0350 6782 1.0390 7003 1.0415 7224 1.0400 7445 1.0375 7666 1.0300 7887 1.0250 8108 1.0200 Notes:
Linear interpolation is adequate for intermediate cycle burnups.
All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
Table 2.6.2.d Required Operating Space Reduction When Faw(Z) Exceeds Its Limits Required Fow(z)
THERMAL POWER Negative AFD Band Positive AFD Band Maroin Improvement Reduction (% RTP)
Reduction (% AFD)
Reduction (% AFD)
- 51%
~3%
~ 1%
~ 1%
>1%AND:52%
~6%
~2%
~2%
> 2% AND s; 3%
~9%
~3%
~3%
>3%
~ 50%
N/A N/A
2.7 COLRBYRON2 Revision 15 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Nuclear Enthalpy Rise Hot Channel Factor (FNllH) (LCO 3.2.2) where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
F§~P = 1.70 PF6H = 0.3
- 2. 7.2 Uncertainty:
The uncertainty, UFllH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNllH shall be calculated by the following formula:
UFllH = UFllHm where:
UFLJHm = Base FNllH measurement uncertainty = 1.04 when PDMS is inoperable (UFllHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)
2.7.3 PDMS Alarms:
FNllH Warning Setpoint = 2% FNllH Margin FNllH Alarm Setpoint = 0% FNllH 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
0:::
w 0
Cl.
...J
<(
~
0:::
w
- c f-Cl w
~
0::: -
0 COLRBYRON 2 Revision 15 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Figure 2.8.1.a:
100 80 60 40 20
-50
-40 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits
-30
-20
-10 0
10 20 AXIAL FLUX DIFFERENCE(%)
30 40 50
a:
w s 0
C.
...I
<(
2 a:
w
- c I-C w
!=r a: -
0 COLRBYRON2 Revision 15 Page 12 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 Figure 2.8.1.b:
120 100 80 60 40 20 0 '
-50 Unac Ope Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits I
I I
I 1,-15, 100) 1 1 (+10, 100) I J V
\\
eptable/
\\
ration I
.j
\\
Acceptable
\\
Ope1 ation i
U1 ; accept, ble
)
. I perat1c'n 1 (-35, 50) I I (+25, 50) I
-40
-30
-20
-10 0
10 20 30 40 AXIAL FLUX DIFFERENCE(%)
so
COLRBYRON2 Revision 15 Page 13 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature,H Setpoint Parameter Values 2.10.1 The Overtemperature 1'1 T reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature l'1 T reactor trip setpoint Tav9 coefficient K2 shall be equal to 0.0297 I °F.
2.10.3 The Overtemperature l'1 T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.
2.10.4 The nominal Tav9 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 l'1 T lead/lag time constant 11 shall be equal to 8 sec.
2.10.7 The measured reactor vessel l'lT lead/lag time constanh2shall be equal to 3 sec.
2.10.8 The measured reactor vessel l'1 T lag time constant 13 shall be less than or equal to 2 sec.
2.10. 9 The measured reactor vessel average temperature lead/lag time constant 14 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant 1s shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant 1s shall be less than or equal to 2 sec.
2.10.12 The f1 (I'll) "positive" breakpoint shall be +10% I'll.
2.10.13 The f1 (I'll) "negative" breakpoint shall be -18% I'll.
2.10.14 The f1 (I'll) "positive" slope shall be +3.47% / % M 2.10.15 The f1 (I'll) "negative" slope shall be -2.61 % / % I'll.
COLRBYRON2 Revision 15 Page 14 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 25 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower~ 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~ T reactor trip setpoint Tav9 rate/lag coefficient K5 shall be equal to 0.02 I °F for increasing Tavg.
2.11.3 The Overpower~ T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I °F for decreasing Tavg 2.11.4 The Overpower ~ T reactor trip setpoint Tav9 heatup coefficient KB shall be equal to 0.00245 I °F when T > T".
2.11.5 The Overpower~ T reactor trip setpoint Tavg heatup coefficient KB shall be equal to O / °F when T ~ T".
2.11.6 The nominal Tav9 at RTP (indicated) T" shall be less than or equal to 583.5 °F.
2.11. 7 The measured reactor vessel ~ T lead/lag time constant,1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel~ T lead/lag time constant,2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel~ 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,B shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant,1 shall be equal to 10 sec.
2.11.12 The fz (~I) "positive" breakpoint shall be O for all M 2.11.13 The fz (~I) "negative" breakpoint shall be O for all ~I.
2.11.14 The fz (~I) "positive" slope shall be O for all ~I.
2.11.15 The fz (~I) "negative" slope shall be O for all ~I.
COLRBYRON2 Revision 15 Page 15 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 2 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 (Tav9) shall be less than or equal to 588.6 °F.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the applicable value given in the Table below (LCO 3.9.1 ). The reported "prior to initial criticality" value also bounds the end-of-cycle requirements for the previous cycle.
2.13.2 To maintain keff:::; 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 Boron Concentration Section Conditions (ppm) 2.13.1 a) prior to initial criticality 1774 b) for cycle burnups 2 0 MWD/MTU 1924 and < 16000 MWD/MTU c) for cycle burnups 2: 16,000 MWD/MTU 1532 2.13.2 a) prior to initial criticality 1849 b) for cycle burnups 2 0 MWD/MTU and<
2126 16000 MWD/MTU c) for cycle burnups 2 16000 MWD/MTU 1642