BYRON 2020-0067, Cycle 22 Core Operating Limits Report
| ML20294A161 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/20/2020 |
| From: | Kanavos M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2020-0067 | |
| Download: ML20294A161 (17) | |
Text
_w Byron Generating Station A
Exeton G enera t i on 4450 North German Church Rd Byron, IL 61O1O9794 www.exeloncorp.com October 20, 2020 LTR: BYRON 2020-0067 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 2 Renewed Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 Cycle 22 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 12, for Cycle 23.
Should you have any questions concerning this report, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Mark E. Kanavos Site Vice President Byron Generating Station
Attachment:
Byron Station Unit 2 Cycle 23, COLR, Revision 12 M EKI\NG/rm cc: Regional Administrator NRC Region III NRC Senior Resident Inspector Byron Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 23 EXELON TRACKING ID:
COLR BYRON 2 REVISION 12
COLR BYRON 2 Revision 12 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 23 has been prepared in accordance with the requirements of Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) 56.5 (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 (Fr%LXH)
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 (SDM) MODE I and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) 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 12 Page 2 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 (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.
LL P
0.2 Fr oc:ion c 1criiria Pover Figure 2.1.1: Reactor Core Limits
COLR BYRON 2 Revision 12 Page 3 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 2.2 SHUTDOWN MARGIN (5DM)
The 5DM limit for MODES 1 2, 3, and 4 is:
2.2. 1 The 5DM shall be greater than or equal to I .3% Ak/k (LCOs 3. 1 I 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 SDM shall be greater than or equal to I .3% Ak/k (LCO 3.1 .1 LCO 3.3.9; TRM TLCOs 3.1 and 3.1.j).
2.3 ModeratorTemperature 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 +1.884 x 1O z\kIkI°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 1O z\kIkI°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1O Ak/k/°F.
2.3.4 The EOL/ARO/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) 231 115
COLR BYRON 2 Revision 12 Page 4 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 220 200 180 160 (100%, 161)
.1 140 U)
Co C
0 100 0
0 C
80 0
60 40 20 0
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: (161170) *
(P-100) + 161 (for 30 P 100)
Where P is defined as the core power (in percent).
COLR BYRON 2 Revision 12 Page 5 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 2.6 Heat Flux Hot Channel Factor (FQ(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FRl FQ(Z) 9---xK(Z) forPO.5 FR 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 0.9 0.8 RI 0.7 a
U w 0.6 N
0.4 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 1011 12 BOTTOM Core Height (ft) TOP
COLR BYRON 2 Revision 12 Page 6 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 2.8.1 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 FCQ(Z) penalty factors that are greater than 2% per the allowable surveillance frequency. These values shall be used to increase the FAbo(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 UJQ = Uq, . U where:
Uqu = Base FQ 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:
FQ(Z) Warning Setpoint = 2% FQ(Z) Margin FQ(Z) Alarm Setpoint = 0% FQ(Z) Margin
COLR BYRON 2 Revision 12 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 Table 2.62.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 3.21.2 Bases)
Height 150 6000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWDIMTU 0.00 (core bottom) 1.2231 1.3525 1.2371 1.2402 0.20 1.2062 1.3194 1.2149 1.2152 0.40 1.2005 1.3043 1.2071 1.2054 0.60 1.1786 1.2587 1.2020 1.1960 0.80 1.1633 1.2366 1.2029 1.1738 1.00 1.1536 1.2207 1.1988 1.1595 1.20 1.1498 1.2041 1.1929 1.1584 1.40 1.1465 1.2001 1.1878 1.1505 1.60 1.1423 1.1882 1.1801 1.1438 1.80 1.1380 1.1736 1.1740 1.1378 2.00 1.1330 1.1587 1.1669 1.1308 2.20 1.1267 1.1423 1.1575 1.1210 2.40 1.1206 1.1284 1.1488 1.1152 2.60 1.1163 1.1263 1.1366 1.1104 2.80 1.1172 1.1236 1.1268 1.1056 3.00 1.1171 1.1209 1.1218 1.1007 3.20 1.1170 1.1185 1.1164 1.1051 3.40 1.1160 1.1158 1.1151 1.1148 3.60 1.1139 1.1125 1.1139 1.1244 3.80 1.1126 1.1119 1.1162 1.1343 4.00 1.1132 1.1114 1.1202 1.1467 4.20 1.1157 1.1103 1.1271 1.1602 4.40 1.1163 1.1081 1.1353 1.1738 4.60 1.1179 1.1061 1.1416 1.1834 4.80 1.1175 1.1027 1.1467 1.1929 5.00 1.1172 1.0992 1.1505 1.2005 5.20 1.1149 1.0955 1.1524 1.2050 5.40 1.1126 1.0915 1.1547 1.2076 5.60 1.1096 1.0879 1.1543 1.2264 5.80 1.1156 1.0933 1.1579 1.2430 6.00 1.1225 1.1019 1.1716 1.2566 6.20 1.1274 1.1085 1.1852 1.2683 6.40 1.1323 1.1151 1.1949 1.2759 6.60 1.1353 1.1198 1.2015 1.2797 6.80 1.1373 1.1251 1.2043 1.2824 7.00 1.1400 1.1303 1.2052 1.2812 7.20 1.1469 1.1363 1.2031 1.2751 7.40 1.1552 1.1421 1.1991 1.2670 7.60 1.1621 1.1464 1.1921 1.2549 7.80 1.1680 1.1497 1.1881 1.2419 8.00 1.1709 1.1514 1.1830 1.2280 8.20 1.1738 1.1530 1.1731 1.2101 8.40 1.1814 1.1591 1.1662 1.2036 8.60 1.1898 1.1711 1.1573 1.1979 8.80 1.1977 1.1869 1.1555 1.1931 9.00 1.2040 1.2053 1.1606 1.1870 9.20 1.2154 1.2222 1.1652 1.1857 9.40 1.2306 1.2335 1.1723 1.2167 9.60 1.2454 1.2484 1.1780 1.2583 9.80 1.2594 1.2624 1.2100 1.2979 10.00 1.2730 1.2728 1.2390 1.3355 10.20 1.2848 1.2816 1.2650 1.3661 10.40 1.2968 1.2898 1.2810 1.3928 10.60 1.2903 1.3001 1.2910 1.4126 10.80 1.2757 1.3052 1.2970 1.4284 11.00 1.2723 1.3125 1.2990 1.4382 11.20 1.2980 1.3144 1.3020 1.4381 11.40 1.2848 1.3300 1.2924 1.4379 11.60 1.3004 1.3379 1.2723 1.4108 11.80 1.3025 1.3413 1.2602 1.3988 12.00(coretop) 1.3083 1.3576 1.2509 1.3915 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 2 Revision 12 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits in Figure 2.8.1 .b iTop and Bottom 8% Excluded ner Rvron SR 321 2 Rases Height 150 6000 14000 20000 (feet) MWD!MTU MWDIMTU MWDIMTU MWDIMTU O.OO(corebottom) 1.3892 1.4948 1.3866 1.3265 0.20 1.3676 1.4563 1.3586 1.3045 0.40 1.3598 1.4385 1.3451 1.2950 0.60 1.3333 1.3851 1.3316 1.2871 0.80 1.3128 1.3603 1.3309 1.2876 1.00 1.2991 1.3416 1.3156 1.2833 1.20 1.2816 1.3219 1.2942 1.2757 1.40 1.2669 1.3180 1.2836 1.2695 1.60 1.2503 1.3023 1.2702 1.2602 1.80 1.2366 1.2835 1.2586 1.2518 2.00 1.2259 1.2638 1.2460 1.2424 2.20 1.2113 1.2438 1.2297 1.2293 2.40 1.1976 1.2269 1.2177 1.2179 2.60 1.1850 1.2059 1.2048 1.2028 2.80 1.1762 1.1921 1.1977 1.1886 3.00 1.1669 1.1876 1.1914 1.1745 3.20 1.1607 1.1805 1.1829 1.1605 3.40 1.1555 1.1750 1.1753 1.1604 3.60 1.1493 1.1694 1.1658 1.1648 3.80 1.1431 1.1643 1.1570 1.1682 4.00 1.1368 1.1578 1.1509 1.1713 4.20 1.1287 1.1497 1.1476 1.1733 4.40 1.1215 1.1411 1.1437 1.1799 4.60 1.1217 1.1330 1.1416 1.1883 4.80 1.1202 1.1224 1.1467 1.1963 5.00 1.1186 1.1129 1.1505 1.2021 5.20 1.1155 1.1028 1.1524 1.2052 5.40 1.1128 1.0915 1.1547 1.2076 5.60 1.1096 1.0879 1.1543 1.2264 5.80 1.1156 1.0933 1.1579 1.2430 6.00 1.1225 1.1019 1.1716 1.2566 6.20 1.1274 1.1085 1.1852 1.2683 6.40 1.1323 1.1151 1.1949 1.2759 6.60 1.1353 1.1198 1.2015 1.2797 6.80 1.1373 1.1251 1.2043 1.2824 7.00 1.1400 1.1303 1.2052 1.2812 7.20 1.1469 1.1363 1.2031 1.2751 7.40 1.1552 1.1421 1.1991 1.2670 7.60 1.1621 1.1464 1.1921 1.2549 7.80 1.1680 1.1497 1.1881 1.2419 8.00 1.1709 1.1514 1.1830 1.2280 8.20 1.1738 1.1530 1.1731 1.2101 8.40 1.1814 1.1591 1.1662 1.2036 8.60 1.1898 1.1711 1.1573 1.1979 8.80 1.1977 1.1869 1.1555 1.1931 9.00 1.2040 1.2053 1.1606 1.1870 9.20 1.2154 1.2222 1.1652 1.1857 9.40 1.2306 1.2335 1.1723 1.2167 9.60 1.2454 1.2484 1.1780 1.2583 9.80 1.2594 1.2624 1.2100 1.2979 10.00 1.2730 1.2728 1.2390 1.3355 10.20 1.2848 1.2816 1.2650 1.3661 10.40 1.2968 1.2898 1.2810 1.3928 10.60 1.2903 1.3001 1.2910 1.4126 10.80 1.2757 1.3052 1.2970 1.4284 11.00 1.2723 1.3125 1.2990 1.4382 11.20 1.2980 1.3144 1.3020 1.4381 11.40 1.2848 1.3300 1.2924 1.4379 11.60 1.3004 1.3379 1.2723 1.4108 11.80 1.3025 1.3413 1.2602 1.3988 12.00(coretop) 1.3083 1.3576 1.2509 1.3915 Note: W(Z) values at 20000 MWU/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BYRON 2 Revision 12 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 Table 2.6.2.c Penalty Factors in Excess of 2%
Cycle Burnup Penalty Factor (MWDIMTU) FCQ(Z) 0 1.0200 150 1.0650 371 1.0735 592 1.0750 813 1.0740 1034 1.0700 1696 1.0500 2579 1.0225 3242 1.0200 10530 1.0200 10971 1.0270 11413 1.0320 13183 1.0335 13624 1.0315 14508 1.0270 16051 1.0232 18259 1.0310 18484 1.0307 18926 1.0290 19809 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 12 Page 1 0 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7. 1 FNAH F[1 .0 + PFAH(1 .0 P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
= 1.70 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:
UFH = UFAHm where:
UFziHm Base FNAH measurement uncertainty = I .04 when PDMS is inoperable (UFAHm 5 defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
FH Warning Setpoint = 2% FNAH Margin FH 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 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 2 Revision 12 Page 11 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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
-J 60 I
LIJ I
0 40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 2 Revision 12 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 LU 60 I-40 20 0
40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 2 Revision 12 Page 1 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactortrip setpoint Ki shall be equalto 1.325.
2.10.2 The Overtemperature AT reactortrip setpointTavgcoefficient K2 shall be equal to 0.0297 I °F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.
2.10.4 The nominal Tavgat 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 ti shall be equal to 8 sec.
- 2. 1 0.7 The measured reactor vessel \T lead/lag time constant t2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant -r 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 t5 be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant t6 be less than or equal to 2 sec.
2.10.12 The fi (Al) positive breakpoint shall be +10% Al.
2.10.13 The fi (Al) negative breakpoint shall be -18% Al.
2.10.14 The fi (Al) positive slope shall be +3.47% / % Al.
2.10.15 The fi (Al) negative slope shall be -2.61% /% Al.
COLR BYRON 2 Revision 12 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 23 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overpower AT Setpoint Parameter Values 2.1 1 .1 The Overpower AT reactor trip setpoint K4 shall be equal to I .072.
2.1 1 .2 The Overpower \T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 I °F for increasing Tavg.
2.11 .3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I °F for decreasing Tavg.
- 2. 1 1 .4 The Overpower \T reactor trip setpoint Tavg heatup coefficient KG shall be equal to 0.00245/°FwhenT>T.
2.1 1 .5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 I °F when T T.
2.11 .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 ti shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant t2 be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant t3 be less than or equal to 2 sec.
2.11 .10 The measured reactor vessel average temperature lag time constant t6 be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant t7 be equal to 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 2 Revision 12 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 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 values given in the Table below.
COLR Boron Concentration Section Conditions (ppm) 2.13.1 a) prior to initial criticality 1726 b) for cycle burnups 0 MWD/MTU 1870 and < 16000 MWD/MTU c) for cycle burnups 16,000 MWD/MTU 1493 2.13.2 a) prior to initial criticality 1818 b) for cycle burnups 0 MWD/MTU and < 2110 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1636