ML081270304
| ML081270304 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/06/2008 |
| From: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW080047 | |
| Download: ML081270304 (15) | |
Text
Exe~n May 6. 2008 8W080047 U~S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Core Operating Limits Report, Braidwood Unit 2 Cycle 14 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 14, in accordance with Technical Specification 5~6.5,Core Operating Limits Report (COLR)~Braidwood Unit 2 Cycle 14 COLR, Revision 3 was implemented during Braidwood Unit 2 Refueling Outage 13 in support of Cycle 14 operation. Note that Revision 3 is the original version of the Braidwood Unit 2 Cycle 14 COLR implemented in support of Cycle 14 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 2 COLR, Le~,Braidwood Unit 2 Cycle 13 COLR, Revision 2.
If you have any questions regarding this matter, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Bryan Hanson Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 14, Revision 3
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 2 Cycle 14 Revision 3
COLR BRAIDWOOD 2 Revision 3 Page I of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 14 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 (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 (F~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 (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 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 1 and MODE 2 with keff 1.0 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 BRAIDWOOD 2 Revision 3 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 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) 21.1 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.
680 660 .s~_____
2250 psia ----.-~--*---.--
Lj
~
640 ._~
2000 ia
~
ji~ 620 600
~
I I 580 I I I I I I) .2 .6 .8 .2 Fraction of Nomina Power Figure 2.1.1: Reactor Core Limits
Exe~n May 6. 2008 8W080047 U~S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Core Operating Limits Report, Braidwood Unit 2 Cycle 14 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 14, in accordance with Technical Specification 5~6.5,Core Operating Limits Report (COLR)~Braidwood Unit 2 Cycle 14 COLR, Revision 3 was implemented during Braidwood Unit 2 Refueling Outage 13 in support of Cycle 14 operation. Note that Revision 3 is the original version of the Braidwood Unit 2 Cycle 14 COLR implemented in support of Cycle 14 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 2 COLR, Le~,Braidwood Unit 2 Cycle 13 COLR, Revision 2.
If you have any questions regarding this matter, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Bryan Hanson Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 14, Revision 3
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 2 Cycle 14 Revision 3
COLR BRAIDWOOD 2 Revision 3 Page I of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 14 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 (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 (F~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 (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 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 1 and MODE 2 with keff 1.0 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 BRAIDWOOD 2 Revision 3 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 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) 21.1 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.
680 660 .s~_____
2250 psia ----.-~--*---.--
Lj
~
640 ._~
2000 ia
~
ji~ 620 600
~
I I 580 I I I I I I) .2 .6 .8 .2 Fraction of Nomina Power Figure 2.1.1: Reactor Core Limits
COLR BRAIDWOOD 2 Revision 3 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 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; 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 5DM 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) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +0.608 x iO5 Ak/k/F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10~Ak/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10~Ak/k/°F.
2.3.4 The EOLIARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10~Ak/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) 226 111 227 112 228 113 229 114
COLR BRAIDWOOD 2 Revision 3 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 Figure 23.1:
Control Bank Insertion Umits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 200 180
~160 (100%, 161) 1140 120 0
~100 In 0
C 0
&60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 RelatIve Power (Percent)
COLR BRA1DWOOD 2 Revision 3 Page 5 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 2,6 Heat Flux Hot Channel Factor (FQ~fl(LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ(Z) 9--xK(Z) forP~0.5 FRTP FQ(Z) ~xK(Z) forP>0.5 where: P the ratio of THERMAL POWER to RATED THERMAL POWER F~T~= 2.60 K(Z) is provided in Figure 2.6.1.
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 in Table 2.6.2.a.
The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2.b shows the F°0(z)penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the F~0(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.b.
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor F~(Z)shall be calculated by the following formula Urn = Uq~* U~.
where:
Uqu = Base F0 measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)
U8 = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
F0(Z) Warning Setpoint 2% of F0(Z) Margin F0(Z) Alarm Setpoint 0% of F0(Z) Margin
COLR BRAIDWOOD 2 Revision 3 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 Figure 2.61 K(Z) Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0 1.0) 1 8~
12 0.924) 0.9 0.8 i;:i 0.7 a
~0.6 40.5 ~*~LOCA Limiting
~ 0.4 Envelope 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 101112 BOTTOM Core Height (ft) TOP
COLR BRAIDWOOD 2 Revision 3 Page 7 of 13 CORE OPERATING LIMiTS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 Table 2 ,6.2.a W(Z~versus Core Hei~t T
( op and Bottom 8%E~luded per WC4P..10216)
Hekjht 150 0000 13000 20000 feet) MWD Mlii bWVD Mlii bYM) MTh MWDMlU 0,00~corabo8om~ 12405 15715 1.4215 12314 0 20 1 .3360 1 5244 1 3908 1 3237 0.40 1.3292 .4961 1.3772 12258 020 1.3218 4788 1.3619 12211 020 1.3101 14523 1.3400 13166 100 1:3008 .4292 1.3273 12111 120 1.2911 2.902 13048 12017 1.40 1.2805 13736 1.2903 12931 120 1.2739 12458 12733 12750 1 20 1 .2849 1 2245 1 2580 1 2626 200 12702 12015 12459 12484 220 .2506 12729 2319 12332 2.40 .2349 12500 .2186 12179 280 .2143 12327 .2037 11997 220 .1988 12225 1900 1.1861 300 .1822 12140 1770 1.1714 320 .1768 12086 .1620 1.1540 3.40 .1745 12033 .1527 1.1560 320 1.1708 1.1959 1.1510 1.1596 320 1.1665 1.1895 1.1488 1.1624 400 .1617 1.1821 1.1460 11633 420 .1551 1.1716 1.1423 1.1636 4.40 .1520 1,1631 1.1376 1.1642 420 1.1527 1.1515 1.1314 1.1784 420 1.1535 1.1410 1.1278 1.1915 500 1.1531 1.1294 1.1291 12023 520 1.1506 1.1168 1.1320 12101 5.40 1.1421 1.1042 1.1358 12168 5.60 1.1445 10895 1.1403 12297 520 1.1398 10929 1.1586 12505 600 1.1474 1.1031 1.1753 12685 820 1,1541 1.1127 1.1889 12829 6.40 1.1588 1.1212 1.2015 12940 6.60 1.1625 1.1294 12112 13004 620 1.1642 1.1353 12179 13042 700 1.1651 1.1402 1.2236 12051 20 1.1639 1.1433 1.2255 12006 7.40 1.1639 1.1453 1.2263 12953 720 1.1634 1.1445 1.2223 12844 20 1.1647 1.1417 1.2192 12736 800 1.1650 1.1379 1.2133 12611 820 1.1633 1.1338 1,2044 1243$
8.40 1.1617 11309 1.1945 12258 850 1.1585 1.1270 1.1836 12049 820 1.1566 1.1369 1.1736 12032 900 1.1661 1.1478 1.1712 12013 920 1.1774 1.1687 1.1722 1.1992 9.40 1.1012 1.1075 1.1728 12179 950 1.1824 12059 1.1740 12556 920 1.1860 12133 1.1873 12903 10.00 1.1868 12187 1.2180 13229 10.20 1.1872 12226 1.2487 13406 10.49 1.1879 12361 1.2674 12763 10.60 1.2089 12482 1.2842 13941 10.80 1.2196 12599 1.2989 14119 11.00 1.2148 1279$ 1.3097 1.4237 11.20 1.2210 12960 1.3097 1.4296 11.40 1.2414 12148 1.3095 14254 1 .60 1.2439 12179 1.2965 14193 11.8$ 1.2486 13242 1,2874 14103 12.00 (core top) 1.2590 13444 1,2842 1.4081 Hote W(Z) values at 20000 MWD2VITU may be applied to c de burnups greater than 1
20000 MWDIMTU to prevent W(Z) 6.inction e>trapolation
COLR BRAIDWOOD 2 Revision 3 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 Table 2,6.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FC0(z) 150 , 1.020 668 1.044 841 . 1.050 1013 1.056 1186 1.061 1359 1.064 1531 1.062 1704 1.056 2049 , 1.045 2913 1.023 3085 A 1.020 A ~ :~
17245 1.020 17590 , 1.025 17763 1.027 17935 1.027 18108 , , 1.027 18453 1.027 18626 1.027 18799 1.025 19317 1.020 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 BRAIDWOOD 2 Revision 3 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN~ (LCO 3.2.2) 2.7.1 F~H~F~~[1.0 + PF\H(1.0 - P)}
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FRTP PF\H = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UF,3H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN.\H shall be calculated by the following formula:
UFAH = UF,\Hm where:
UF,,~Hm= Base FN,\H measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FN H Warning Setpoint 2% of FN,.\H Margin 3
FNAH Alarm Setpoint 0% of 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 Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
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 1.536 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% of DNBR Margin DNBR Alarm Setpoint 0% of DNBR Margin
COLR BRAIDWOOD 2 Revision 3 Page 10 of 13 CORE OPERATING LIMiTS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with POMS Inoperable 120
(-15, 100) (+10, 100)
LU 100 Unacceptable r~:~\ Unacceptable 0 80 ~lo// \\Pe~tIon
-J LU I 60 I-LU I
a:: 40 .~ ~.. (~2~5.~5O~
0 20 0
40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 2 Revision 3 Page II of 13 CORE OPERATING LIMITS REPORT (COLR) for BRA1DWOOD UNIT 2 CYCLE 14 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 T8~9coefficient K, shall be equal to 0.0297 / ~F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal T8~9at 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 t~ shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant ~2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant t3shall 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 t~shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant t~ be less than or equal to 2 sec.
2.10.12 The f1 (Al) 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% / % Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% / % Al.
COLR BRAIDWOOD 2 Revision 3 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 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 K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint T~~ rate/lag 9 coefficient K5 shall be equal to 0.02 / °Ffor increasing T0~9 2.11.3 The Overpower AT reactor trip setpoint Ta89 rate/lag coefficient K5 shall be equal to 0 / F for decreasing T889 2.11.4 The Overpower AT reactor trip setpoint T889 heatup coefficient K8 shall be equal to 0.00245/FwhenT>T.
2.11.5 The Overpower AT reactor trip setpoint T8,,9 heatup coefficient K6 shall be equal to 0 / F when T ~ T.
2.11.6 The nominal T889 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 t1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant t3shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant t~ shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant t 7
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 BRAIDWOOD 2 Revision 3 Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 14 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 (T889) 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 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 Canditicits Baton Caucentiation iOt ~
2.13.1 Refueling 1633 2.13.2 a) prior to initial criticality 1661 2.13.2 b) all other times in life 1919