ML050880402
| ML050880402 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/23/2005 |
| From: | Polson K Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW050029 | |
| Download: ML050880402 (18) | |
Text
Exelon Generation Company, LLC www.exeloncorp.com Exelkrn. Nuclea Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL60407-9619 March 23,2005 BW050029 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, Revision 1 The purpose of this letter is to transmit a recent revision to 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 revises a Note in Table 2.6.2, "Penalty Factors in Excess of 2% per 31 EFPD." The Note regarding penalties applied to values outside the range of the Table was incorrectly specified in the original issuance of the Braidwood Unit 1 Cycle 12 COLR. The Note requires revision for clarity and consistency with the Best Estimate Analyzer for Core Operations Nuclear (BEACON) methodology.
If you have any questions regarding this matter, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.
Sincerely, Keith . Polson Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 1 Cycle 12, Revision 1 cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station
,,9M
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1, Cycle 12 Revision 1
Revision I 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 (Fo(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)
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 (SDM) - MODE 1 and MODE 2 with keff 2 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)
Revision I 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.
668 2471 ipsa 661 071 L..
- M 225 psik, _
60 E
6 20
'9 C,
0 PS\
L_.
580 600 5 80 2
Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
Revision I 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.J and 3.1.j).
2.3 Moderator Temrerature 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 +1.335 x 10'5 Ak/k/OF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 104 Ak/k/OF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/OF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 Ak/k/rF.
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) l 225 110 226 111 i
227 112 228 113 229 114
Revision I Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Figure 2.5.1:
Control Bank Insertion Linits Versus Percent Rated Thermal Power 224 (27%, 224) (770/, 224) 220 200 180 C
¢ 160 , a*- L ,(100%A161) la
- 140 0
M 0.
~120 C
0
--con100 0
0.
C 80 40 MO60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
Revision I Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.6 Heat Flux Hot Channel Factor (F(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FRTP FQ (Z) < 0-5 xK(Z) for P < 0.5 FRTP FQ(Z) < p xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FoTP = 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 Fo(Z) shall be calculated by the following formula UFQ = Uqu
- U.
where:
Uqu = Base Fo 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:
F0 (Z) Warning Setpoint 2 2% of Fo(Z) Margin FQ(Z) Alarm Setpoint 2 0% of Fo(Z) Margin
Revision I 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 N
a U.
'a a
0 2
N:A 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
Revision I Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)
Feet Braidwood Unit 1 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.a 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 150 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.A0 1.0000 1.60 1.0000 1.80 1.1868 2.00 1.1696
.2.20 1.1535
.2.40 1.1512
' 2.60 1.1463 2.80 1.1432 3.00 1.1391 3.20 1.1334 3.40 1.1293 3.60 1.1237 3.80 1.1188 4.00 1.1188 420 1.1199 4.40 1.1201 4.60 1.1194 4.80 1.1177 5.00 1.1161 2520 1.1127 I .
5.40 1.1149 5.60 5.80 1.1206 1.1335 I.I 6.00 1.1482
.620 1.1609 I I
,6.40 1.1726
,6.60 1.1824 6.80 1.1902 7.00 1.1983 720 1.2049 II 7.40 1.2089 7.60 1.2104 7.80 1.2094 8.00 1.2050 8.20 . 1.1974 8.40 1.1913 8.60 8.80 9.00 920 9.40 1.1957 1.2043 1.2130 1.2320 1.2490 I
9.60 1.2620 9.80 1.2760 10.00 1.2890 10.20 1.2996 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1120 1.0000 11.A0 1.0000 11.60 1.0000 11.80 1.0000 12.00 1.0000
Revision I Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)
Feet Braidwood Unit I Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.b 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 6000 MWDIATU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP 10216) 1.00 1.0000
- 120 1A0 1.0000 1.60 1.0000 1.35 1.80 1.2081
.2.00 1.1920
- 220 1.1719
- 2.40 1.1559 2.60 1.1388 2.80 1.1260 3.00 1.1248 320 1.1217 1.30 3.40 1.1195 3.60 1.1201 3.80 1.1230 4.00 1.1257 420 1.1273 4.40 1.1289 4.60 1.1283 4.80 1.1279 1.25 5.00 1.1265
- 520 1.1237 5.40 1.1203 5.60 1.1167 5.80 1.1124 6.00 1.1070 6.20 1,1099 1.20 6.40 1.1266 E 6.60 1.1433 6.80 1.1599 7.00 1.1738 720 1.1876 7.40 1.1995 7.60 1.2086 7.80 1.2176 1.15 8.00 1.2247 820 1.2298 8.40 1.2368 8.60 1.243 1 8.80 1.2536 9.00 1.2659 9.20 1.2787 ' 1.10 9.40 1.2913 9.60 1.3035 9.80 1.3150 10.00 1.3230 1020 1.3277 10.40 1.0000 10.60 1.0000 10.80 1.0000 1.05 L..
11.00 1.0090 0.00 2.00 4.00 6.00 8.00 10.00 12.00 1120 1.0000 11.40 1.00D0 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 12.00 1.0000
Revision I Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)
Feet Braidwood Unit 1Cycle 12 0.00 1.0DO0 0.20 1.0000 Figure 2.62.c 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 14000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 120 1.0000 1.40 1.0000 1.60 1.0000 1.40 1.80 1.3044 2.00 1.2883 2.20 1.2661 2.40 1.2490 2.60 1.2290 2.80 1.2191 3.00 1.2075 1.35 3.20 1.1943 3AO 1.1880 3.60 1.1812 3.80 1.1742 4.00 1.1664 4.20 1.1577 1.1489 1.30 4.40 4.60 1.1391 4.80 1.1301 5.00 1.1203 520 1.1098 5.40 1.1082 5.60 1.1145 1.25 5.80 1.1274 z0 6.00 1.1395 620 1.1495 6.40 1.1586 FT 6.60 1.1658 6.80 1.1712 z: 1.20 7.00 1.1755 720 1.1782 7.40 1.1787 7.60 1.1774 7.80 1.1764 8.00 1.1734 820 1.1676 8.40 1.1638 1.15 8.60 1.1645 8.80 1.1658 9.00 1.1662 920 1.1638 9.40 1.1633 9.60 1.1656 1.10 9.80 1.1698 10.00 1.1739 10.20 1.1790 10A0 1.000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 Lj 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000
Revision I { Page IO of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 Height MAX W(Z)
Feet
- Braidwood Unit 1 Cyde 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.d 0.40 2.0000 0.60 1.0000 Summary of W(Z) Function at 20000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-1 0216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.80 1.2835 2.00 1.2693 2.20 1.2531 2.40 1.2378 2.60 1.2196 2.80 1.2023 3.00 1.1850 320 1.1846 3.40 1.1866 3.60 2.1864 3.80 I.1865 4.00 1.1845 420 1.1814 4.40 1.1772 4.60 1.1707 I 4.80 1.1675 I 5.00 1.1726 5.20 1.1767 5.40 I .1802 5.60 1.1889 5.80 1.2040 6.00 12.181 620 1.2281 I I 6A0 1.2372 6.60 1.2414 6.80 1.2457 7.00 1.2464 7.20 1.2431 7A0 1.2383 7.60 7.80 8.00 8.20 8.40 1.2304 1.2211 1.2107 1.1958 1.1819 t I 8.60 1.1667 8.80 1.1653 9.00 1.1649 9.20 I .1619 9A0 1.1607 9.60 1.1730 9.80 1.2090 10.00 1.2420 10.20 1.2730 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 11.20 1.0000 11A0 1.0000 11.60 1.0000 11.80 1.0000 12.00 1.0000
Revision I Page II 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 PenaIt Factor (MWD/MTU) Fo(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 bumups outside the range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
Revision I Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 2.7 Nuclear Enthaloy Rise Hot Channel Factor (FN4 H) (LCO 3.2.2) 2.7.1 FIS H<FRP[1 .0+ PFAH(1.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FaH= 1.70 PFH =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:
QUH= , Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
F'aH Warning Setpoint 2 2% of FNAH Margin FNAH Alarm Setpoint 2 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 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 Ž 0% of DNBR Margin
Revision I 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
(-1 ,10 ) +10, 100 1 100 Unac epta le Unacceptable
- 0 80 p t __ __ -\- 0 peration-
- a.
A ctble
_ =2 / _Operat on db I- 60 a
LI-
- l l 40 35, -(
0 Z10 20 0 r-
- - - - -I 40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
Revision I Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 12 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 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 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 Tr 1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant T,2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant s3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/ag time constant r4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant 5shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant r6 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 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 f, (Al) "negative" slope shall be -2.61 %% Al.
Revision I 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 Tavg rate/lag coefficient K5 shall be equal to 0.02/ 'IF for increasing Teyg.
2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0/ OF for decreasing Tag.
2.11.4 The Overpower AT reactor trip setpoint Tayg heatup coefficient K6 shall be equal to 0.00245/ 'F when T > T.
2.11.5 The Overpower AT reactor trip setpoint Tayg heatup coefficient K6 shall be equal to 0/'Fwhen T<T".
2.11.6 The nominal Tavg 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 A 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 T3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant T6 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 (AI) "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 I 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 3.1.9 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