BYRON 2015-0103, Cycle 21 Core Operating Limits Report
| ML15265A072 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/22/2015 |
| From: | Kearney F Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2015-0103 | |
| Download: ML15265A072 (17) | |
Text
Byron Generating Station Exeton Generation 4450 North German Church Rd Byron, IL 61010-9794 www.exeloncorp.com September 22, 2015 LTR: BYRON 207 5-0103 File: 2.07 .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 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454
Subject:
Byron Station Unit 1 Cycle 21 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 11, for Cycle 21.
Should you have any questions concerning this report, please contact Mr. Douglas Spitzer, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Site Vice Byron Generating )n
Attachment:
Byron Station Unit 1 Cycle 21, COLR, Revision 11 FAK/GC/sg cc: Regional Administrator NRC Region III NRC Senior Resident Inspector Byron Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT I CYCLE 21 EXELON TRACKING ID:
COLR BYRON I REVISION II
COLR BYRON I Revision 11 Page 1 of 15 CORE OPERATING LtMtTS REPORT (COLR) for BYRON UNIT I CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (CDLR) for Byron Station Unit 1 Cycle 21 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 (LCD5) affected by this report are listed below:
SL 2.1.1 Reactor Core Safety Limits (SL5)
LCD 3.1.1 SHUTDOWN MARGIN (SDM)
LCD 3.1.3 Moderator Temperature Coefficient (MTC)
LCD 3.1.4 Rod Group Alignment Limits LCD 3.1.5 Shutdown Bank Insertion Limits LCD 3.1.6 Control Bank Insertion Limits LCD 3.1.8 PHYSICS TESTS Exceptions MODE 2 LCD 3.2.1 Heat Flux Hot Channel Factor (F0(Z))
LCD 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH)
LCD 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCD 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
LCD 3.3.1 Reactor Trip System (RTS) Instrumentation LCD 3.3.9 Boron Dilution Protection System (BDPS)
LCD 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCD 3.9.1 Boron Concentration The portions of the Technical Requirements Manual (TRM) affected by this report are listed below:
TRM TLCD 3.1 .b Boration Flow Paths Operating TRM TLCO 3.1 .d Charging Pumps Operating TRM TLCO 3.1.1 Borated Water Sources Operating TRM TLCD 3.1 .g Position Indication System Shutdown TRM TLCO 3.1 .h Shutdown Margin (5DM) MODE 1 and MODE 2 with keff 1.0 TRMTLCD 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1.] Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)
COLR BYRON I Revision I Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I 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 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.
660 psia 66 U psia ci ci 640 S.
ooo psia N 0)
E 0) 620 0)
C)
CL) 6C -____
- I I I I I I I 0.2 0.1 0.6 0.6 1 1.2 Fracion o NcrinaI Povir Figure 2.1.1: Reactor Core Limits
COLR BYRON I Revision 11 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 21 2.2 SHUTDOWN MARGIN (SDM)
The SDM limit for MODES 1, 2, 3, and 4 is:
2.2.1 The SDM 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, 3.1.1, 3.1.h, and 3.1.j).
The SDM 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 Moderator Temrerature 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 +2.035 x i0 Ak/k/CF.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x i04 Ak/k/CF.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0 Ak/k/CF.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1 0 Ak/k/CF.
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 I Revision 11 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (26.52%, 224) (76.96%, 224) 220 200 180 160 (100%, 161) 140 0
0.
C) 120 0c CC V
0 60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BYRON I Revision 11 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 2.6 Heat Flux Hot Channel Factor (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FRTP FQ(Z) 9-xK(Z) forP0.5 RTP FQ(Z) 9-xK(Z) for P>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTF= 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 t91i :PiL21J 1
[ço,0.924)I 0.9 0,8 0.7 a
U V
0.6 LOCA Limiting 0.4 Envelope 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 1 Revision 11 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 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 for the full cycle and correspond to the 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.
- 2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOL-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.
Table 2.6.2.c shows the FCo(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F0(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, UFO, to be applied to the Heat Flux Hot Channel Factor F0(Z) shall be calculated by the following formula
= 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:
F0(Z) Warning Setpoint = 2% F0(Z) Margin F0(Z) Alarm Setpoint = 0% F0(Z) Margin
COLR BYRON I Revision 11 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 21 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFO Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-1 0216)
Height 150 6000 14000 20000 (feet) MWDIMTU MWD!MTU MWD!MTU MWD!MTU 0.00 (core bottom) 1.3318 1.4685 1.4170 1.3511 0.20 1.3188 1.4244 1.3820 1.3254 0.40 1.3143 1.4056 1.3650 1.3132 0.60 1.3088 1.3888 1.3480 1.3027 0.80 1.2997 1.3656 1.3270 1.2984 1.00 1.2884 1.3526 1.3140 1.2936 1.20 1.2746 1.3369 1.2980 1.2868 1.40 1.2651 1.3201 1.2870 1.2801 1.60 1.2569 1.2987 1.2740 1.2694 1.80 1.2514 1.2807 1.2620 1.2607 2.00 1.2422 1.2592 1.2500 1.2510 2.20 1.2262 1.2369 1.2360 1.2364 2.40 1.2110 1.2154 1.2230 1.2247 2.60 1.1941 1.1920 1.2079 1.2091 2.80 1.1794 1.1737 1.1970 1.1945 3.00 1.1681 1.1692 1.1902 1.1833 3.20 1.1590 1.1645 1.1821 1.1764 3.40 1.1528 1.1603 1.1746 1.1820 3.60 1.1438 1.1538 1.1647 1.1852 3.80 1.1395 1.1480 1.1609 1.1886 4.00 1.1344 1.1418 1.1567 1.1908 4.20 1.1296 1.1328 1.1507 1.1900 4.40 1.1313 1.1251 1.1446 1.1927 4.60 1.1319 1.1151 1.1376 1.2011 4.80 1.1323 1.1060 1.1381 1.2075 5.00 1.1311 1.0989 1.1386 1.2110 5.20 1.1285 1.0955 1.1397 1.2143 5.40 1.1261 1.0912 1.1411 1,2170 5.60 1.1215 1.0868 1.1497 1.2354 5.80 1.1178 1.0897 1.1641 1,2507 6.00 1.1237 1.0955 1.1776 1.2640 6.20 1.1304 1.1003 1.1884 1.2724 6.40 1.1351 1.1061 1.1971 1.2779 6.60 1.1389 1.1147 1.2029 1.2796 6.80 1.1417 1.1214 1.2076 1.2794 7.00 1.1435 1.1271 1.2085 1.2753 7.20 1.1446 1.1338 1.2065 1.2662 7.40 1.1479 1.1447 1.2035 1,2562 7.60 1.1582 1.1543 1.1965 1.2404 7.80 1.1680 1.1635 1.1886 1.2255 8.00 1.1767 1.1728 1.1788 1.2077 8.20 1.1849 1.1830 1.1661 1.1873 8.40 1.1919 1.1934 1.1546 1.1774 8.60 1.1976 1.2023 1.1555 1.1646 8.80 1.2005 1.2107 1.1577 1.1519 9.00 1.2005 1.2186 1.1598 1.1415 9.20 1.2129 1.2365 1.1630 1.1764 9.40 1.2203 1.2536 1.1714 1,2100 9.60 1.2274 1.2687 1.1960 1.2560 9.80 1.2313 1.2837 1.2300 1.2960 10.00 1.2348 1.2979 1.2610 1.3320 10.20 1.2429 1.3104 1.2860 1.3640 10.40 1.2509 1.3227 1.3030 1.3900 10.60 1.2447 1.3314 1.3139 1.4156 10.80 1.2514 1.3363 1.3287 1,4364 11.00 1.2490 1.3290 1.3385 1.4492 11,20 1.2341 1.3207 1.3380 1.4300 11.40 1.2386 1.3260 1,3350 1.4170 11.60 1.2433 1.3329 1.3062 1.3900 11.80 1.2486 1.3394 1.2951 1.3849 12.00 (core top) 1.2572 1.3498 1.2878 1,3886 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 I Revision II Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 Table 2.6.2.b EOL-only W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded er WCAP-1 0216)
Height 18000 20000 24114 (feet) MWD!MTU MWDIMTU MWDIMTU 0.00 (core bottom) 1 2467 1.2264 1.2264 0.20 1 2208 1.2019 1.2019 0.40 1.2067 1.1875 1.1875 0.60 1.1960 1.1794 1.1794 0.80 1.1886 1.1788 1.1788 1.00 1.1826 1.1766 1.1766 1.20 1.1728 1.1722 1.1722 1.40 1.1668 1.1676 1.1676 1.60 1.1586 1.1599 1.1599 1.80 1.1523 1.1535 1.1535 2.00 1.1502 1.1471 1.1471 2.20 1.1448 1.1376 1.1376 2.40 1.1401 1.1294 1.1294 2.60 1.1334 1.1192 1.1192 2.80 1.1276 1.1102 1.1102 3.00 1.1240 1.1078 1.1078 3.20 1.1244 1.1136 1.1136 3.40 1.1282 1.1257 1.1257 3.60 1.1345 1.1409 1.1409 3.80 1.1447 1.1551 1.1551 4.00 1.1543 1.1673 1.1673 4.20 1.1630 1.1792 1.1792 4.40 1.1697 1.1891 1.1891 4.60 1.1749 1.1976 1.1976 4.80 1.1798 1.2056 1.2056 5.00 1.1833 1.2110 1.2110 5.20 1.1859 1.2143 1.2143 5.40 1.1884 1.2170 1.2170 5.60 1.2035 1.2354 1.2354 5.80 1.2193 1.2507 1.2507 6.00 1.2333 1.2640 1.2640 6.20 1.2433 1.2724 1.2724 6.40 1.2504 1.2779 1.2779 6.60 1.2536 1.2796 1.2796 6.80 1.2553 1.2794 1.2794 7.00 1.2530 1.2753 1.2753 7.20 1.2462 1.2662 1.2662 7.40 1.2381 1.2562 1.2562 7.60 1.2248 1.2404 1.2404 7.80 1.2115 1.2255 1.2255 8.00 1.1957 1.2077 1.2077 8.20 1.1767 1.1873 1.1873 8.40 1.1643 1.1774 1.1774 8.60 1.1568 1.1646 1.1646 8.80 1.1500 1.1519 1.1519 9.00 1.1445 1.1415 1.1415 9.20 1.1644 1.1764 1.1764 9.40 1.1863 1.2100 1.2100 9.60 1.2237 1.2560 1.2560 9.80 1.2626 1.2960 1.2960 10.00 1.2977 1.3320 1.3320 10.20 1.3276 1.3640 1.3640 10.40 1.3501 1.3900 1.3900 10.60 1.3694 1.4156 1.4156 10.80 1.3884 1.4364 1.4364 11.00 1.4013 1.4492 1.4492 1 1.20 1.3908 1.4300 1.4300 11.40 1.3815 1.4170 1.4170 11.60 1.3508 1.3900 1.3900 11.80 1.3416 1.3849 1.3849 12.00 (core top) 1.3391 1.3886 1.3886 Note: W(Z) values at 20000 MWUIMTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BYRON 1 Revision 11 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDIMTU) FC0(z) 0 1.0200 502 1.0200 1205 1.0427 1381 1.0450 1700 1.0450 1909 1.0422 2085 1.0392 2261 1.0356 2964 1.0214 3140 1.0200 14396 1.0200 14572 1.0204 15099 1.0208 15803 1.0213 16600 1.0218 17034 1.0218 17913 1.0215 18100 1.0213 18660 1.0200 24114 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 11 Page 10 of 15 CORE OPERATING LtMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7.1 FH F[1.0 ÷ PFH(l.0 P)] -
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
RTP PFH = 0.3
2.7.2 Uncertainty
The uncertainty, UF.\H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FH shall be calculated by the following formula:
UFH = UF.Hm where:
UF]Hm = Base FH measurement uncertainty = 1.04 when PDMS is inoperable (UFHm is defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
FH Warning Setpoint = 2% FH Margin FNAH Alarm Setpoint = 0% FH 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 full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.
b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.
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% RIP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin
COLR BYRON I Revision 11 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON tIN IT I CYCLE 21 Figure 2.8.1.a:
Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)
Axial Flux Difference Limits with PDMS Inoperable 120
(-15, 100) (+10, 100) 100 1
w UnacceptablE Unaceptaile 0 80 0peation
/ Operatlo 0
-J / Acceptable Operati n
\
/
Ui I
60 I
/
Ui I.
(-3 5, 50) (+ 5, 5 )
40 0
20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON I Revision II Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 Figure 2.8.1.b:
Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup 18000 MWDIMTU)
Axial Flux Difference Limits with PDMS Inoperable 120
(-10,100) (+10,100) 100 0-
-J 80 Unacceptable Operation
/ \
I Unacceptable Operation Acceptable Operation 60
(-20,50) (+25, 50) 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON I Revision 11 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - OvertemperatureAT Setpoint Parameter Values 2.10.1 The OvertemperatureAT reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The OvertemperatureAT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.
2.10.3 The OvertemperatureAT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 / psi.
2.10.4 The nominal Tavgat 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 r1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r2shall 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.
2.10.11 The measured reactor vessel average temperature lag time constant r6shall be less than or equal to 2 sec.
2.10.12 The f1(AI) positive breakpoint shall be +10% Al.
2.10.13 The f1(Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive slope shall be +3.47% I % Al.
2.10.15 The f1(AI) negative slope shall be -2.61% 1% Al.
COLR BYRON 1 Revision II Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 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 1<4 shall be equal to 1 .072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing Tavg.
2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient 1(5 shall be equal to 0 / F for decreasing Tavg.
2.11.4 The Overpower AT reactor trip setpointTavgheatup 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 I 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 r1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant r2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant tshall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant r6shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant t7 shall 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 11 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 21 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 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.
. Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1653 b) for cycle burnups 0 MWD/MTU 1764 and < 16000 MWD/MTU c) for cycle burnups 16,000 MWD/MTU 1410 2.13.2 a) prior to initial criticality 1754 b) all other times in life 1980