BYRON 2017-0098, Cycle 21 Core Operating Limits Report
| ML17282A002 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/09/2017 |
| From: | Chalmers T Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2017-0098 | |
| Download: ML17282A002 (17) | |
Text
- _:-
Byron Generating Station E- Exeton 0 enera t I on 445ONorthGerrnanChurch Rd www.exeloncorp.com October 9, 2017 LTR: BYRON 201 7-0098 File: 2.01.0300 (5A.101) 1 .10.0101 (1D.101)
United States Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket No. SIN 50-455
Subject:
Byron Station Unit 2 Cycle 21 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 9, for Cycle 21.
Should you have any questions concerning this report, please contact Mr. Douglas Spitzer, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Thomas D. btmrs Acting SitVice President Byron Generating Station
Attachment:
Byron Station Unit 2 Cycle 21 COLR, Revision 9 TDC/GC/rm cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 21 EXELON TRACKING ID:
COLR BYRON 2 REVISION 9
COLR BYRON 2 Revision 9 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 21 has been prepared in accordance with the requirements of Technical Specification Safety Limits and Limiting Conditions for Operation (LCO5) 5.6.5 (ITS).
The Technical Specification Safety Limits and Limiting Conditions for Operation (LCO5) 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 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)
COLR BYRON 2 Revision 9 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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 ReactorCore Safety Limits(SLs) (5L2.1.1) 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 I.
2.rI psia U- 22Opsia Th L) 2000 psia N
1860 )Sia N
620 -
C) a)
- I I 58 0.1 0.6 I .2 FtIL Llr U [lu trial I Figure 2.1 .1 : Reactor Core Limits
COLRBYRON2 Revision 9 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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, 31.6, 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% z\klk (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 +2.155 x iO AkIkI°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x i04 AkIkI°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i04 Ak/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x iO Ak!kI°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 2 Revision 9 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure 25.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power (27%, 224) (77%, 224) 220 200 180 160 (100%, 161)
(U L.
140 0
4 120 0
C 0
100 0
C 80 0
60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BYRON 2 Revision 9 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.6 Heat Flux Hot Channel Factor (FQf)j (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F FQ (Z) 9-xK(Z) for P 0.5 F
FQ(Z) 2---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 (0.0 1.0) (6.0 1.0) 0.9 1
z: 0.924) 0.8 iz:i 0.7 a
U-N 0.6 E
I-0 0.5 z
N LOCA Limiting 0.4 Envelope 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
COLR BYRON 2 Revision 9 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 26.2 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 F0(Z) shall be calculated by the following formula UFQ cju
- where:
Uqu Base FQ measurement uncertainty = I .05 when PDMS is inoperable (Uqu 15 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 2 Revision 9 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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 WCAP-10216)
Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2208 1.3471 1.2396 1.22 18 0.20 1.2141 1.3171 1.2179 1.1946 0.40 1.2097 1.3005 1.2150 1.1830 0.60 1.2000 1.2868 1.2044 1.1817 0.80 1.1670 1.2581 1.1882 1.1804 1.00 1.1582 1.2253 1.1766 1.1775 1.20 1.1665 1.2300 1.1600 1.1729 1.40 1.1627 1.2178 1.1494 1.1666 1.60 1.1529 1.2072 1.1446 1.1574 1.80 1.1430 1.1904 1.1425 1.1490 2.00 1.1388 1.1759 1.1385 1.1399 2.20 1.1339 1.1608 1.1358 1.1278 2.40 1.1295 1.1465 1.1311 1.1160 2.60 1.1281 1.1318 1.1247 1.1074 2.80 1.1267 1.1185 1.1183 1.1114 3.00 1.1249 1.1167 1.1117 1.1180 3.20 1.1220 1.1151 1.1060 1.1238 3.40 1.1189 1.1127 1.1120 1.1286 3.60 1.1148 1.1094 1.1183 1.1428 3.80 1.1123 1.1073 1.1247 1.1579 4.00 1.1146 1.1077 1.1289 1.1720 4.20 1.1169 1.1068 1.1329 1.1849 4.40 1.1182 1.1059 1.1360 1.1957 4.60 1.1183 1.1038 1.1376 1.2044 4.80 1.1185 1.1018 1.1388 1.2118 5.00 1.1181 1.0994 1.1411 1.2163 5.20 1.1164 1.0961 1.1426 1.2194 5.40 1.1146 1.0920 1.1442 1.2218 5.60 1.1107 1.0895 1.1511 1.2384 5.80 1,1103 1.0919 1.1657 1.2550 6.00 1.1163 1.1003 1.1798 1.2686 6.20 1.1217 1.1075 1.1907 1.2782 6.40 1.1267 1.1150 1.1995 1.2849 6.60 1.1307 1.1205 1.2053 1.2866 6.80 1.1346 1.1251 1.2092 1.2874 7.00 1.1364 1.1302 1.2113 1.2842 7.20 1.1373 1.1353 1.2096 1.2762 7.40 1.1398 1.1413 1.2067 1.2665 7.60 1.1436 1.1463 1.2016 1.2528 7.80 1.1464 1.1508 1.1975 1.2371 8.00 1.1512 1.1568 1.1925 1.2193 8.20 1.1545 1.1630 1.1846 1.1976 8.40 1.1586 1.1659 1.1804 1.1845 8.60 1.1616 1.1756 1.1789 1.1810 8.80 1.1667 1.1838 1.1753 1.1759 9.00 1.1738 1.1904 1.1701 1.1695 9.20 1.1799 1.2023 1.1729 1.1677 9.40 1.1912 1.2130 1.1765 1.2010 9.60 1.2059 1.2286 1.1867 1.2453 9.80 1.2119 1.2462 1.2155 1.2835 10.00 1.2123 1.2595 1.2402 1.3172 10.20 1.2154 1.2712 1.2669 1.3492 10.40 1.2185 1.2823 1.2806 1.3796 10.60 1.2183 1.2956 1.2954 1.4120 10.80 1.2226 1.3067 1.3087 1.4265 11.00 1.2359 1.3168 1.3189 1.4363 11.20 1.2474 1.3221 1.3195 1.4312 11.40 1.2571 1.3390 1.3192 1.4171 11.60 1.2549 1.3403 1.2933 1.4001 11.80 1.2561 1.3435 1.2812 1.3860 12.00 (core top) 1.2672 1.3578 1.2729 1.3738 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
COLRBYRON2 Revision 9 Page 8 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 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-102l6) height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (corebottom) 1.3857 1.4842 1.3979 1.3238 0.20 1.3757 1.4485 1.3709 1.3178 0.40 1.3698 1.4276 1.3663 1.3154 0.60 1.3574 1.4136 1.3534 1.3138 0.80 1.3121 1.3805 1.3323 1.3099 1.00 1.2982 1.3443 1.3178 1.3050 1.20 1.3119 1.3467 1.2975 1.2976 1.40 1.3061 1.3312 1.2841 1.2893 1.60 1.2925 1.3174 1.2662 1.2765 1.80 1.2799 1.2954 1.2527 1.2655 2.00 1.2677 1.2758 1.2379 1.2539 2.20 1.2516 1.2542 1.2228 1.2378 2.40 1.2352 1.2351 1.2161 1.2223 2.60 1.2170 1.2162 1.2073 1.2043 2.80 1.2008 1.1992 1.1988 1.1902 3.00 1.1850 1.1860 1.1904 1.1779 3.20 1.1763 1.1795 1.1817 1.1691 3.40 1.1720 1.1738 1.1738 1.1704 3.60 1.1662 1.1686 1.1636 1.1739 3.80 1.1608 . 1.1632 1.1571 1.1763 4.00 1.1549 1.1572 1.1535 1.1786 4.20 1.1472 1.1486 1.1480 1.1849 4.40 1.1398 1.1411 1.1427 1.1957 4.60 1.1305 1.1315 1.1376 1.2044 4.80 1.1222 1.1224 1.1388 1.2118 5.00 1.1181 1.1124 1.1411 1.2163 5.20 1.1164 1.1013 1.1426 1.2194 5.40 1.1146 1.0920 1.1442 1.2218 5.60 1.1107 1.0895 1.1511 1.2384 5.80 1.1103 1.0919 1.1657 1.2550 6.00 1.1163 1.1003 1.1798 1.2686 6.20 1.1217 1.1075 1.1907 1.2782 6.40 1.1267 1.1150 1.1995 1.2849 6.60 1.1307 1.1205 1.2053 1.2866 6.80 1.1346 1.1251 1.2092 1.2874 7.00 1.1364 1.1302 1.2113 1.2842 7.20 1.1373 1.1353 1.2096 1.2762 7.40 1.1398 1.1413 1.2067 1.2665 7.60 1.1436 1.1463 1.2016 1.2528 7.80 1.1464 1.1508 1.1975 1.2371 8.00 1.1512 1.1568 1.1925 1.2193 8.20 1.1545 1.1630 1.1846 1.1976 8.40 1.1586 1.1659 1.1804 1.1845 8.60 1.1616 1.1756 1.1789 1.1810 8.80 1.1667 1.1838 1.1753 1.1759 9.00 1.1738 1.1904 1.1701 1.1695 9.20 1.1799 1.2023 1.1729 1.1677 9.40 1.1912 1.2130 1.1765 1.2010 9.60 1.2059 1.2286 1.1867 1.2453 9.80 1.2119 1.2462 1.2155 1.2835 10.00 1.2123 1.2595 1.2402 1.3172 10.20 1.2154 1.2712 1.2669 1.3492 10.40 1.2185 1.2823 1.2806 1.3796 10.60 1.2183 1.2956 1.2954 1.4120 10.80 1.2226 1.3067 1.3087 1.4265 11 00 1.2359 1.3168 1.3189 1.4363 11.20 1.2474 1.3221 1.3195 1.4312 11.40 1.2571 1.3390 1.3192 1.4171 11.60 1.2549 1.3403 1.2933 1.4001 11.80 1.2561 1.3435 1.2812 1.3860 12.00 (core top) 1.2672 1.3578 1.2729 1.3738 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 2 Revision 9 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penal,y Factor (MWDIMTU) F (Z) 0 1.0205 677 1.0510
$53 1056$
1029 1.0600 13$0 1052$
2259 1.0250 2610 1.0200 9999 1.0200 13330 1.0200 14033 1.0246 14911 1.0235 15790 1.0240 16669 1.0252 17723 1.0264 1$074 1.0260 1$602 1.0270 1$777 1.0262 19129 1.0242 194$0 1.0220 19656 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.
COLRBYRON2 Revision 9 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F1 (LCO 3.2.2) 2.7.1 FNAH F[1.0 + PFAH(l.O P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
FRTP AH 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:
UFAH UFAHm where:
UFjHm 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 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.
2.8.2 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 2 Revision 9 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure 2.8.J.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 w
0 0
-J 80 Unacceptab e Ope rat io n
/ \ Unacceptable
- EQE w 60 I-1----
40 -
1 (20 50) f j(+25 50)[
20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 2 Revision 9 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 Figure 2.8.1.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits with PDMS Inoperable 120 100 LU 0
- a. 80
-I 60 I-LU 40 I
0 20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 2 Revision 9 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 210.1 The Overtemperature AT reactortrip setpoint K1 shall be equalto 1.325.
2.1 0.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/°F.
2.1 0.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 / psi.
2.10.4 The nominal Tavg 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 AT lead/lag time constant t1 shall be equal to 8 sec.
2.1 0.7 The measured reactor vessel AT lead/lag time constant E2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant r3shall be less than or equal to 2 sec.
2.1 0.9 The measured reactor vessel average temperature lead/lag time constant E4 shall be equal to 33 sec.
2.1 0.1 0 The measured reactor vessel average temperature lead/lag time constant r5 shall 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% z\l.
2.10.13 The f1 (Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive slope shall be +3.47% / % Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% / % Al.
COLR BYRON 2 Revision 9 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.11 ReactorTrip System (RTS) Instrumentation (LCO 3.3.1) OverpowerAl Setpoint Parameter Values 2.11 .1 The Overpower AT reactor trip setpoint K4 shall be equal to I .072.
2.1 1 .2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K shall be equal to 0.02 / °F for increasing Tavg.
2.11 .3 The Overpower AT 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/°FwhenT>T.
2.1 1 .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 583.5 °F 2.1 1 .7 The measured reactor vessel AT lead/lag time constant t1 shall be equal to 8 sec.
- 2. 1 1 .8 The measured reactor vessel AT lead/lag time constant E2 shall be equal to 3 sec.
2.1 1 .9 The measured reactor vessel AT lag time constant t3 shall 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.
2.1 1 .1 1 The measured reactor vessel average temperature rate/lag time constant -r7 shall be equalto 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 9 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 21 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.41) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 p51g.
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 greaterthan or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greaterthan or equal to the applicable value given in the Table below (LCO 3.9.1). The reported priorto 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 Conditions Boron Concentration Section (ppm) 2.13.1 a) priorto initial criticality 1714 b) for cycle burnups 0 MWD/MTU 829 and < 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1443 2.13.2 a) priorto initial criticality 1789 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2056 c) for cycle burnups 16000 1585 MWD/MTU