BYRON 2020-0015, Cycle 24 Core Operating Limits Report
| ML20077J368 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/17/2020 |
| From: | Kanavos M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2020-0015 | |
| Download: ML20077J368 (17) | |
Text
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Byron Generating Station Exeton 0enerat Ion 445ONorthGerrnanChurch Rd wwwexeloncorp.com March 17, 2020 LTR:
BYRON 2020-0015 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 24 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 15, for Cycle 24.
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 1 Cycle 24, COLR, Revision 15 M EK/WG/rm cc:
Regional Administrator NRC Region III NRC Senior Resident Inspector Byron Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT I CYCLE 24 EXELON TRACKING ID:
COLR BYRON UNIT I REVISION 15
I.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit I Cycle 24 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 (5DM)
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 (FNAH)
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 Technical Requirements Manual (TRM) affected by this report are listed below:
Boration Flow Paths Operating Charging Pumps Operating Borated Water Sources Operating Position Indication System Shutdown Shutdown Margin (SDM)
MODE I and MODE 2 with keff 1.0 Shutdown Margin (SDM)
MODE 5 Shutdown and Control Rods Position Indication System Shutdown (Special Test Exception)
COLR BYRON I Revision 15 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 The portions of the TRM TLCO 3.1.b TRM TLCO 3.1.d 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
COLRBYRON I Revision 15 Page 2 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 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:
<I:
Fri1::i:)r1 YJrirvi I I
Figure 2.1.1 : Reactor Core Limits
COLR BYRON 1 Revision 15 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 2.2 SHUTDOWN MARGIN (5DM)
The 5DM limit for MODES I, 2, 3, and 4 is:
2.2.1 The 5DM shall be greaterthan or equal to I.3% Ak/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 5DM limit for MODE 5 is:
2.2.2 SDM shall be greaterthan orequal to 1.3% AkIk(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 +2.097 x 1O Ak/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 1O Ak/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1O z\\k/kI°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1O 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) 228 113
COLR BYRON 1 Revision 15 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 220 (27%, 224)
(77%, 224)
(100%, 161) 200 180 I
160 140 Cl)0.
C)
I-120
100 00 Ix 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 1 Revision 15 Page 5 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 2.6 Heat Flux Hot Channel Factor (FQ(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ(Z) xK(Z) forPO.5 FRTP FQ(Z) 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
LL 0.6 N
Cu 0.5 0z RI 0.4 0.3 0.2 0.1 0
0 1
2 3
4 5
6 7
8 9
101112 BOTTOM Core Height (ft)
COLR BYRON I Revision 15 Page 6 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 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 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWQ(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 UFO = Uqu
- 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 I Revision 15 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 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)
MWDIMTU MWDIMTU MWDIMTU MWDIMTU O.OO(corebottom) 1.2785 1.3690 1.2443 1.1921 0.20 1.2621 1.3361 1.2220 1.1704 0.40 1.2515 1.3235 1.2118 1.1619 0.60 1.2403 1.3093 1.1991 1.1593 0.80 1.2055 1.2593 1.1768 1.1653 1.00 1.1943 1.2425 1.1695 1.1627 1.20 1.1810 1.2232 1.1656 1.1532 1.40 1.1853 1.2056 1.1615 1.1496 1.60 1.1745 1.1857 1.1556 1.1418 1.80 1.1690 1.1750 1.1515 1.1350 2.00 1.1640 1.1690 1.1464 1.1278 2.20 1.1570 1.1610 1.1390 1.1182 2.40 1.1510 1.1530 1.1331 1.1093 2.60 1.1440 1.1440 1.1257 1.0975 2.80 1.1370 1.1370 1.1224 1.0898 3.00 1.1311 1.1330 1.1202 1.0930 3.20 1.1298 1.1280 1.1171 1.1021 3.40 1.1285 1.1225 1.1139 1.1112 3.60 1.1261 1.1207 1.1109 1.1194 3.80 1.1236 1.1188 1.1149 1.1316 4.00 1.1200 1.1169 1.1232 1.1454 4.20 1.1159 1.1137 1.1319 1.1596 4.40 1.1144 1.1104 1.1389 1.1702 4.60 1.1120 1.1060 1.1448 1.1812 4.80 1.1096 1.1020 1.1491 1.1895 5.00 1.1080 1.0970 1.1532 1.1957 5.20 1.1046 1.0933 1.1540 1.2012 5.40 1.1020 1.0915 1.1556 1.2056 5.60 1.0978 1.0983 1.1643 1.2243 5.80 1.1056 1.1061 1.1799 1.2418 6.00 1.1124 1.1139 1.1925 1.2555 6.20 1.1173 1.1207 1.2031 1.2680 6.40 1.1222 1.1256 1.2109 1.2757 6.60 1.1290 1.1305 1.2156 1.2784 6.80 1.1377 1.1338 1.2184 1.2792 7.00 1.1436 1.1380 1.2182 1.2780 7.20 1.1484 1.1433 1.2151 1.2708 7.40 1.1550 1.1480 1.2091 1.2628 7.60 1.1618 1.1508 1.2001 1.2488 7.80 1.1681 1.1582 1.1903 1.2368 8.00 1.1734 1.1646 1.1842 1.2220 8.20 1.1767 1.1690 1.1733 1.2022 8.40 1.1796 1.1684 1.1654 1.1942 8.60 1.1871 1.1730 1.1601 1.1861 8.80 1.1934 1.1786 1.1631 1.1788 9.00 1.1991 1.1870 1.1653 1.1829 9.20 1.2025 1.1963 1.1661 1.1860 9.40 1.2069 1.2121 1.1738 1.2179 9.60 1.2256 1.2327 1.2020 1.2635 9.80 1.2439 1.2525 1.2360 1.3051 10.00 1.2610 1.2707 1.2660 1.3447 10.20 1.2680 1.2871 1.2940 1.3794 10.40 1.2620 1.3029 1.3120 1.4121 10.60 1.2287 1.3165 1.3270 1.4338 10.80 1.2267 1.3312 1.3320 1.4556 11.00 1.2545 1.3437 1.3310 1.4654 11.20 1.2827 1.3555 1.3390 1.4583 11.40 1.2873 1.3516 1.3235 1.4582 11.60 1.2895 1.3568 1.2985 1.4282 11.80 1.2943 1.3637 1.2864 1.4142 12.00(coretop) 1.3052 1.3794 1.2781 1.4049 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 1 Revision 15 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 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 MWDIMTU MWDIMTU MWDIMTU O.OO(corebottom) 1.4130 1.5187 1.3922 1.3093 0.20 1.3930 1.4792 1.3647 1.2921 0.40 1.3800 1.4639 1.3523 1.2885 0.60 1.3660 1.4470 1.3362 1.2840 0.80 1.3260 1.3892 1.3094 1.2885 1.00 1.3120 1.3691 1.2953 1.2840 1.20 1.2950 1.3455 1.2695 1.2710 1.40 1.2990 1.3250 1.2572 1.2656 1.60 1.2850 1.3006 1.2411 1.2553 1.80 1.2740 1.2795 1.2279 1.2461 2.00 1.2630 1.2609 1.2206 1.2367 2.20 1.2460 1.2407 1.2120 1.2237 2.40 1.2320 1.2212 1.2042 1.2116 2.60 1.2140 1.2052 1.1941 1.1958 2.80 1.1990 1.2016 1.1883 1.1818 3.00 1.1834 1.1973 1.1820 1.1668 3.20 1.1753 1.1912 1.1728 1.1500 3.40 1.1689 1.1859 1.1646 1.1536 3.60 1.1613 1.1778 1.1574 1.1583 3.80 1.1538 1.1707 1.1569 1.1617 4.00 1.1462 1.1634 1.1556 1.1646 4.20 1.1369 1.1535 1.1528 1.1663 4.40 1.1288 1.1444 1.1492 1.1718 4.60 1.1177 1.1335 1.1448 1.1828 4.80 1.1096 1.1234 1.1491 1.1911 5.00 1.1080 1.1133 1.1532 1.1972 5.20 1.1046 1.1007 1.1540 1.2018 5.40 1.1020 1.0915 1.1556 1.2056 5.60 1.0978 1.0983 1.1643 1.2243 5.80 1.1056 1.1061 1.1799 1.2418 6.00 1.1124 1.1139 1.1925 1.2555 6.20 1.1173 1.1207 1.2031 1.2680 6.40 1.1222 1.1256 1.2109 1.2757 6.60 1.1290 1.1305 1.2156 1.2784 6.80 1.1377 1.1338 1.2184 1.2792 7.00 1.1436 1.1380 1.2182 1.2780 7.20 1.1484 1.1433 1.2151 1.2708 7.40 1.1550 1.1480 1.2091 1.2628 7.60 1.1618 1.1508 1.2001 1.2488 7.80 1.1681 1.1582 1.1903 1.2368 8.00 1.1734 1.1646 1.1842 1.2220 8.20 1.1767 1.1690 1.1733 1.2022 8.40 1.1796 1.1684 1.1654 1.1942 8.60 1.1871 1.1730 1.1601 1.1861 8.80 1.1934 1.1786 1.1631 1.1788 9.00 1.1991 1.1870 1.1653 1.1829 9.20 1.2025 1.1963 1.1661 1.1860 9.40 1.2069 1.2121 1.1738 1.2179 9.60 1.2256 1.2327 1.2020 1.2635 9.80 1.2439 1.2525 1.2360 1.3051 10.00 1.2610 1.2707 1.2660 1.3447 10.20 1.2680 1.2871 1.2940 1.3794 10.40 1.2620 1.3029 1.3120 1.4121 10.60 1.2287 1.3165 1.3270 1.4338 10.80 1.2267 1.3312 1.3320 1.4556 11.00 1.2545 1.3437 1.3310 1.4654 11.20 1.2827 1.3555 1.3390 1.4583 11.40 1.2873 1.3516 1.3235 1.4582 11.60 1.2895 1.3568 1.2985 1.4282 11.80 1.2943 1.3637 1.2864 1.4142 12.00(coretop) 1.3052 1.3794 1.2781 1.4049 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 15 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDIMTU)
FCQ(Z) 0 1.0200 150 1.0500 500 1.0620 750 1.0640 1000 1.0630 1500 1.0500 2000 1.0350 2500 1.0210 3000 1.0200 9900 1.0200 10250 1.0242 10680 1.0236 12000 1.0255 14000 1.0222 15000 1.0200 17500 1.0200 17750 1.0211 18000 1.0210 18500 1.0205 19000 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 I Revision 15 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH (LCO 3.2.2) 2.7.1 FNAH F![1.O + PFAH(1.O
- P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
F= 1.70 PFAH = 0.3
2.7.2 Uncertainty
The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FH shall be calculated by the following formula:
UFAH = 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:
FNAH Warning Setpoint = 2% FNAH Margin FNAH 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
LU 0a-
-I LU I-.0 LU 0
0 COLR BYRON I Revision 15 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 Figure 2.8.1.a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 120 100 80 60 40 20 0
(-10,100)
(+10,100)
Unacceptab e Uhacceptable
/
AcceptaHe 1
(20, 50)
% I (+25, 50)
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 1 Revision I 5 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 Figure 2.8.1.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 100 w
0 Q-80
-I 60 I-uJ I-<
40 4-0 20 0
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON Revision I 5 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 2.10 Reactor Trir 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 reactortnp setpoint pressure coefficientK3 shall be equal to 0.001 35 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 AT lead/lag time constant ti shall be equal to 8 sec.
2.1 0.7 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant t3shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant T4 be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant t5shall 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% 1% Al.
COLR BYRON I Revision 15 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 24 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1)
- Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to I.072.
2.11.2 The Overpower T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing Tavg.
2.11.3 The Overpower \\T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / °F for decreasing Tavg.
2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / °F when T > T.
2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 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 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 t6shall 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 I Revision 15 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 24 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 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 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 31.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 1734 b) for cycle burnups 0 MWD/MTU 1850 and < 16000 MWD/MTU c) for cycle burnups 16000 1447 MWD/MTU 2.13.2 a) prior to initial criticality 1837 b) for cycle burnups 0 MWD/MTU 2081 and < 16000 MWD/MTU c) for cycle burnups 16000 1583 MWD/MTU