BYRON 2010-0040, Cycle 16 Core Operating Limits Report
| ML101240940 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/03/2010 |
| From: | Enright D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BYRON 2010-0040 | |
| Download: ML101240940 (18) | |
Text
Exelon Generation Com pa '~y, LLC Byron Station W\/v'vv.cxelonccrp.con1 Nuclear 4450 North Cermdfl Church RDad Syron. II. 61010-9794 May 3,2010 LTR: BYRON 2010-0040 File: 2.01.0300 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 Cycle 16 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 3 for Cycle 16.
Should you have any questions concerning this report, please contact David GUdger, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Daniel J. Enright Site Vice President Byron Station
Attachment:
Byron Station Unit 2 Cycle 16, COLR, Revision 3 DJ E/DG/J EUcy cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
ATTACHMENT Byron Station Unit 2 Core Operating Limits Report Revision 3 Cycle 16
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 16 EXELON TRACKING 10:
COLR BYRON 2 REVISION 3
COLRBYRON 2 Revision 3 Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 16 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specifications affected by this report are listed below:
SL 2.1.1 Reactor Core Safety Limits (SLs)
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 (Fo(Z>>
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN"'H)
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 (BOPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (ONB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual 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 (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 TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)
COLR BYRON 2 Revision 3 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 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.
680 .,-----r----'---,...-------,------r----,------,
660 - t - - - ' - - = - . t : : - - - - f - - - - - t - - - - - t - - - - + - - - - - 1 LL..
0'\
<l>
<<:::::)
-..... 6 of 0 ;-----+--~~k_---_+_---_+---.,;::"""""'=:__+----_I
<l>
~
=:J
~
<l>
a..
E
<l>
t- 620 -+--~~+----+_=:::........:__-+_---I__-----1I___=='''"=-_'lI
<l>
0'\
o
~
<l>
~
600 +----+----+----+_--.::::~I__---I__~......".._l o .2 . .. .6 .8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
COLRBYRON2 Revision 3 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 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% L'lk/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 SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% L'lk/k (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 BOUARO/HZP-MTC upper limit shall be +1.894 x 10-5 L'1k/k/oF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10-4 L'lk/k/oF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 L'1k/kJOF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 L'lk/k/oF.
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
COLRBYRON 2 Revision 3 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 Figure 2.5.1 :
Control Bank Insertion Umits Versus Percent Rated Thermal Power (27%.224) (77%,224) 224 220 +--_. I------+-----'----F--*- -.-..-.- .-.---.---
i i .__ .. _ f + ~,- ; --.*..***.. **..* *f-- *--*1 200
.I-f------f--*-..* --f----*-* -.. -.----.
180 c~ 160 'Jr-.=__~=__~f__-+_---+-~iIf-----i---l----+----+-----A (100%,161)
]g i [
~ 140 =""""'~""-"""---+-----'--f' 1/1 ! 1
~ 120 -- i *---i----
i 100 . *-1~- -IT~+- I
- c. I :
~ 80 +---+~'------+-------+--+---+--+--~-+---+-----+----I
~
"~ 60 20 -t------t-------+--+---A---+----'-----+---+----I--------I o _...-_+-_-!-_+--I---I---l.---i.-~~-ol-----
60 70 80 90 100 o 10 20 30 40 50 Relative Power (Percent)
COLR BYRON 2 Revision 3 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 2.6 Heat Flux Hot Channel Factor (Fggu (LCO 3.2.1) 2.6.1 Total Peaking Factor:
RTP F
FQ(Z) S -Q-xK(Z) for P sO.5 0.5 F RTP FQ(Z) s -Q-xK(Z) for P > 0.5 P
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~TP = 2.60 K(Z) is provided in Figure 2.6.1.
Figure 2.6.1 K(Z) - Normalized Fa(Z) as a Function of Core Height
- 1. 1 (0.0 1.0) (6.0 1.0) 1 (12.( ,0.924) 0.9 0.8 NO.7 a
".~ 0.6 IV E
o 0.5 z
N SZ 0.4 I* LOCA Limiting I L_____§.!l_~~()pe --
0.3 0.2 0.1 o
012 3 4 5 6 7 8 9 10 11 12 BOTTOM COfe Height (ft) TOP
COLRBYRON2 Revision 3 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 2.6.2 W(Z) Values:
a) When 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 Feo(z) penalty factors that are greater than 2% per 31 Effective W
Full Power Days (EFPD). These values shall be used to increase the F o(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 Fo(Z) shall be calculated by the following formula where:
Uqu =Base Fa measurement uncertainty =1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)
Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
=
Fo(Z) Warning Setpoint 2% Fo(Z) Margin
=
Fo(Z) Alarm Setpoint 0% Fo(Z) Margin
COLRBYRON2 Revision 3 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 Table 2.6.2.8 Full Cycle W(ZI versus Core Height for AFO Acceptable Operation Umits In Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-102161 Height 150 6000 14000 20000 (feet) MWOIMTU MWDIMTU MWOIMTU MWDIMTU 0.00 (core bottom) 1.4015 1.4857 1.3963 1.3157 0.20 1.3801 1.4394 1.3714 1.3025 0.40 1.3676 1.4204 1.3633 1.2953 0.60 1.3550 1.4033 1.3477 1.2901 0.80 1.3367 1.3829 1.3268 1.2873 1.00 1.3232 1.3640 1.3123 1.2822 1.20 1.3236 1.3404 1.2688 1.2746 1.40 1.3111 1.3275 1.2580 1.2677 1.60 1.2918 1.3096 1.2448 1.2572 1.80 1.2754 1.2869 1.2330 1.2483 2.00 1.2578 1.2651 1.2204 1.2378 2.20 1.2366 1.2484 1.2044 1.2236 2.40 1.2192 1.2246 1.1926 1.2100 2.60 1.1998 1.2059 1.1824 1.1942 2.80 1.1905 1.1906 1.1737 1.1796 3.00 1.1846 1.1853 1.1849 1.1668 3.20 1.1772 1.1794 1.1547 1.1610 3.40 1.1698 1.1739 1.1508 1.1652 3.60 1.1610 1.1665 1.1467 1.1689 3.80 1.1531 1.1591 1.1456 1.1720 4.00 1.1479 1.1516 1.1455 1.1732 4.20 1.1408 1.1412 1.1440 1.1750 4.40 1.1340 1.1323 1.1417 1.1884 4.60 1.1254 1.1204 1.1374 1.1973 4.80 1.1172 1.1104 1.1365 1.2056 5.00 1.1085 1.1073 1.1424 1.2108 5.20 1.1053 1.1024 1.1471 1.2148 5.40 1.1038 1.0996 1.1490 1.2168 5.60 1.1015 1.0958 1.1515 1.2316 5.80 1.0981 1.0924 1.1521 1.2501 6.00 1.1046 1.0949 1.1651 1.2647 6.20 1.1123 1.1026 1.1797 1.2773 6.40 1.1172 1.1103 1.1914 1.2869 6.60 1.1231 1.1170 1.2011 1.2916 6.80 1.1271 1.1228 1.2088 1.2953 7.00 1.1310 1.1278 1.2146 1.2951 7.20 1.1343 1.1340 1.2165 1.2908 7.40 1.1399 1.1429 1.2174 1.2847 7.60 1.1467 1.1502 1.2144 1.2737 7.80 1.1516 1.1570 1.2104 1.2617 8.00 1.1549 1.1634 1.2064 1.2487 8.20 1.1592 1.1672 1.1995 1.2318 8.40 1.1630 1.1732 1.1926 1.2149 8.60 1.1649 1.1822 1.1827 1.2054 8.80 1.1682 1.1909 1.1739 1.2036 9.00 1.1734 1.1981 1.1767 1.2008 9.20 1.1786 1.2106 1.1833 1.1950 9.40 1.1795 1.2331 1.1895 1.2359 9.80 1.1908 1.2531 1.1943 1.2775 9.80 1.1967 1.2726 1.2104 1.3162 10.00 1.1988 1.2906 12391 13508 10.20 1.2022 1.2972 1.2648 1.3795 10.40 1.2008 13001 1.2858 1.4062 10.60 1.2210 1.3102 1.3043 1.4339 10.60 1.2385 1.3207 1.3182 1.4537 11.00 12516 1.3336 1.3279 1.4695 11.20 12742 13559 1.3248 1.4834 11.40 1.2949 1.3609 1.3227 1.4572 11.60 1.2999 13660 1.3008 1.4332 11.60 1.3063 1.3749 1.2915 1.4231 12.00 (cora klp) 1.3201 1.3972 1.2873 1.4189 Note: W(Z) values at 20000 MWDIMTU may be applied to cycle burnups greater than 20000 MWOIMTU to prevent W(ZI function extrapolation
COLRBYRON2 Revision 3 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 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 per WCAP-10216)
Height 18000 20000 23533 (feet) MWD/MTU MWD/MTU MWDIMTU 0.00 (core bottom) 12097 12064 12064 020 1.1873 1.1794 1.1794 0.40 11783 1.1664 1.1664 060 1.1685 1.1582 1.1582 0.80 1.1599 1.1553 1.1553 100 1.1537 1.1523 1.1523 120 1.1443 1.1474 1.1474 1.40 1.1409 1.1430 1.1430 160 1.1352 1.1355 1.1355 1.80 1.1309 1.1291 1.1291 2.00 1.1265 1.1235 1.1235 2.20 1.1222 1.1199 1.1199 2.40 1.1178 1.1154 1.1154 2.60 1.1125 1.1104 1.1104 2.80 1.1099 1.1073 1.1073 3.00 1.1083 1.1052 1.1052 3.20 1.1091 1.1068 1.1068 3.40 1.1151 1.1181 1.1181 3.60 1.1230 1.1333 1.1333 3.80 1.1304 1.1476 1.1476 4.00 1.1399 1.1615 1.1615 4.20 1.1503 1.1749 1.1749 4.40 1.1586 1.1864 1.1864 4.60 1.1693 1.1973 1.1973 4.80 1.1778 1.2056 1.2056 5.00 1.1839 1.2108 1.2108 5.20 1.1890 1.2148 1.2148 5.40 1.1914 1.2168 1.2168 5.60 1.2014 1.2316 1.2316 5.80 1.2124 1.2501 1.2501 6.00 1.2272 1.2647 1.2647 6.20 1.2412 1.2773 1.2773 6.40 1.2520 1.2869 1.2869 6.60 1.2591 1.2916 1.2916 6.80 12647 1.2953 1.2953 7.00 1.2672 1.2951 12951 7.20 1.2652 1.2908 1.2908 7.40 1.2615 1.2847 1.2847 7.60 1.2531 1.2737 1.2737 780 1.2437 1.2617 1.2617 8.00 1.2337 1.2487 12487 8.20 12203 12318 1.2318 8.40 1.2067 1.2149 1.2149 8.60 1.1955 1.2054 1.2054 880 11891 1.2036 1.2036 900 1.1884 1.2008 1.2008 9.20 1.1875 1.1950 1.1950 9.40 1.2118 1.2359 1.2359 9.60 1.2361 1.2775 12775 9.80 1.2646 1.3162 1.3162 1000 1.2974 1.3508 1.3508 1020 1.3263 1.3795 1.3795 1040 1.3520 1.4062 1.4062 1060 13765 1.4339 14339 10.80 1.3940 1.4537 1.4537 11.00 14069 1.4895 1.4695 1120 1.4001 1.4634 14634 11.40 1.3952 1.4572 1.4572 11.60 1.3696 1.4332 1.4332 11.80 13586 1.4231 1.4231 12.00 (core lop) 1.3522 1.4189 14189 Note: W(Zl values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Zl function extrapolation
COLRBYRON2 Revision 3 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 Table 2.6.2.c
---.--.-- -i;):e:~~~j!y£~~!§_rsi ~:~~~~:~f2o/.~-e!f~;(~F:r:'[r~:*:*---
__C;¥.cJ~ B.!J~~e. __ .____ .. ~e_naltYJ.~?tO! ._.....
(MWD/MTIJ) FCo(z) o 1.0601 150 1.0601 323 1.0655 669 1.0691 842 1.0691 1189 1.0622 2573 1.0200 15036 1.0200 15209 1.0227 15556 1.0256 16421 1.0307 18152 1.0322 18671 1.0309 19710 1.0200 Notes:
linear interpolation is adequate for intermediate cycle burnups.
All cycle burnups outside the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
COLR BYRON 2 Revision 3 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 N
2.7 Nuclear Enthalpy Rise Hot Channel Factor (F Al::l1 (LCO 3.2.2) 2.7.1 FN6H ~ F~~P[1.0 + PF6H(1.0 - P)]
=
where: P the ratio of THERMAL POWER to RATED THERMAL POWER
=
F~~P 1.70 PF6H = 0.3
2.7.2 Uncertainty
The uncertainty, UFilH , to be applied to the Nuclear Enthalpy Rise Hot Channel Factor N
F 6H shall be calculated by the following formula:
where:
UF&lm =Base F 6H measurement uncertainty =1.04 when PDMS is inoperable N
(U F6Hm is defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
N
= N F 6H Warning Setpoint 2% F ilH Margin N
= N F 6H Alarm Setpoint 0% F 6H 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) (LeO 3.2.5) 2.9.1 DNBR APSL ~ 1.536 The Axial Power Shape Limiting DNBR (DNBRAPsd 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
COLRBYRON 2 Revision 3 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 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 I
I I
120 I
I I I
~+ 10 I
i (-1 100 . _
~ ~ -..+ , ", .
I I I I : i 0::
w i Unacfepta~le I i Unacceptable I
~ ' . 1 .1 Q I
~ 80 ..".p IHa tL0'1---. ".- - .. -t-_** - -- --- t*~* . -~~.- .. 0 peratlpn." ...
Ii ' A~cept~ble I j
..oJ
- E dperatlon I I 0:: I I I f W + ,., ,.. "',.. I
.... 60
- t: ..' j . ..... _..1
- 1 I o
....w i I
,. __ (~35J-5J.L .....
I I
C2 40 o
j i C+/-1/25 ."t L.+-.
i o
I
'cf? I L.
I :
I ~ i
._- " '. ,. r--" ....
I i 20 ~- r*---i--- T-I o I .
I I o I
.~-i--~---+----.;.----;---i---+---'---4-_-l 40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
II
COLR BYRON 2 Revision 3 Page 120fl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 Figure 2.8.1.b:
Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup ~ 18000 MWD/MTU)
I I Axial Flux Difference Limits I with PDMS Inoperable I
Unacceptabl~
-Operation-t------ --
o 20 - --- ..........*- . __ I .
o
-50 -40 -30 -20 -10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BYRON 2 Revision 3 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 2.10 Reactor Trip System eRTS) Instrumentation (LCO 3.3.1) - Overtemperature tiT Setpoint Parameter Values 2.10.1 The Overtemperature tiT reactor trip setpoint K 1 shall be equal to 1.325.
2.10.2 The Overtemperature tiT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ of.
2.10.3 The Overtemperature tiT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 of.
2.10.5 The nominal RCS operating pressure (indicated) pi shall be equal to 2235 psig.
2.10.6 The measured reactor vessel tiT lead/lag time constant '1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel tiT lead/lag time constant '2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel tiT lag time constant '3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant '4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant '5 shall 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 (til) "positive" breakpoint shall be +10% til.
2.10.13 The f 1 (til) "negative" breakpoint shall be -18% til.
2.10.14 The f 1 (til) "positive" slope shall be +3.47% / % til.
2.10.15 The f 1 (til) "negative" slope shall be -2.61% / % til.
COLRBYRON 2 Revision 3 Page 14 of 15 CORE OPERATrNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower t.T Setpoint Parameter Values 2.11.1 The Overpower t.T reactor trip setpoint K; shall be equal to 1.072.
2.11.2 The Overpower t.T reactor trip setpoint Tavg ratellag coefficient Ks shall be equal to 0.021 of for increasing T avg 2.11.3 The Overpower t.T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to o1 °F for decreasing Tavg.
2.11.4 The Overpower t.T reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0.002451 of when T> Tit.
2.11.5 The Overpower t.T reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 01 of when T::;; Tit.
2.11.6 The nominal Tavg at RTP (indicated) Tn shall be less than or equal to 588.0 of 2.11.7 The measured reactor vessel t.T lead/lag time constant '1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel t.T lead/lag time constant '2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel t.T lag time constant '3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant 'S shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant '7 shall be equal to 10 sec.
2.11.12 The f2 (t.I) "positive" breakpoint shall be 0 for all t.1.
2.11.13 The f2 (t.I) "negative" breakpoint shall be 0 for all t.1.
2.11.14 The fdt.l) "positive" slope shall be 0 for all t.1.
2.11.15 The f2 (t.I) "negative" slope shall be 0 for all t.1.
COLRBYRON2 Revision 3 Page 15 of 15 CORE OPERATfNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 16 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 of.
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 value given in the Table below (LCO 3.9.1). The reported 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 values given in the Table below.
COLR Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1682 2.13.2 a) prior to initial criticality 1759 2.13.2 b) all other limes in life 1938