BYRON 2011-0139, Cycle 17 Core Operating Limits Report
| ML112730009 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/29/2011 |
| From: | Tulon T Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| BYRON 2011-0139 | |
| Download: ML112730009 (18) | |
Text
Church Road September 29,2011 L TR:
BYRON 2011-0139 File:
2.01.0300 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455 Byron Station Unit 2 Cycle 17 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 4 for Cycle 17.
Should you have any questions concerning this report, please contact Mr. David Gudger, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Tim~y J. Tulon Site Vice President Byron Station
Attachment:
Byron Station Unit 2 Cycle 17, COLR, Revision 4 T JT/DG/JEL/cy 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
ATIACHMENT Byron Station Unit 2 Core Operating Limits Report Revision 4 Cycle 17
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 17 EXELON TRACKING 10:
COLR BYRON 2 REVISION 4
COLRBYRON2 Revision 4 Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 17 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 (DNB) 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 TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLeO 3.1.h TRM TLeO 3.1.i TRM TLeO 3.1.j TRM TLeO 3.1.k Boration Flow Paths - Operating Charging Pumps - Operating Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff?: 1.0 Shutdown Margin (SDM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)
COLR BYRON 2 Revision 4 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 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------~------r-----~
660+---~~~----~------+------+------~----~
600+-------+------4------~----~~------~--~~~
o
.2
.4
.6
.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
COLR BYRON 2 Revision 4 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 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% Ilklk (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% Ilklk (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 +1.587 x 10.5 llk/k/oF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10-4 IlklkloF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 IlklkloF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 IlklkloF.
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 4 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 Figure 2.5.1 :
Control Bank Insertion Limits Versus Percent Rated Thermal Power (27%,224)
(77%,224)
(100%,161) 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLRBYRON2 Revision 4 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 2.6 Heat Flux Hot Channel Factor (Fg(Z>> (LCO 3.2.1) 2.6.1 Total Peaking Factor:
1.1 0.9 0.8 NO.7 a
LI..
"C
.~ 0.6
-; e o 0.5 z
E!
- c: 0.4 0.3 0.2 0.1 o
FRTP FQ(Z) ~ -Q-xK(Z) for P ~ 0.5 0.5 F RTP FQ(Z) ~ -Q-xK(Z) for P > 0.5 P
where: P = the ratio ofTHERMAL 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 FQ(Z) as a Function of Core Height (0.0 1.0) o BOTTOM 2
3 (6.0 4
5 6
7 Core Height (ft) 1.0)
(12.* -
..... LOCA Limiting. ~
Envelope 8
9 10 11 TOP 12 0.924)
COLRBYRON2 Revision 4 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 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 P: a(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWa(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, UFa, to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula where:
Uqu = Base Fa measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)
Us = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FdZ) Warning Setpoint = 2% Fa(Z) Margin Fo(Z) Alarm Setpoint = 0% Fa(Z) Margin
COLRBYRON2 Revision 4 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits In Figure 2.8.1.a (Top and Bottom 8% Excluded perWCAP.10216)
Height 150 6000 14000 (feet)
MWD/MTU MWD/MTU MWD/MTU 0,00 (core bottom) 1,3299 1,4657 1,3922 0,20 13205 1,4365 1,3669 0,40 13190 1,4197 1,3620 0,60 13072 1,4030 1,3515 0,80 12805 13653 1,3168 100 12685 1,3449 1.3011 120 12644 13440 12925 1,40 1,2523 1,3311 12839 160 1.2419 1,3099 1,2674 180 12432 1.2914 12568 2,00 12395 12725 12417 2,20 1,2258 12601 12278 2,40 12107 12312 1,2184 2,60 11935 1,2100 1,2081 280 1,1782 1,1949 1,2015 3,00 1,1694 11890 11932 3,20 1.1605 11615 1,1828 JAO 1,1538 1,1750 1,1738 3,80 1,1468 1,1669 1.1626 3,80 1.1442 1.1592 1,1525 400 1 1392 1,1510 1,1495 4,20 1,1371 1.1414 1 1456 4,40 11370 1,1316 1,1409 460 1.1354 1,1202 1,1350 480 11344 1,1093 1.1287 5,00 1,1336 1,1056 1,1200 5,20 1,1316 1,1005 1.1154 5,40 11272 1,0995 1.1177 5,80 1.1245 1,0930 1,1191 5,80 11320 10913 1.1352 6,00 1 1361 1,1027 11485 620 1,1444 11098 1,1599 6.40 11503 11162 11707 6,80 1 1533 1.1216 1,1777 6,80 1,1563 1,1261 11847 700 1,1568 1,1296 1,1876 7,20 11554 11339 11886 740 1.1555 1,1411 11817 760 11573 11488 1.1840 780 1.1580 11544 1,1790 8.00 1 1580 1.1599 11741 8.20 1.1561 11650 11683 8,40 11614 1 1700 11700 8.60 11687 11825 1.1745 6,80 11723 11913 1.1766 900 11747 12003 11778 920 11776 12170 11775 940 1 1792 12298 1 1780 980 11855 12402 1 1767 980 1 1947 12494 1.1529 1000 12067 12583 11939 10 20 12156 12690 12187 10 '0 12276 12769 12384 1080 12375 12867 12468 1050 12482 12887 12595 1100 12563 1 2829 12683 11 20 12456 12937 12671 1140 12694 13050 12545 11 SO 12506 1 3112 12257 1180 12455 13192 12149 1200 (core top) 12497 13383 12138 Note: W(Z) values at 20000 MWDIMTU may be applied to cycle burnups greater than 20000 MWDIMTU to prevent W(Z) functlon extrapolation 20000 MWDIMTU 13458 1,3415 13328 13262 13210 13158 1.3020 12948 12828 12728 12599 12443 1,2291 12114 1,1943 1,1171 1.1628 1.1617 1,1592 1,1600 1.1598 1,1578 1.1556 1,1638 1,1703 1 1746 1 1784 1,1817 11915 12090 1.2232 12346 12436 1.2490 12535 1.2530 1 2491 12436 12322 12199 12057 1.1876 1,1776 1.1778 1.1749 11722 1 1679 111185 1 1880 12209 12530 12852 13118 13436 13595 13705 13716 13540 13335 13338 13293
COLRBYRON2 Revision 4 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 Tabl. 2.S.2.b EOL-only W(2) va....... Core HeIght for AFO Acceptabl. Operation Llmlta In FIgure 2.8.1.b (Top and Bottom 8% Excluded per WCAP.l0218)
Height 18000 20000 25472 (reet)
MWOIMTU MWOIMTU MWO/MTU 0.00 (core bottom) 1.2161 1.2064 0.20 1.2056 1.2049 0.40 1.2020 1.1984 0.60 1.1984 1.1936 0.80 1.1837 1.1906 1.00 1.1772 1.1874 1.20 1.1680 1.1776 1.40 1.1640 1.1725 1.60 1.1576 1.1637 1.80 1.1521 1.1559 2.00 1.1462 1.1460 2.20 1.1372 1.1337 2.40 1.1275 1.1217 2.60 1.1213 1.1169 2.80
.1196 1.1139 3.00 1.1184 1.1138 3.20 1.1153 1.1118 3.40 1.1143 1.1105 3.60 1.1181 1.1168 3.80 1.1227 1.1253 4.00 1.1278 1.1341 4.20 1.1341 1.1457 4.40 1.1382 1.1547 4.60 1.1415 1.1638 4.80 1.1457 1.1703 5.00 1.1496 1.1746 5.20 1.1526 1.1784 5.40 1.1556 1.1817 5.60 1.1616 1.1915 5.80 1.1792 1.2090 6.00 1.1947 1.2232 6.20 1.2074 1.2346 6.40 1.2171 1.2438 6.60 1.2225 1.2490 6.80 1.2276 1.2535 7.00 1.2288 1.2530 7.20 1.2273 1.2497 7.40 1.2226 1.2438 7.60 1.2133 1.2322 780 1.2032 1.2199 8.00 1.1928 1.2057 8.20 1.1796 1.1876 8.40 1.1742 1.1776 8.60 1.1749 1.1776 8.00 1.1731 1.1749 9.00 1.1711 1.1722 9.20 1.1667 1.1679 9.40 1.1664 1.1685 9.60 1.1751 1.1860 9.80 1.1976 1.2209 10.00 12209 1.2530 10.20 12513 1.2852 10.40 1.2754 1.3118 10 50 1.2984 1.3436 10.80 13141 1.3595 11.00 1.3250 1.3705 11.20 1.3235 1.3716 1140 13053 1.3540 11.60 1.2789 1.3338 11.80 1.2739 1.3338 12.00 (core top) 1.2708 1.3293 Nota: W(Zl values at 20000 MlND/MTU may be applied to cycle bumups greater than 20000 MlND/MTU to prevent W(Zl function extrapolation 1.2064 1.2049 1.1984 1.1936 1.1906 1.1874 1.1776 1.1725 1.1637 1.1559 1.1460 1.1337 1.1217 1.1169 1.1139 1.1138 1.1118 1.1105 1.1168 1.1253 1.1341 1.1457 1.1547 1.1638 1.1703 1.1746 1.1784 1.1817 1.1915 1.2090 1.2232 1.2346 1.2436 1.2490 1.2535 1.2530 1.2497 1.2436 1.2322 1.2199 1.2057 1.1876 1.1776 1.1776 1.1749 1.1722 1.1679 1.1685 1.1860 12209 1.2530 12852 13118 1.3436 1.3595 1.3705 13716 13540 13335 1.3338 1.3293
Notes:
COLRBYRON2 Revision 4 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 Table 2.6.2.c Penalty Factors In Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor (MWD/Mru)
FC Q(z) 496 1.0200 841 1.0338 1014 1.0406 1187 1.0456 1360 1.0497 1532 1.0530 1705 1.0515 1878 1.0490 2051 1.0461 2224 1.0435 2396 1.0408 2915 1.0356 3087 1.0347 3260 1.0339 3433 1.0330 3606 1.0317 3779 1.0298 3951 1.0272 4470 1.0200 25472 1.0200 Linear interpolation is adequate for intermediate cycle burnups.
All cycle burn ups outside the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance ReqUirements.
COLRBYRON2 Revision 4 Page 100fl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN,.w (LCO 3.2.2) 2.7.1 FNilH ~ F~~P[1.0 + PFolH(1.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
~~P = 1.70 PF,~H = 0.3
2.7.2 Uncertainty
The uncertainty, UFilH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN olH shall be calculated by the following formula:
where:
UFdHm = Base FN,lH measurement uncertainty = 1.04 when PDMS is inoperable (UF!>Hm is defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
FN clH Warning Setpoint = 2% FN ilH Margin FN ilH Alarm Setpoint = 0% FN ilH 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 DNBRAPsl ~ 1.539 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
ex: w
~
0 a.
..J <<
- IE ex: w
- J:
0 w
~
0
- ('1 "
COLRBYRON2 Revision 4 Page II of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 120 100 80 60 40 20 o
Unacc Ope
(-3 I
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
(-15 100)
(+10, 00) eptabh V
\\
ation
/ V A,",cepta )Ie
\\
C perati( n
/
~, 50'
(+
I j,
Una Fcepta 0 ~eratio
\\
\\
25,5( >>)
I I
)Ie
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLRBYRON2 Revision 4 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 Figure 2.8.1.b:
Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup ~ 18000 MWD/MTU)
Axial Flux Difference Limits with PDMS Inoperable 120.---,----r---,---,,---.---,----r---.--~--~
(+10] 100)
I 100 -t--------
r--~---~-~--t-- ----- ------+------.
~
I W
I 3:
eptabl~
~ 80+-~~~fflr~--~~~----4----+--*~~~~~~--~
..J
<C
- !!l a::
~ 60+----+----~---Hr__4----4_--~----~~--~--_4--~
l-e W
I-
~ 40 o
20-L o +----r------------~----~--~----+---~--~--~
-50 40
-30
-20
-10 o
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLRBYRON2 Revision 4 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature tiT Setpoint Parameter Values 2.10.1 The Overtemperature tiT reactor trip setpoint Kl 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 T.vg at RTP (indicated) T' shall be less than or equal to 588.0 of.
2.10.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.
2.10.6 The measured reactor vessel tiT leadllag 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 ~ T 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 1:6 shall be less than or equal to 2 sec.
2.10.12 The fl (til) "positive" breakpoint shall be +10% ~1.
2.10.13 The fl (~I) "negative" breakpoint shall be -18% Ill.
2.10.14 The f1 (~I) "positive" slope shall be +3.47% / % ~I.
2.10.15 The f1 (~I) "negative" slope shall be -2.61 % / % Ill.
COLRBYRON2 Revision 4 Page 14 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower L\\ T Setpoint Parameter Values 2.11.1 The Overpower L\\ T reactor trip setpoint ~ shall be equal to 1.072.
2.11.2 The Overpower L\\ T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02/ of for increasing Tavg.
2.11.3 The Overpower L\\ T reactor trip setpoint Tavg ratellag coefficient Ks shall be equal to 0/ OF for decreasing Tavg.
2.11.4 The Overpower L\\ T reactor trip setpoint T.vg heatup coefficient Ks shall be equal to 0.00245/ of when T > T".
2.11.5 The Overpower L\\T reactor trip setpolnt Tavg heatup coefficient Ka shall be equal to 0 / OF when T:5 T".
2.11.6 The nominal T.vg at RTP (indicated) T" shall be less than or equal to 588.0 of 2.11.7 The measured reactor vessel L\\ T lead/lag time constant '1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel L\\ T lead/lag time constant '2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel L\\ 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 '6 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 (L\\I) "positive" breakpoint shall be 0 for all t.1.
2.11.13 The f2 (L\\I) "negative" breakpoint shall be 0 for all t.1.
2.11.14 The f2 (t.I) "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 4 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 17 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Soiling (DNS) 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 Soron 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 1737 2.13.2 a) prior to initial criticality 1787 2.13.2 b) all other times in life 2030