BYRON 2017-0017, Cycle 22 Core Operating Limits Report
| ML17068A067 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/09/2017 |
| From: | Kanavos M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2017-0017 | |
| Download: ML17068A067 (17) | |
Text
Byron Generating Station Exeton Generation Rd www.exeloncorp.com March 9, 2017 LTR:
BYRON 2017-0017 File:
1.10.0101 (1D.101) 2.01.0300 (5A.l01)
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 22 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 12, for Cycle 22.
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 22, COLR, Revision 12 MEK/GC/sg cc:
Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Generating Station
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 1 CYCLE 22 EXELON TRACKING ID:
COLR BYRON UNIT 1 REVISION 12
1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 22 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 21.1 Reactor Core Safety Limits (SL5)
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 (F0(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH)
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 ILCO 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 1 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 IRM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)
COLR BYRON I Revision 12 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22
COLR BYRON I Revision 12 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 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) fSL 2.1.1) 2.1.1 In MODES 1 and 2, the combination of Thermal Power, Reactor Coolant System (RCS) highest ioop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.
U 0) ci ci ci P
ci 0 t bl 670 600 241 I)sia 2250psia
-0 psia N
1860 psia
\\
JO J
I I
I I
I I
I I
I I
N 0
02 0.4 0.6 0.8 Frc:iori c NorrriuI Power 1.2 Figure 2.1.1: Reactor Core Limits
COLR BYRON 1 Revision 12 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 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 (LCO5 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRMTLCOs 3.1.b, 3.1.d, 3.1.f, 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 Temperature Coefficient (MTC) (LCD 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +1.328 x 10 AkIk/5F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 Ak/k/5F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0 Ak/k/5F.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1 0 Ak/k/SF.
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 (LCD 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCD 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 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power Revision 12 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 (26.52%, 224)
(76.96%, 224) 224 220 200 180 160 140 0
C) 120 100 0
60 40 20 0
(100%, 161) 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BYRON I Revision 12 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 2.6 Heat Flux Hot Channel Factor (F0)j (LCO 3.2.1) 2.6.1 Total Peaking Factor:
RTP fQ(Z) 9-xK(Z) forPO.5 F RTP FQ(Z) 9xK(Z) forP>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 0.7 a
La G)N E
0z
- 0.4 1.1 1
0.9 0.8 I (61j Li 00.924)1 0.3 0.2 0.1 0
LOCAL1mWng 1 Envelope 0
1 2
3 4
5 6
7 8
9 101112 BOTTOM Core Height (ft)
COLR BYRON I Revision 12 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 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 WfZ) 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 FCo(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FN(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
=
where:
Uqu = Base F0 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% F0(Z) Margin F0(Z) Alarm Setpoint = 0% FQ(Z) Margin
COLR BYRON I Revision 12 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON LINIT 1 CYCLE 22 Table 2.6.2.a WfZ) 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 MWDIMTU 0.00 (core bottom) 1.1866 1.3294 1.2862 1.2229 0.20 1.1731 1.2937 1.2601 1.2074 0.40 1.1646 1.2748 1.2479 1.2007 0.60 1.1610 1.2591 1.2356 1.1997 0.80 1,1605 1.2398 1.2193 1.1974 1.00 1.1560 1.2251 1.2071 1.1962 1,20 1,1545 1.2152 1.1936 1.1886 1,40 1,1556 1.2100 1.1824 1.1827 1,60 1.1461 1.1906 1.1683 1.1702 1.80 1.1418 1.1757 1.1643 1.1616 2.00 1.1400 1.1620 1.1597 1.1517 2.20 1.1355 1.1466 1.1524 1.1389 2.40 1.1317 1.1337 1.1448 1.1273 2.60 1.1270 1.1224 1.1374 1.1128 2.80 1.1214 1.1197 1,1348 1.1076 3.00 1.1166 1.1163 1.1312 1.1064 3.20 1.1114 1.1137 1.1258 1.1110 3.40 1,1139 1.1110 1.1205 1.1197 3.60 1.1195 1.1082 1.1142 1.1284 3.80 1.1243 1.1078 1.1108 1.1361 4.00 1,1289 1.1072 1.1143 1.1437 4.20 1.1336 1.1053 1.1187 1.1517 4.40 1.1362 1.1036 1.1229 1.1650 4,60 1.1389 1.1015 1.1261 1.1771 4.80 1,1405 1.0988 1.1275 1.1872 5.00 1.1412 1.0959 1.1294 1.1953 5.20 1,1408 1.0918 1.1324 1.2003 5.40 1,1408 1,0878 1.1336 1.2038 5.60 1.1491 1.0847 1.1370 1.2168 5.80 1.1559 1.0911 1.1536 1.2363 6.00 1.1616 1.0988 1.1692 1.2529 6.20 1,1663 1.1067 1.1819 1.2656 6.40 1,1700 1.1126 1.1936 1.2762 6.60 1,1717 1.1186 1,2013 1.2820 6.80 1,1715 1.1244 1.2081 1.2858 7.00 1.1712 1,1309 1.2128 1.2855 7,20 1.1681 1.1395 1.2137 1.2804 7.40 1.1694 1.1483 1.2136 1.2753 7.60 1.1692 1.1567 1.2105 1.2652 7.80 1.1734 1.1640 1.2065 1.2542 8.00 1.1797 1.1709 1.2005 1.2413 8.20 1.1845 1.1762 1.1896 1.2254 8.40 1.1883 1.1820 1.1817 1.2105 8.60 1,2036 1.1899 1.1728 1.1926 8,80 1.2057 1.1992 1,1708 1.1908 9.00 1.2002 1.2076 1.1692 1.1889 9.20 1.1966 1.2201 1.1755 1.1955 9.40 1,1947 1.2382 1,1609 1.2409 9,60 1.1887 1.2598 1.1867 1.2835 9.80 1.1843 1.2789 1.2175 1.3222 10.00 1.1779 1.2969 1.2471 1.3578 10,20 1.2000 1.3122 1.2748 1,3876 10.40 1.2220 1.3106 1.2966 1.4163 10,60 1,2400 1.3040 1,3154 1 4351 10.80 1.2530 1.3016 1,3302 1.4539 11.00 1.2600 1.3100 1,3400 1.4647 11.20 1,2311 1.3295 1.3379 1.4676 11.40 1,2296 1.3480 1.3337 1.4565 11.60 1.2270 1.3514 1,3057 1.4255 11,80 1,2314 1.3591 1.2936 1.4104 12.00 (core top) 1,2410 1.3777 1.2864 1.4002 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 12 Page $ of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 Table 2.6.2.b W(Z) versus Core Height for Expanded AFO Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 6% Excluded per WCAP-10216)
Height 150 6000 14000 20000 (feet)
MWDIMTU MWD!MTU MWDIMTU MWDIMTU 000 (Core bottom) 1.3378 1.5031 1.4319 1.3408 0.20 1.3202 1.4580 1.4004 1.3292 0.40 1.3025 1.4344 1.3856 1.3254 0.60 1.2868 1.4159 1.3708 1.3235 0.80 1.2742 1.3924 1.3502 1.3188 1.00 1.2664 1.3729 1.3354 1.3161 1.20 1.2647 1,3602 1.3186 1.3055 1.40 1.2886 1.3496 1.3049 1.2977 1.60 1.2759 1.3241 1.2872 1.2812 1.80 1.2633 1.3016 1.2724 1.2705 2.00 1.2516 1.2809 1.2566 1.2579 2.20 1.2369 1.2565 1.2380 1,2414 2.40 1.2243 1.2359 1.2222 1.2268 2.60 1.2096 1.2125 1.2090 1.2083 2.80 1.1959 1.1949 1.1980 1.1917 3.00 1.1823 1.1861 1.1898 1.1757 3.20 1.1666 1.1786 1.1791 1.1582 3.40 1.1590 1.1740 1.1714 1.1574 3.60 1.1553 1.1669 1.1622 1.1640 3.80 1.1513 1.1613 1.1546 1.1685 4.00 1.1473 1.1543 1.1484 1,1730 4.20 1.1427 1.1457 1.1442 1.1751 4.40 1.1441 1.1376 1.1390 1.1756 4.60 1.1454 1.1270 1.1324 1.1771 4.80 1.1458 1.1180 1.1275 1.1872 5.00 1.1452 1,1079 1.1294 1,1953 5.20 1.1435 1.0963 1.1324 1.2003 5.40 1.1409 1.0878 1.1336 1.2038 5.60 1.1491 1.0847 1.1370 1.2168 5.80 1.1559 1,0911 1.1536 1,2363 6.00 1.1616 1.0988 1.1692 1,2529 6.20 1.1663 1.1067 1.1819 1.2656 6.40 1.1700 1.1126 1.1936 1.2762 6.60 1.1717 1.1186 1.2013 1.2820 6.80 1.1715 1.1244 1.2081 1.2858 7.00 1.1712 1.1309 1.2128 1.2855 7.20 1.1681 1.1395 1.2137 1.2804 7.40 1.1694 1.1483 1.2136 1.2753 7.60 1.1692 1,1567 1.2105 1,2652 7.80 1.1734 1.1640 1.2065 1.2542 8.00 1.1797 1,1709 1,2005 1.2413 8.20 1.1845 1.1762 1.1896 1.2254 8.40 1.1883 1.1820 1.1817 1,2105 8.60 1.2036 1.1899 1.1728 1.1926 8.80 1.2057 1.1992 1.1708 1.1908 9.00 1.2002 1.2076 1.1692 1.1889 9.20 1.1966 1.2201 1.1755 1,1955 9,40 1.1947 1.2382 1.1809 1.2409 9.60 1.1887 1.2598 1.1867 1,2835 9,80 1.1843 1.2789 1.2175 1.3222 10.00 1.1779 1.2969 1.2471 1.3578 10.20 1.2000 1.3122 1.2748 1,3676 10.40 1.2220 1.3106 1.2966 1.4163 10.60 1.2400 1.3040 1.3154 1.4351 10.80 1.2530 1.3016 1,3302 1.4539 11.00 1.2600 1,3100 1.3400 1.4647 11.20 1.2311 1.3295 1.3379 1.4676 11.40 1.2296 1.3480 1.3337 1.4565 11.60 1.2270 1.3514 1.3057 1.4255 11.80 1.2314 1,3591 1.2936 1,4104 12.00 (core top) 1.2410 1.3777 1.2864 1.4002 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 12 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWDIMTU)
FC0(z) 678 10200 854 1.0297 1381 1.0385 1557 1.0385 1909 1.0337 2436 1.0200 8416 1.0200 8592 1.0234 8768 1.0250 8944 1.0244 9296 1.0230 9999 1.0200 13692 1.0200 14044 1.0233 14748 1.0242 15099 1.0252 15979 1.0285 17034 1.0312 18617 1.0312 19848 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 12 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F). (LCD 3.2.2) 2.7.1 FH F[l.0 + PFH(1.O
- P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RIP)
RTP CjH
PFH = 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:
UFXH = UFHm where:
UFJHm = Base FH measurement uncertainty = 1.04 when PDMS is inoperable fUFHm is defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
FH Warning Setpoint = 2% FF4H Margin FNH 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 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% 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 12 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 Figure 2.8.1.a:
Normal Axial Flux Difference Limits as a Function of Rated Thermal Power 120 100 Co 80
-J 60 I
w 40 0
p 0
20 0
Normal Axial Flux Difference Limits with PDMS Inoperable
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 1
Revision 12 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 Figure 2.8.1.b:
Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power 120 100 w
0.
80
-j 60 I
0 Expanded Axial Flux Difference Limits with PDMS Inoperable
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON I Revision 12 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1)
- Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / F.
2.10.3 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 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 r shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant t3 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 r5shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant 6 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 11 (Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) upositive slope shall be +3.47% / % Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% 1% Al.
COLR BYRON I Revision 12 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 2.11 Reactor Trip System (RTS) Instrumentation (LCD 3.3.1)
- Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint T89 rate/lag coefficient K5 shall be equal to 0.02 I F for increasing avg 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.
2.11.5 The Overpower AT reactor trip setpoint Tag heatup coefficient K6 shall be equal to 0 / °F when I T.
2.11.6 The nominal Tavg at RIP (indicated) T shall be less than or equal to 588.0 F.
2.11.7 The measured reactor vessel AT lead/lag time constant t1 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 shall be equal to 10 sec.
2.11.12 The f2 (Al) positive breakpoint shall be 0 for all Al.
2.11.13 The 12 (Al) negative breakpoint shall be 0 for all Al.
2.11.14 The 12 (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 12 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 22 2.12 Reactor Coolant System (RCS) Pressure. Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCD 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 (LCD 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 8.2 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 1700 b) for cycle burnups 0 MWD/MTU 1808 and < 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1479 2.13.2 a) prior to initial criticality 1736 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 2014 c) for cycle burnups 16000 1593 MWD/MTU