BYRON 2018-0096, Cycle 23 Core Operating Limits Report
| ML18260A269 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/17/2018 |
| From: | Kanavos M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2018-0096 | |
| Download: ML18260A269 (17) | |
Text
Byron Generating Station
,.EE:_w ExelonGeneration 445ONorthGerrnanChurchRd www.exeloncorp.com September 17, 2018 LTR: BYRON 201 8-0096 File: 1.10.0101 (YD.101) 2.01 .0300 (5A.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. SIN 50-454
Subject:
Byron Station Unit 1 Cycle 23 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 13, for Cycle 23.
Should you have any questions concerning this report, please contact Mr. Douglas Spitzer, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Mark E. Kanavos Site Vice President Byron Generating Station
Attachment:
Byron Station Unit 1 Cycle 23, COLR, Revision 13 MEKIGC/rm cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Generating Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT I CYCLE 23 EXELON TRACKING ID:
COLR BYRON UNIT I REVISION 13
COLR BYRON 1 Revision 13 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 I .0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit I Cycle 23 has been prepared in accordance with the requirements of Technical Specification 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 (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 (FNtXH)
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 (5DM) MODE I and MODE 2 with keff I .0 TRM TLCO 3.1.i Shutdown Margin (5DM) 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 13 Page 2 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 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 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.
1:}s.ia U- 22.5() psia a) _J t
.2oo psia N 1860 i3s1a L
c;r - \\
- *\
I I I I I I I I I I I I Fr I1Li J nI ti ] F1 Figure 2.1 .1 : Reactor Core Limits
COLR BYRON 1 Revision 13 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.2 SHUTDOWN MARGIN (5DM)
The 5DM limit for MODES , 2, 3, and 4 is:
2.2.1 The 5DM shall be greater than or equal to 1.3% 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 greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 ModeratorTemperature Coefficient(MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOUAROIHZP-MTC upper limit shall be +1 .813 x iO Ak/k/°F.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x iO AkIkI°F.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x iO AkIkI°F.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x I O kIkI°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 13 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 220 200 z::_v (27%, 224) (77%, 224)
I 80
/
I 160 (100%, 161)
(0%, 1 62) j_*/
140 U) 120 100 Q / . ANKDI cc 0 /
60 40 20
/
0 .
0 10 20 30 40 50 60 70 80 90 100 Relative 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 13 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.6 Heat Flux Hot Channel Factor (F2Lfl (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ (Z) xK(Z) for P 0.5 0.5 F RTP FQ(Z) xK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FgTP 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 I
m [.00.924)I 0.9 0.8 0.7 a
U-
- D w
N Cu E
L 0
z LOCA Limiting
- 0.4 Envelope 0.3 0.2 0.1 0
0 I 2 3 4 5 6 7 8 9 101112 BOUOM Core Height (ft) TOP
COLR BYRON I Revision 13 Page 6 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 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 operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. 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 UfQ UquUe where:
Uqu Base FQ measurement uncertainty = I .05 when PDMS is inoperable (Uqu 5 defined by PDMS when OPERABLE.)
Ue Engineering uncertainty factor = I .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 13 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Table 2.6.2.a W(Z) versus Core Heightfor Normal AFD Acceptable Operation Limits in Figure 28.1.a (Top and Bottom 8% Excluded per WCAP-1 0216)
Height 150 6000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWDIMTU 0.00(coreboftom) 11505 1.3370 1.3325 1.2559 0.20 1.1435 1.2986 1.2977 1.2280 0.40 1.1394 1.2821 1.2821 1.2128 0.60 1.1348 1.2661 1.2664 1.1961 0.80 1.1333 1.2266 1.2468 1.1850 1.00 1.1296 1.2041 1.2335 1.1822 1.20 1.1237 1.2131 1.2096 1.1778 1.40 1.1199 1.2066 1.2006 1.1730 1.60 1.1140 1.1891 1.1937 1.1656 1.80 1.1093 1.1736 1.1878 1.1592 2.00 1.1072 1.1591 1.1809 1.1524 2.20 1.1068 1.1421 1.1730 1.1434 2.40 1.1065 1.1276 1.1651 1.1352 2.60 1.1046 1.1111 1.1579 1.1246 2.80 1.1023 1.0971 1.1539 1.1154 3.00 1.0994 1.0908 1.1500 1.1184 3.20 1.0963 1.0897 11441 1.1226 3.40 1.0934 1.0894 1.1381 1.1287 3.60 1.0907 1.0885 1.1312 1.1429 3.80 1.0956 1.0893 1.1263 1.1571 4.00 1.0995 1.0892 1.1314 1.1702 4.20 1.1036 1.0891 1.1352 1.1818 4.40 1.1065 1.0888 1.1382 1.1916 4.60 1.1086 1.0868 1.1388 1.2001 4.80 1.1107 1.0855 1.1384 1.2065 5.00 1.1119 1.0834 1.1396 1.2110 5.20 1.1112 1.0811 1.1408 1.2143 5.40 1.1167 1.0785 1.1421 1.2160 5.60 1.1251 1.0849 1.1497 1.2344 5.80 1.1319 1.0926 1.1650 1.2497 6.00 1.1386 1.1003 1.1776 1.2630 6.20 1.1433 1.1070 1.1882 1.2717 6.40 1.1471 1.1128 1.1969 1.2784 6.60 1.1498 1.1176 1.2026 1.2801 6.80 1.1516 1.1218 1.2064 1.2799 7.00 1.1514 1.1277 1.2072 1.2757 7.20 1.1503 1.1369 1.2051 1.2676 7.40 1.1535 1.1466 1.2010 1.2576 7.60 1.1627 1.1558 1.1931 1.2427 7.80 1.1701 1.1709 1.1832 12279 8.00 1.1770 1.1886 1.1715 12101 8.20 1.1820 1.2037 1.1567 1.1884 8.40 1.1886 1.2189 1.1402 1.1667 8.60 1.1965 1.2314 1.1366 1.1548 8.80 1.2032 1.2380 1.1371 1.1473 9.00 1.2091 1.2436 1.1407 1.1415 9.20 1.2140 1.2554 1.1458 1.1704 9.40 1.2236 1.2575 1.1520 1.2080 9.60 1.2298 1.2603 1.1920 1.2540 9.80 1.2297 1.2603 1.2250 1.2940 10.00 1.2258 1.2588 1.2550 1.3290 10.20 1.2232 1.2596 1.2830 1.3600 10.40 1.2197 1.2634 1.3050 1.3860 10.60 1.2225 1.2669 1.3230 1.4130 10.80 1.2277 1.2754 1.3300 1.4283 11.00 1.2349 1.2857 1.3340 1.4431 11.20 1.2465 1.2914 1.3290 1.4270 11.40 1.2523 1.3088 1.3260 1.4130 11.60 1.2586 1.3162 1.2900 1.3810 11.80 1.2659 1.3239 1.2700 1.3728 12.00(coretop) 1.2767 1.3418 1.2567 1.3785 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BYRON 1 Revision 13 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 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 WCAP-10216)
Height 150 6000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWD/MTU 0.00 (core bottom) 12947 1.4548 1.4510 1.3553 0.20 1.2795 1.4106 1.4110 1.3288 0.40 1.2703 1.3931 1.3930 1.3163 0.60 1.2588 1.3758 1.3750 1.3068 0.80 1.2444 1.3330 1.3520 1.3016 1.00 1.2349 1.3097 1.3360 1.2976 1.20 1.2281 1.3155 1.3090 1.2907 1.40 1.2315 1.3066 1.2940 1.2838 1.60 1.2255 1.2847 1.2760 1.2739 1.80 1.2197 1.2662 1.2610 1.2650 2.00 1.2138 1.2469 12460 1.2551 2.20 1.2042 1.2240 1.2290 1.2412 2.40 1.1944 1.2037 1.2165 1.2293 2.60 1.1801 1.1809 1.2108 1.2135 2.80 1.1682 1.1723 1.2053 1.1996 3.00 1.1603 1.1675 1.1987 1.1837 3.20 1.1524 1.1607 1.1899 1.1812 3.40 1.1475 1.1569 1.1819 1.1860 3.60 1.1380 1.1509 1.1744 1.1900 3.80 1.1331 1.1459 1.1710 1.1932 4.00 1.1330 1.1401 1.1665 1.1944 4.20 1.1346 1.1318 1.1606 1.1942 4.40 1.1352 1.1240 1.1541 1.1932 4.60 1.1347 1.1147 1.1462 1.2001 4.80 1.1343 1.1064 1.1384 1.2065 5.00 1.1327 1.0972 1.1396 1.2110 5.20 1.1293 1.0928 1.1408 1.2143 5.40 1.1257 1.0887 1.1421 1.2160 5.60 1.1251 1.0849 1.1497 1.2344 5.80 1.1319 1.0926 1.1650 1.2497 6.00 1.1386 1.1003 1.1776 1.2630 6.20 1.1433 1.1070 1.1882 1.2717 6.40 1.1471 1.1128 1.1969 1.2784 6.60 1.1498 1.1176 1.2026 1.2801 6.80 1.1516 1.1218 1.2064 1.2799 7.00 1.1514 1.1277 1.2072 1.2757 7.20 1.1503 1.1369 1.2051 1.2676 7.40 1.1535 1.1466 1.2010 1.2576 7.60 1.1627 1.1558 1.1931 1.2427 7.80 1.1701 1.1709 1.1832 1.2279 8.00 1.1770 1.1886 1.1715 1.2101 8.20 1.1820 1.2037 1.1567 1.1884 8.40 1.1886 1.2189 1.1402 1.1667 8.60 1.1965 1.2314 1.1366 1.1548 8.80 1.2032 1.2380 1.1371 1.1473 9.00 1.2091 1.2436 1.1407 1.1415 9.20 1.2140 1.2554 1.1458 1.1704 9.40 1.2236 1.2575 1.1520 1.2080 9.60 1.2298 1.2603 1.1920 1.2540 9.80 1.2297 1.2603 1.2250 1.2940 10.00 1.2258 1.2588 1.2550 1.3290 10.20 1.2232 1.2596 1.2830 1.3600 10.40 1.2197 1.2634 1.3050 1.3860 10.60 1.2225 1.2669 1.3230 1.4130 10.80 1.2277 1.2754 1.3300 1.4283 11.00 1.2349 1.2857 1.3340 1.4431 11.20 1.2465 1.2914 1.3290 1.4270 11.40 1.2523 1.3088 1.3260 1.4130 11.60 1.2586 1.3162 1.2900 1.3810 11.80 1.2659 1.3239 1.2700 1.3728 12.00(coretop) 1.2767 1.3418 1.2567 1.3785 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 13 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(Z) 150 10200 1028 1.0550 1203 1.0560 1730 1.0540 2800 1.0330 3200 1.0250 3500 1.0210 3600 1.0200 12400 1.0200 12700 1.0205 12800 1.0210 12965 1.0220 13141 1.0235 13317 1.0245 13600 1.0264 14050 1.0264 14200 1.0260 14500 1.0240 15200 1.0205 16000 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 1 Revision 13 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN (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)
FRTP AH PFAH 0.3
2.7.2 Uncertainty
The uncertainty, UFH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F1H shall be calculated by the following formula:
UFAH UFHm where:
UFAHm 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 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.
a) Figure 2.8.1.a is the NormalAFD 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.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
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 1 Revision 13 Page 11 ofl5 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.8.1 .a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits with PDMS Inoperable 120
( 10 100) (+10 100) 100 Unacceptabie w
0 / Unacceptable 0 80
-I Ope ratb LU 60 I-40 .. .. .......
1 (-20, 50) .. - . . ..
I (+25, 50) f 20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 1 Revision 13 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 Figure 2.8.J.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits with PDMS Inoperable 120 100 w
C 0 80
-I ii:
60 I-w 40 I
0 20 0
40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 1 Revision 13 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.10 Reactor Trip System (RTS) Instrumentation (LCO 33.1) Overtemperature AT Setpoint Parameter Values 2.1 0. 1 The Overtemperature AT reactor trip setpoint K1 shall be equal to I .325.
2.10.2 The Overtemperature z\T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.
2.1 0.3 The Overtemperature AT 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 z\T lead/lag time constant El shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT 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 r4shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant r5shall be equal to 4 sec.
2.1 0. 1 1 The measured reactor vessel average temperature lag time constant r6 shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) positive breakpoint shall be +10% Al.
2.10.13 The f1 (Al) negative breakpoint shall be -18% Al.
2.10.14 The 11 (Al) positive slope shall be +3.47% /% Al.
2.10.15 The f1(Al) negative slope shall be -2.61% / % Al.
COLR BYRON 1 Revision 13 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.1 1 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The OverpowerAT reactortrip setpoint K4 shall be equalto 1.072.
2.1 1 .2 The Overpower AT reactor trip setpoint avg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing avg 2.11 .3 The Overpower AT reactor trip setpoint avg rate/lag coefficient K5 shall be equal to 0 / °F for decreasing avg 2.1 1 .4 The Overpower AT reactor trip setpoint avg heatup coefficient 1(6 shall be equal to 0.00245 / °F when T > T.
2.1 1 .5 The Overpower AT reactor trip setpoint avg heatup coefficient K6 shall be equal to 0 / °F when T T.
2.11 .6 The nominal avg 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 r shall be equal to 8 sec.
2.1 1 .8 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.1 1 .9 The measured reactor vessel AT lag time constant r3 shall be less than or equal to 2 sec.
- 2. 1 1 I 0
. The measured reactor vessel average temperature lag time constant r6 shall be less than or equal to 2 sec.
- 2. 1 1 I I
. The measured reactor vessel average temperature rate/lag time constant r-, shall be equal to 10 sec.
2.11.12 The f2(AI) positive breakpoint shall be 0 for all Al.
2.11.13 The f2(Al) negative breakpointshall be 0 for all Al.
2.1 1 .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 1 Revision 13 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 23 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 34.1) 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 fullywithdrawn in MODES 3, 4, or5 (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 1679 b) for cycle burnups 0 MWD/MTU 1799 and < I 6000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1438 2.13.2 a) priorto initial criticality 1740 b) for cycle burnups 0 MWD/MTU and < I 6000 MWD/MTU 2009 c) for cycle burnups 16000 1578 MWD/MTU