BW040094, Core Operating Limits Report, Cycle 12
| ML042950620 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/14/2004 |
| From: | Joyce T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW040094 | |
| Download: ML042950620 (20) | |
Text
Exeltkns Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 October 14, 2004 BW040094 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456
Subject:
Core Operating Limits Report, Braidwood Unit 1 Cycle 12 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 12, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR).' This revision of the COLR was recently implemented in support of a reload cycle.
If you have any questions regarding this matter, please contact Mr. Dale Ambler, Regulatory Assurance Managcr, at (815) 417-2800.
Respectfully, I..
T. P.
yce Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 1 Cycle 12 cc:
Regional Administrator-NRC Region III NRC Senior Resident Inspector - Braidwood Station 4JD
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1, Cycle 12
TRM TRM Control Program Appendix S ATTACHMENT C TECHNICAL REQUIREMENTS MANUAL CHANGE INSTRUCTION FORM FOR ONSITE/OFFSITE DISTRIBUTION AND FOR UPDATING EDMS Braidwood/Byron/Dresden/LaSalle/QC (circle one) TRM Revision # N/A NOTE: This change is effective as of entering MODE 6 in AIR11 and shall be implemented by 10/08/04.
(ITR/PORC or Amendment Implementation Date)
(Date)
I 2,S.
Approved for distribution:
Verified:
/
t1ol(
IOf (Date (RA LE Signature) iK7 t^
M
__ /a/IC (Date)
(RA LE Signature)
REMOVE REMOVE Section INSERT UPDATE EDMS l UPDATE EDMS
_Section I Page IPage Section I Page I
Unit 1 COLR CAD-03-89, Unit 1 COLR Revision 0 File xmitted to Update Rev. 1 Records appplicable TR4 (Cover sheet Management file in ENS (Pgs 1 and pgs. 1 through 17)
-through 16)
BRAIDWOOD UNITS 1 & 2 Technical Requirements Manual 12 of 14 Revision 13
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 12 (REVISION 0)
Revision 0 Page I of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 12 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 (Fa(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNA)
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 T TRM TLCO 3.1.b TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.1 TRM TLCO 3.1.J TRM TLCO 3.1.k echnical Requirements Manual affected by this report are listed below:
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 2 1.0 Shutdown Margin (SDM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)
Revision 0 Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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.
680 660 L..
EM..
i 620 4)
,_Cl 600 580 241 p\\sis\\
2 e
2 I
I I
2 t
2 I
t 2
Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
Revision 0 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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.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) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOIJARO/HZP-MTC upper limit shall be +1.335 x 10 5 Ak/k/F.
2.3.2 The EOIJARO/HFP-MTC lower limit shall be -4.6 x 104 Ak/k/0F.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k10F.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 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) 225 110 226 111 227 112 228 113 229 114
Revision 0 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 220 200 180 C3 160 w
I-
§ 140 120 C
0
-100 In 0
= 00 C 80
'U a 60 40 20 0
(27%, 224)
(77°/. 224) igg I IZ (7
/
(100%, 161) 162) 7 ANO-
=
=
I
/
I C
/()I I
=I
-=
i I
X I-7 I I
-=
0 10 20 30 40 50 60 70 Relative Power (Percent) 80 90 100
Revision 0 Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.6 Heat Flux Hot Channel Factor (FEQZ)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
QRTP FQ (Z) < 0.5 xK(Z) for P 5 0.5 FR1 FQ(Z) < Fp xK(Z) forP >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.
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 Figures 2.6.2.a through 2.6.2.d.
The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2 shows the Fca(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.
2.6.3 Uncertainty
The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula UFQ = Uq, *U, where:
Uq, = Base Fa measurement uncertainty = 1.05 when PDMS Is Inoperable (Uqu Is defined by PDMS when OPERABLE.)
U6 = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
Fa(Z) Warning Setpoint 2 2% of F0(Z) Margin F0(Z) Alarm Setpoint 2 0% of Fa(Z) Margin
Revision 0 Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.6.1 K(Z) - Normalized F0(Z) as a Function of Core Height IL Na 0
2
.U (0.0 1.0)
(6.0,1.0) 0.9 0.8 0.7-
0.6 0.5 0.4-----
_-4LOCA Limiting 0.4 Envelope_
0.3 0.2 -
0.1 0--
,0.924) 0 1
BOTTOM 2
3 4
5 6
7 Core Height (ft) 8 9
10 11 12 TOP
Revision 0 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 120 1A0 1.60 1.80 2.00 220 2.40 2.60 2.80 3.00 3.20 3A0 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11A0 11.60 11.80 12.00 MAX W(Z) l.0000 1.0000 1.0000 1.0DDO 1.0000 1.0000 1.0000 1.0000 1.0000 1.1868 1.1696 1.1535 1.1512 1.1463 1.1432 1.1391 1.1334 1.1293 1.1237 1.1188 1.1188 1.1199 1.1201 1.1194 1.1177 1.1161 1.1127 1.1149 1.1206 I.1335 1.1482 1.1609 1.1726 1.1824 1.1902 1.1983 1.2049 12089 112104 1.2094 1.2050 1.1974 1.1913 1.1957 1.2043 1.2130 1.2320 12490 1.2620 12760 1.2890 12996 2.0000 1.0000 1.0000 I.0000 1.0000 1.0000 1.0000 I.0000 1.0000 Braldwood Unit 1 Cycle 12 Figure 2.62.a Summary of W(Z) Function at 150 MWD/MTU (Top and Bottom 15% Excluded per WCAP-10216) 1.35 4 :,:
1.30 1.25 I I I I 1 -
I
= 1.20-111 10 1.15 N
0.00 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET) 10.00 12.00
Revision 0 Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height Feet 0.00 020 0.40 0.60 0.80 1.00 120 1.40 1.60 1.80 2.00 2.20 2.40 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11A0 11.60 11.80 12.00 MAX W(Z) 1.0000 1.0000 1.0000 1.0000 1.0000 I.0000 1.0000 1.0000 1.0000 1.2081 1.1920 1.1719 1.1559 1.1388 1.1260 1.1248 1.1217 1.1195 1.1201 1.1230 1.1257 1.1273 1.1289 1.1283 1.1279 1.1265 1.1237 1.1203 1.1167 1.1124 1.1070 1.1099 1.1266 1.1433 1.1599 1.1738 1.1876 1.1995 1.2086 1.2176 1.2247 1.2298 1.2368 1.2431 1.2536 1.2659 1.2787 1.2913 1.3035 1.3150 1.3230 1.3277 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Braidwood Unit 1 Cycle 12 Figure 2.62.b Summary of W(Z) Function at 6000 MWDIMTU (Top and Bottom 15% Excluded per WCAP-10216) 1.35 1.30 1.25 z
z 1.20 IL 1.15 1.10 1.05 ii+ i+ +F ii i W i ii l l l l l l _
I I ;
l l I X X X X,' t- _ t_
ffl ffl e X f ffl X t X ++
l l
_ l l I I e e tH e te f f WW'WX _ X TT
_ 7 l
4 X 44-t X 0.00 2.00 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET)
Revision 0 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 1A0 1.60 1.80 2.00 2.20 2A0 2.60 2.80 3.00 3.20 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11A0 11.60 11.80 12.00 MAX W(Z)
L.OD00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3044 1.2883 1.2661 1.2490 1.2290 1.2191 1.2075 1.1943 1.1880 1.1812 1.1742 1.1664 1.1577 1.1489 1.1391 1.1301 1.1203 1.1098 1.1082 1.1145 1.1274 1.1395 1.1495 1.1586 1.1658 1.1712 1.1755 1.1781 1.1787 1.1774 1.1764 1.1734 1.1676 1.1638 1.1645 1.1658 1.1662 1.1638 1.1633 1.1656 1.1698 1.1739 1.1790 1.0D00 1.0000
.OD00 I.OD00 1.0000
.OD00 I.D000 I.D000 1.0000 Braidwood Unit 1 Cycle 12 Figure 2.62.c Summary of W(Z) Function at 14000 MWD/MTU (Top and Bottom 15% Excluded per WCAP-10216) 1.40 1.35 1.30 2 1.25 z
Iz 3 1.20 1.15 1.10 1.05 0.00 2.00 4.00 6.00 8.00 10.00 12.00 CORE HEIGHT (FEET)
Revision 0 Page IO of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height Feet 0.00 0.20 0.40 0.60 0.80 1.00 120 1.40 1.60 1.80 2.00 220 2.40 2.60 2.80 3.00 320 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 5.00 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 MAX W(Z) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2835 1.2693 1.2531 1.2378 1.2196 1.2023 1.1850 1.1846 1.1866 1.1864 1.1865 1.1845 1.1814 1.1772 1.1707 1.1675 1.1726 1.1767 1.1802 1.1889 1.2040 1.2181 1.2281 1.2372 1.2414 1.2457 1.2464 1.2431 1.2383 1.2304 1.2211 1.2107 1.1958 1.1819 1.1667 1.1653 1.1649 1.1619 1.1607 1.1730 12090 1.2420 1.2730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Braidwood Unit I Cycle 12 Figure 2.62.d Summary of W(Z) Function at 20000 MWD/ITU (Top and Bottom 1t5% Excluded per WCAP-1 0216) 1.35 1.30 1.25 z0 z
1.20 1.15 1.10
- 1:.:
- ii44...
.4.
---1I 1.05 0.00 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET) 10.00 12.00
Revision 0 Page 11 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penaylt Factor (MWD/MTU)
F(z) 668 1.0200 841 1.0229 1013 1.0271 1186 1.0300 1359 1.0311 1877 1.0325 2395 1.0314 2567 1.0310 2740 1.0307 3258 1.0303 3431 1.0298 3776 1.0273 3949 1.0250 4121 1.0220 4294 1.0200 14136 1.0200 14309 1.0203 14481 1.0205 14654 1.0203 14827 1.0200 Notes:
Linear interpolation Is adequate for intermediate cycle burnups.
All cycle burnups outside the range of the table shall use a 2% decrease in F 0 margin for compliance with the 3.2.1.2 Surveillance Requirements.
Revision 0 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7.1 F AH
- F2H '[1.0 + PFAH(1.0 - P)A where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F,=THP 1.70 PFAH=0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNAH shall be calculated by the following formula:
UFAH = UFAHm where:
UidHm = Base FN measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNAH Warning Setpoint 2 2% of FNAH Margin FNAlH Alarm Setpoint 2 0% of F NAH 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 2 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER 2 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint 2 2% of DNBR Margin DNBR Alarm Setpoint 2 0% of DNBR Margin
Revision 0 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 100 w
0 0
IL
-J 2
a:
0 80 60 40 20 0 40 20 -10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
Revision 0 Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.10 Reactor Trio System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K, 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 0.00181 /psi.
2.10.4 The nominal Tayg at RTP (indicated) T' shall be less than or equal to 588.0 OF.
2.10.5 The nominal RCS operating pressure (indicated) F" 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 leadAag time constant x2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT 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 X4 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 16 shall be less than or equal to 2 sec.
2.10.12 The fI (Al) "positive" breakpoint shall be +10% Al.
2.10.13 The f, (Al) 'negative" breakpoint shall be -18% Al.
2.10.14 The fI (Al) 'positive" slope shall be +3.47% I % Al.
2.10.15 The f, (Al) 'negative" slope shall be -2.61%%
Al.
Revision 0 Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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 Tang rate/lag coefficient K5 shall be equal to 0.02/ 'F for increasing T8 g.
2.11.3 The Overpower AT reactor trip setpoint Tang rate/lag coefficient K5 shall be equal to 0 / 'F for decreasing Ta,.
2.11.4 The Overpower AT reactor trip setpoint Tang heatup coefficient Kr shall be equal to 0.00245/ 'F when T > T".
2.11.5 The Overpower AT reactor trip setpoint T8,, heatup coefficient Kc6 shall be equal to 0/'FwhenT*T".
2.11.6 The nominal Tag at RTP (indicated) To shall be less than or equal to 588.0 OF 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 x2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant X3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant X6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant r7 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.
Revision 0 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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 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 1781 2.13.2 a) prior to Initial criticality 1871 2.13.2 b) all other times In core life 2066