ML051310163
| ML051310163 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/04/2005 |
| From: | Polson K Exelon Generation Co, Exelon Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW050041 | |
| Download: ML051310163 (18) | |
Text
"5 , *Exeicbm Exelon Generation Company. LLC Braidwood Station www.exeloncorp.com Ex 1 1 Nuclear 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 May 4, 2005 BW050041 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 12 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 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 Manager, at (815) 417-2800.
Sincerely,
)<xS Keith olson Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 12 cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 2, Cycle 12
It Revision 0 Page 1 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 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 Umits (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 (FNH)
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 i and MODE 2 with keff 2 1.0 TRM TLCO 3.1.1 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 o Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 _ _ _ _
.2471 pim 6LL<
.580 640 Frac~onof Nom."inaloe Figure 2.1.1: Reactor Core Limits
Revision 0 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 3.1.1 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 +1.28 x 10- Ak0kPAF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 104 Ak/k/0 F.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/ 0F.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 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 Ufe 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 Llmit (step) 225 110 226 111 227 112 228 113 229 114
I Revision 0 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Figure 2.5.1:
Control Bank Insertion Umits Versus Percent Rated Thermal Power 224 220 200 180 3 (100%/6 161) 160 4-140 0.
120 0
CL a)
Cn 0~
100 0
0 0
80 60 40 20 0*
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
Revision 0 Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 2.6 Heat Flux Hot Channel Factor (FiZ (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FRTP FQ(Z)
- Q xK(Z) forP<0.5 0.5 Fw FQ(Z) < xK(Z) for P>0.5 P
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER Fa = 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 bumups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2 shows the Fco(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 UFO = U,,
- U, where:
Uw = Base Fo measurement uncertainty = 1.05 when PDMS is inoperable (Uq Is defined by PDMS when OPERABLE.)
U0 = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
Fa(Z) Warning Setpoint 2 2% of Fa(Z) Margin FO(Z) Alarm Setpoint 2 0% of Fa(Z) Margin
Revision 0 Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Figure 2.6.1 K(Z) - Normalized F0 (Z) as a Function of Core Height 1.1 l(Io.01.)
11(6 I I Il (6.01.0) I I I I 14 I I I 1 (12.1,0.924) 0.9 0.8 E- 0.7 ILe N
0.6 E
0" 0.5 Z'0.
0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
I Revision 0 Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Height MAX W(Z)
Feet Briadwood Unit 2 Cycle 12 0.00 1.0000 0.20 I00D" 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-1 0216) 1.00 1.0000 120 I.0D0 1.40 I0000
.1 1.60 1D0000 1.80 12639 2.00 12467 2.20 12262 I 2.40 12077 2.60 1.1870 2.80 1.1675 D00 1.1540 3.20 3.40 3.60 1.1432 1.1405 1.1376 I1 I
II 1.1348 I
3.80 4.00 1.1362 I 4.20 1.1355 II 4.40 1.1357 4.60 1.1342 4.80 1.1324 5.00 1.1297 5.20 1.1248 5.40 1.1201 5.60 1.1199 5.80 1.1301 6.00 1.1477 6.20 1.1643 6.40 1.1790 6.60 1.1927 6.80 12046 I I I; I I1 7.00 12157 7.20 12247 7A0 7.60 12321 12366 II I
7.80 12413 8.00 12450 8.20 12452 _.1 8.40 12453 I 8.60 12428 8.80 12373 9.00 12363 9.20 12362 9.40 12400 9.60 12376 9.80 12374 10.00 12361 1020 12307 1OAO 1.0000 10.60 1.000D 1080 1.0000 1 1.00 1.0000 1120 1000 11AO 1.0000 11.60 1.000D 11.80 1.0000 12.00 1.0000
Revision 0 Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Height MAX W(Z)
Feet Briadwood UNt 2 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.62.b 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 6000 MWWDIMTU 0.80 IDO0O (Top and Bottom 15% Excluded per WCAP-1 0216) 1.00 1.0000 120 1.0000 10AO 1.0000 1.60 1.0000 12119 1.40
\ I I I I I 1 1_ll I I 1 1_1 1 1 m I I 1.80 2.00 1,1973 Tr l l l X1 @e T 0 I I I l l l I Tl I
!1-1 1ITfflfflt t1 2.20 1.1764 2.40 1.1642 2.60 2.80 3.00 1.1598 1.1549 1.1501 1.35 j
3.20 1.1433 3.40 1.1365 3.60 1.1287 3.80 1.1215 t t t fflrrEl2f lf 4.00 4.20 1.1188 1.1149 1.30 7 I T 17 7 Tr t 8 r 11 7 1 1 l l l 4.40 1.1117
____ _tA- __t _t X _
4.60 1.1065 4.80 1.1013 5.00 1.0966 5.20 5.40 1.0898 1.0937
__ __ __ __ __ + W _ _ _ + _ X X H:
5.60 5.80 1.0990 1.1064 z 1.25 IT _ 1I - I l 6.00 6.20 6.40 1.1132 1.1244 1.1392 0
z fF XX + + X H 6.60 6.80 7.00 1.1529 1.1647 1.1766 E
1.20 iEE TW ++ X X 7.20 7AO 1.1835 1.1926 H ' f H +; X H 7.60 7.80 8.00 8.20 12014 12086 12132 12153 CEE I I X i I X X _
f XL
+
-fL X e
_ I I H 11 1.15 8.40 12147 12165 t-- t-ttt-tt-8.60 8.80 12260 9.00 1.2510 9.20 12760 9.40 12980 tC I _ T _. - -I 1- I I _
71 I_ A _ l l _ I I TZ _
9.60 13170 1.10 9.80 10.00 10.20 10.40 10.60 13370 13570 13710 1.0000 1.0000 4 q ij 4 TTI 4 4 1080 1.OODO 11.00 l.0000 1.05 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 1120 11.40 I.0000 CORE HEIGHT (FEET) 11.60 l.0000 11.O 1.0000 12.00 1.0000
Revision 0 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Height MAX W(Z)
Feet Briadwood Unit 2 Cycle 12 0.00 1.0000 0.20 1.0000 Figure 2.6.2.c 0.40 1)0000 0.60 1.0000 Summary of W(Z) Furction at 14000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1AO 1.0000 1.60 1.0000
) HXXlIE 1.40 1.80 12899 2.00 12730 2.20 12447 2.40 1225S 2.60 1.2100 2.80 1.1995 3.00 1.1890 1.35 3.20 1.1782 3.40 1.1684 3.60 1.1568 3.80 1.1520 4.00 1.1486 4.20 1.1443 1.30 4.40 1.1390 4.60 1.1318 4.80 1.1358 Ci Xffl4 M 5.00 1.1386 5.20 1.1394 -1 111ff :~
5.40 1.1398 5.60 1.1403 1.25 5.80 1.1392 I -s- 4X 6.00 1.1528 6.20 6.40 6.60 6.80 1.1655 1.1761 1.1838 1.1896 1___ r1 11 7.00 1.1934 1.20 7.20 1.1943 7.40 1.1941 7.60 1.1921 7.80 1.1900 8.00 1.1869 8.20 I.1820 1.15 8.40 1.1741 8.60 1.1737 8.80 1.1746 9.00 1.1743 9.20 1.1728 9.40 1.1715 9.60 1.1770 1.10 9.80 12130 10.00 12460 10.20 1.2770 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 11.20 L.000O 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11A0 1.0000 11.60 CORE HEIGHT (FEET) 1.0000 11.80 1.0000 12.00 1.0000
Revision 0 Page 10 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Height MAX W(Z)
Feet Briadwood Unit 2 Cycle 12 0.00 1.eo 0.20 1.0000 Figure 2.6.2.d 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 20000 MWDIMTU 0.80 I1O0 (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 1.40 1.80 1.2510 I I I i 2.00 1.2365 2.20 12236 2.40 12122 2.60 1.1974 2.80 1.1851 3.00 1.1740 1.35 3.20 1.1700 3.40 1.1690 3.60 1.1670 3.80 1.1643 4.00 1.1732 4.20 1.1800 1.30 4.40 1.1871 4.60 1.1967 4.80 1.2054 5.00 12110 5.20 12145 5.40 12175 5.60 12170 Z 1.25 - -.- - L 5.80 12181 0 6.00 1.2316 6.20 1.2421 6.40 6.60 1.2498 1.2534 6.80 1.2561 1.2564 B 1.20 7.00 7.20 7.40 1.2548 12519
- -L t -
7.60 12443 7.80 12357 8.00 12260 8.20 12122 1.15 8.40 1.1985 8.60 1.1827 8.80 1.1697 9.00 1.1687 9.20 1.1748 9.40 1.1911 9.60 1.2336 1.10 9.80 1.2711 10.00 1.3056 I
10.20 13353 10.40 1.00W 10.60 1.0000 10.80 1.0000
=
11.00 1.0000 1.05 1120 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 12.00 1.0000
Revision 0 Page II of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 Table 2.6.2 Penalty Factors In Excess of 2% per 31 EFPD Cycle Burnup Penaly Factor (MWD/MTU) Fi(z) 13080 1.0200 13252 1.0216 13424 1.0203 13597 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.
Revision 0 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 12 2.7 Nuclear Enthalpv Rise Hot Channel Factor (FNAH) (LCO 3.2.2) 2.7.1 FNAH 5 FZ [1 .0 + PFH(1 .0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F1HT= 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:
UFM = UFam where:
UF4Jm = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNAH Waming Setpoint 2 2% of FNm Margin FNAH Alarm Setpoint 2 0% of F^AH Margin 2.8 AXIAL FLUX DIFFERENCE (AFO) (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 2 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 80 a.
IW 60 0
I--
0 40 0
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 2 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 Kg shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Ta, 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 T,,g 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 T shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant x3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant r4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant T 5 shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant X6 shall be less than or equal to 2 sec.
2.10.12 The f, (Al) Opositivew breakpoint shall be +10% Al.
2.10.13 The f, (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 % I % Al.
Revision 0 Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 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 / OF for Increasing Tag.
2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0/ OF for decreasing Tavg.
2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient Kr, shall be equal to 0.00245 / OF when T > To.
2.11.5 The Overpower AT reactor trip setpoint T.,, heatup coefficient K6 shall be equal to 0
/IFwhenT*T".
2.11.6 The nominal T. at RTP (indicated) T" shall be less than or equal to 588.0 OF 2.11.7 The measured reactor vessel AT leadAag time constant T1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant C2shall 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 6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant X7 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 2 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 (T.) 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 3.1.9 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 1750 2.13.2 a) prior to Initial criticality 1838 2.13.2 b) all other times In core life 1966