BYRON 2009-0107, Cycle 17 Core Operating Limits Report
| ML092740072 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/30/2009 |
| From: | Enright D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.01.0300, BYRON 2009-0107 | |
| Download: ML092740072 (16) | |
Text
Exelorl Cerif'fritlOn COnirX!ny, LLC
- >tation
\vww.exeloncorp.con I Nuclear North C;C'rnl,HI Church Klidd 8yron. IL 6101O* Q 794 September 30, 2009 LTR: BYRON 2009-0107 File: 2.01.0300 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454
Subject:
Byron Station Unit 1 Cycle 17 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the Unit 1 COLR Revision 6 for Cycle 17.
Should you have any questions concerning this report, please contact David Gudger, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully,
~~~
Daniel J. Enright Site Vice President Byron Station
Attachment:
Byron Station Unit 1 Cycle 17, COLR, Revision 6 DJE/DG/JEUcy 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
ATTACHMENT Byron Station Unit 1 Core Operating Limits Report Revision 6 Cycle 17
NF-CB-09-115 July 22, 2009 CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 1 CYCLE 17 EXELON TRACKING 10:
COLR BYRON 1 REVISION 6
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 1 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 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 (Fa(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F NLlH )
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 ~ 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)
NF-CB-09-115 July 22. 2009 COLRBYRON 1 Revision 6 Page 2 of 13 CORE OPERATING LlMITS REPORT (COLR) for BYRON UNIT 1 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 - - - - .
660 +_-~;::,-.,t.::----+----+----t__----+----I u..
~
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o
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- J e
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t- 620 +--~o::::::_+----+-;::",.",:::::_-+_---t_---t_~::::__~
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e Q.)
.lC 600 +_---+-----jf-----t--~~----t--.=....,c__l o .2 .4 .6 .8 1. 2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
NF-CB-09-115 July 22, 2009 COLRBYRON I Revision 6 Page 3 of 13 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT I 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% L'l.k/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% L'l.k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 Moderator Temperature Coefficient (MTG) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTG) limits are:
2.3.1 The BOLIARO/HZP-MTC upper limit shall be +2.603 x 10-5 L'l.k/k/oF.
2.3.2 The EOLIARO/HFP-MTC lower limit shall be -4.6 x 10"4 L'l.k/krF.
2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 L'l.k/k/oF.
2.3.4 The EOLIARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10'4 L'l.k/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) 228 113
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 Figure 2.5.1 :
Control Bank Insertion Umits Versus Percent Rated Thermal Power 224 (27%,224) (77%,224) 220 ****1 i!
200 -*-t-I 180 _..... ~-- : _--_.
C I
~
ta 160 r- I-- (100%, 161)
"C
~
~ 140 I til
~
0.
Q) c:
120 I I
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- e 100 - . J--- __ L til 0
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IBANKD
, I!.
..x:
c: 80 ta lD "C
~
0 60 40 j
20 ** *1", .... ~ . f . L I
I 0-..,----..,......-......- ......- -........ -0+--......,.... . . . . . . - ---...,
o 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 5 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 2.6 Heat Flux Hot Channel Factor (FQ{Z>> (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ(Z) ~-Q-xK(Z) forP ~0.5 0.5 F RTP FQ(Z) ~-Q-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 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 Feo(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWo(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 Fo(Z) shall be calculated by the following formula V FQ = V qu eVe where:
Uqu = Base Fa measurement uncertainty = 1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)
Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
Fo(Z) Warning Setpoint =2% of Fo(Z) Margin Fo(Z) Alarm Setpoint =0% of Fo(Z) Margin
NF-CB-09-115 july 22, 2009 COLRBYRON 1 Revision 6 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0)
....--,.._......,r----r-.....--.....--.---,..--r----r--.,.-.......-
(6.0 1.0) ...
r-rl-l-T-rlr':::::::t::::f=l=:JO(~12~*i(,lo.924 )
0.9 +--+-~I----+--+--+---+--+--+-----t~-+--+---f
~
0.8 +--+---il---+--+--+-+--+--+---i--+--+---t ga O. 7 +--+-~I---+--+---+---+--+--I-----t--+--+---f LL "C
.~
"iO 0.6 +--+---il---f--+---+-+--+--t---t--+--+---f E
- 0.5 +--+-~I----+--+--+---+--+--+-----t~-+--+---f z
N i~ LOCA Limiting
~ 0.4 +--+---il---+--+--+-+--+ :. .E_nve.I<:>£e..-
I 0.3 +--+----ll----+--+---+---+--+--I-----t--+--+---f 0.2 +--+---fl---f--+---+-+--+--t---t--+--+---f 0.1 +--+---il---+--+--+-+--+--+---il---+--+---f O+--+-~I----+--+--+---+--+--I-----t---+--+---f o 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
NF-CB-09-115 July 22, 2009 COLRBYRON I Revision 6 Page 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 Table 2.6.2.a W(Z) versus Core Height (Top and Bottom 8% Excluded per WCAP*10216)
Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3890 1.4859 1.3906 1.3006 0.20 1.3652 1.4421 1.3625 1.3000 0.40 1.3473 1.4236 1.3577 1.2972 0.60 1.3334 1.4061 1.3433 1.2926 0.80 1.3206 1.3828 1.3250 1.2901 100 1.3097 1.3643 13114 1.2855 1.20 13207 1.3420 1.2922 1.2790 1.40 1.3108 1.3265 12826 12725 1.60 1.2950 1.3090 12653 12602 1.80 1.2811 1.2876 1.2528 1.2488 2.00 1.2662 1.2671 1.2402 1.2394 2.20 1.2493 1.2448 1.2249 1.2271 2.40 1.2335 1.2242 1.2107 1.2147 2.60 1.2156 1.2009 1.2018 1.1996 2.80 1.1997 1.1894 1.1957 1.1862 3.00 1.1839 1.1836 1.1896 1.1719 3.20 1.1694 1.1786 1.1818 1.1548 3.40 1.1659 1.1740 1.1753 1.1514 3.60 1.1614 1.1680 1.1657 1.1570 3.80 1.1563 11619 1.1572 11618 4.00 1.1513 1.1549 1.1486 1.1657 4.20 1.1448 11459 1.1375 1.1671 4.40 1.1378 11378 1.1270 1.1685 4.60 1.1303 1.1272 1.1251 1.1786 4.80 1.1222 1.1182 1.1262 1.1874 5.00 1.1141 1.1076 1.1259 1.1942 5.20 1.1123 1.0961 1.1266 1.1989 5.40 1.1091 1.0869 1.1279 1.2024 5.60 1.1055 1.0834 1.1306 1.2144 5.80 1.1018 1.0899 1.1472 1.2330 6.00 1.0978 1.0975 1.1618 1.2486 6.20 1.1094 1.1050 1.1745 1.2602 6.40 1.1202 1.1116 1.1851 1.2698 6.60 1.1299 11164 1.1958 1.2745 6.80 1.1387 11215 1.2026 1.2782 7.00 11455 1.1270 1.2054 1.2781 7.20 1.1509 1.1343 1.2052 12729 7.40 1.1589 1.1406 1.2022 1.2659 7.60 1.1668 1.1464 1.1971 1.2500 7.80 1.1736 1.1518 1.1902 1.2370 8.00 1.1789 1.1561 1.1822 1.2231 8.20 1.1832 1.1599 1.1713 1.2062 8.40 1.1870 11673 11708 1.1903 860 1.1883 1.1793 1.1694 1.1757 8.80 1.1902 1.1957 1.1681 1.1777 9.00 1.1910 1.2153 1.1656 1.1791 9.20 11893 1.2327 1.1626 1.1799 9.40 11895 1.2483 1.1664 1.2200 9.60 1.2039 12632 11736 1.2616 980 1.2174 12774 1.1970 13002 10.00 1.2247 1.2902 1.2240 1.3348 10.20 1.2247 1.2934 1.2550 1.3626 1040 12167 12916 1.2696 13893 10.60 1.2203 1.2907 12854 1.4121 10.80 1.2241 1.2940 1.2982 1.4299 11.00 1.2275 13050 1.3061 1.4397 11.20 12381 1.3200 1.3029 14405 1140 1.2450 13333 1.2997 1.4324 11.60 1.2465 1.3424 1.2747 1.4074 11.80 1.2502 13509 1.2627 1.4033 12.00 (core top) 1.2601 1.3703 1.2554 1.3941 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWDIMTU to prevent W(Z) function extrapoiation
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 Table 2.G.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) Fea(z) 150 1.0200 323 1.0220 1015 1.0514 1188 1.0551 1534 1.0551 1879 1.0510 2225 1.0440 3090 1.0225 3263., 1.0200
".--r;,- ,,--'. ~.,.... :..**y ,.
16061 1.0200 16234 1.0207 16580 1.0256 16753 1.0271 17618 1.0285 18137 1.0287 18483 1.0295 18656 1.0295 19347 1.0244 19693 1.0206 19866 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.
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 N
2.7 Nuclear Enthalpy Rise Hot Channel Factor (F M:0 (LCO 3.2.2) 2.7.1 FN6H ~ F~~P[1.0 + PF6H (1.0 - P)]
where: P =the ratio of THERMAL POWER to RATED THERMAL POWER
=
F~~P 1.70 PF6H =0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UF~H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN6H shall be calculated by the following formula:
where:
UFtJHm =Base F 6H measurement uncertainty =1.04 N
2.7.3 PDMS Alarms:
F 6H Warning Setpoint =2% of F 6H Margin N N F ~H Alarm Setpoint =0% of F ~H Margin N N 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 Z 1.536 The Axial Power Shape Limiting DNBR (DNBRAPsd is applicable with THERMAL POWER z 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
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 i I :
i 100 +---+,-
Jci-10~)
I :
(+10,100)
-""i--+--~---+-----'--+----i 0::: I ! I W
3: U naccepta~le I Unaccept,able
, Ir***** i !
~ 80 . op~rat1°1 ....... I Qpe.ratir"--
, I
...J Acceptable
- E I I , J Operation 0::: i * !
w 60 L..... --.,-.. .! .... -
- I:
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. -.,_ . . . . 1-I '
o ;
40 20 -10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature ~T Setpoint Parameter Values 2.10.1 The Overtemperature ~T reactor trip setpoint K 1 shall be equal to 1.325.
2.10.2 The Overtemperature ~ T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ of.
2.10.3 The Overtemperature ~ T reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00181/ psi.
2.10.4 The nominal Tavg at RTP (indicated) l' 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 ~T lead/lag time constant t1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel ~T lead/lag time constant t2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel ~T lag time constant t3 shall 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 ts shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant ts shall be less than or equal to 2 sec.
2.10.12 The f 1 (~I) "positive" breakpoint shall be +1 0% ~1.
2.10.13 The f 1 (~I) "negative" breakpoint shall be -18% ~1.
2.10.14 The f 1 (~I) "positive" slope shall be +3.47% / % ~1.
2.10.15 The f 1 (~I) "negative" slope shall be -2.61 % / % ~1.
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 2.11 Reactor Trip System eRTS) Instrumentation (LeO 3.3.1) - Overpower ~T Setpoint Parameter Values 2.11.1 The Overpower ~T reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower ~T reactor trip setpoint Tavg ratellag coefficient Ks shall be equal to 0.02/ of for increasing Tavg .
2.11.3 The Overpower ~ T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0/ OF for decreasing Tavg 2.11.4 The Overpower ~ T reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0.00245/ of when T > T".
2.11.5 The Overpower ~T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0/ OF when T ~ P.
2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 of 2.11.7 The measured reactor vessel ~ T lead/lag time constant "(1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel ~ T leadllag time constant "(2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel ~ 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 (~I) "positive" breakpoint shall be 0 for all ~1.
2.11.13 The f2 (~I) "negative" breakpoint shall be 0 for all ~I.
2.11.14 The f2 (~I) "positive" slope shall be 0 for all ~1.
2.11.15 The f2 (~I) "negative" slope shall be 0 for all ~1.
NF-CB-09-115 July 22, 2009 COLRBYRON 1 Revision 6 Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 17 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 avg ) 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.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 1689 2.13.2 a) prior to initial criticality 1754 2.13.2 b) all other times in life 1983