BYRON 2004-0036, Issuance of Core Operating Limits Report, Cycle 12
| ML041040628 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/05/2004 |
| From: | Kuczynski S Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.01.0700, BYRON 2004-0036 | |
| Download: ML041040628 (20) | |
Text
FV Exelkns.
Exelon Generation Company, LLC Byron Station 4450 North German Church Road Byron, IL 61010-9794 www.exeloncorp.com Nuclear April 5, 2004 LTR:
BYRON 2004-0036 File:
2.01.0700 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Issuance of Core Operating Limits Report for Byron Station Unit Two Cycle 12
Reference:
Licensee Event Report 454-2003-003-01, 'Licensed Maximum Power Level Exceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements," Dated March 31, 2004 In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the COLR for Byron Station, Unit 2 Cycle 12.
The cycle 12 core contains 85 new fuel assemblies, 88 once burned assemblies and 20 twice burned assemblies. All the new assemblies contain Integral Fuel Burnable Absorbers and all 8 of the twice-burned assemblies have had their top nozzle replaced due to the potential top nozzle screw fracture problem.
The nuclear design and safety analyses also considered the possible effects from overpower operation of Byron Station Unit 2 that may have occurred due to the inaccuracies in the Ultrasonic Flow Measurement System flow correction factors. (See reference 1)
Should you have any questions concerning these reports, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station
,\\ oo l
Attachment:
Byron Station, Unit 2 Cycle 12, COLR
cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety
Attachment Byron Station, Unit 2 Cycle 12, COLR
CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 2 CYCLE 12
Page I of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron 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 Limits (SLs)
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 (FNm)
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)
Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON 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.
6 80 680-2471 psia 660 2250 psia 64 0 I--
620 a)
On 600
.c8D Froction of Nominol Power Figure 2.1.1: Reactor Core Limits
Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON 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 BOLUARO/HZP-MTC upper limit shall be +2.17 x 105 Ak/kPF.
2.3.2 The EOLJARO/HFP-MTC lower limit shall be -4.6 x 10' 4k/k/0F.
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/0F.
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)
I Overlap Limit (step) 228 113
Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Figure 2.5.1:
Control Bank Insertion ULmits Versus Percent Rated Therml Power (2704 224)
(7704 224)
,-1,,----1)..
e (100%, 161)
C3 160 oc
- 140 QC.
e 120 C0-100 U)0a.
C 80 m
so 0
60 40 20 0
0 10 20 30 40 50 60 70 Relative Power (Percent) 80 90 100
Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 2.6 Heat Flux Hot Channel Factor (F("Z (LCO 3.2.1) 2.6.1 Total Peaking Factor:
QRTP FQ (Z) < -xK(Z) for P S0.5 0.5 FRTP FQ(Z) < FQ xK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER Fo" = 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 MWDIMTU.
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 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.
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 U0=U,., *Ug where:
Uw = Base F0 measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)
U. = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
Fo(Z) Warning Setpoint Ž 2% of Fo(Z) Margin FO(Z) Alarm Setpoint 2 0% of Fo(Z) Margin
Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Figure 2.6.1 K(Z) - Normalized F0(Z) as a Function of Core Height (0.0 1.0)
(6.0,10) 10--1 1
1 1
1 1ll l
{
I 0.9_
0.8
~0.7-ILe 0.6 U 0.6 -
E~ 0.5
=
=
}_-4-LOCA Limiting 0y.4_
PEfnvlinas I
0 1
2 3
4 5
6 7
8 9
10 11 12 BOTTOM Core Height (ft)
. TOP
Page7of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 H4ogt Feem 0.00 0.20 0.40 0.60 0.80 1.00 1.20 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 4.00 420 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 3.0000 1.0000 1.2337 1.2087 1.1941 1.1863 1.1759 1.1694 1.1676 1.1643 1.1621 1.1575 1.1532 1.1482 I.1416 1.1352 1.1312 1.1217 1.1246 1.1211 1.1206 1.1241 1.127 1.1404 1.1522 1.1640 1.1719 1.1798 1.1858 1.1891 1.1902 1.1904 1.1 962 1004 12031 12066 1.2123 1.2140 1.2122 12181 1.2275 1.2355 1.2437 1.2510 1.2542 1.0000 1.0000 1.0000 3.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Byn Urit 2 Cyde 12 rlgie 2.6.2.a SumrneydW(Z)Fmon at 150 ANDh U
(T cpad8cm9ex E15%
Exdup WCAP-10216) 1.35 1.30 1.25 z0 Z 1.20 1.15 1.10 I
I
-I 4
-I. 4
.4 4.
4 4.
4--
4 4
4 4
4 4.
I flg 0.00 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET) 10.00 12.00
Page 8 of 16 CORE OPERATING UMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 0Q00 0.20 040 0.60 0.80 1.00 1.20 1.40 1.60 180 200 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 6.60 680 -
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.lO 10.20 10.40 10.60 10.60 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 10000 10000 l.OOO I1.000 1.2300 12102 1.1920 1.1789 1.1694 1.16s2 1.1602 I.1533 1.1464 1.1384 1.1305 1.1225 1.1126 1.1094 2.2052 1.2022 l.0985 1.093B l.0900 I.0850 2.0925 I.l002 1.1069' 1.1 176 1.1328 1.1494 1.1642 1.1780 1.1903 1.2014 12111 1.2197 1.2267 12.19 1.2352 I.386 2.2462 2.2616 1.2763 1.2892 23029 13148 13244 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Byron Urit2 Cyde 12 Figire2.6.2.b
.SLTrryd W(2) Funbcn a 600D O
NDM U (T cp a-d Bctcon 15% Exdb1d pE WCAP.10216)
Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Hd6gt F eet 0.00 0.20 0.40 0.60 0.80 1.00 1.20 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 J.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 1.40 10.60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 MAX W(2) 1.0000 1.0000 1.0000 I.0000 1.0000 1.0000 1.0000 1.0000 I2692 I12520 2349 I.2I92 I 2029 1.1932 1.139 1.174S I.I656 1.1601 1.156S 1.1535 I.I487 1.2431 1.1363 1.1317 1.1343 1.1359 I.I374 1.14I2 1.1566 1.1710 I.I8t7 2.I914 I.I983 1203I I.2059 l1049 12029 1.1960 1.I891 1.1793 I.I665 1.1596 2.15 28 l.1512 2.1543 2.2553 2.2578 2.1591 l.l880 I2190 I.2470 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Byal U rit 2 Cyde 12 Flgxe 2.62.c Sunrry d WtZ) FLrdcn mS 14000 MNDMr U (lcpsalBcatcnl5% ExdudedapWCAP.10216) 1.35 1.30 1.25 a
0 P120 1.15 1.10 1.05 0.
I
4 4
4 4
4
.4 4
4 t
I 100 2.00 4.00 6.00 8.00 CORE HEIGHT (FEET) 10.00 t2.00
Page lOof 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Heip FeM 0.00 020 0.40 0.60.
0.80 1.0o 1.20 1.40 1.60 1.80 2.00 2.20 2.40 2.60 260 100 120 3.40 3.60 3.80 4.00 4.20 4.40 4.60 4.80 s.m 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 B.00 8.20 8.40 8.60 880 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.0 11.20 11.40 11.60 11.80 12.00 MAX W(Z) 1.0000 L.O00 1.0000 1.0000 o0000 l.0000 l.OXOD l.OOCO l OXO 112628 1.2449 1.2287 1.2189 1.2061 1.1943 I.I8 16 1.1734 1.1789 1.1832 I.1368 1.l888 1.1890 1,1874 1.1949 12023 1.2075 1.2115 12149 12275 12J38 2572 12678 1.2755 1.27t2 12t800 12778 12708 12628 12488 12359 12191 1.1984 1.1777 l1.532 1.1513 1.1510 1.1541 1.1600 1.2040 12430 12770 1.3090 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0D00 Brw Unt 2 Cyde 12 F giue 2.6.2.d S txnrTry d WJZ) Ftxrlon at 20000 MNDAlT U
(
np Edx BrSn 15% Exdu dpe WCAP-10216) -
1Ao 1.35 1.30 z
- .Cu 0
F E
'a-1.20 1.15 1.10 u..v.z 4
V
-- I..
4 4---
4
.4 4
-1
1.05 0.00 2.00 4.00 6.00 8.00 10.00 CORE HEIGHT (FEET) 12.00
Page I I of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor - FcQ(z)
(MWD/MTU)
(%)
150 2.13 322 2.50 494 2.44
- 666 2.33 838 2.14 1010 2.00 4624 2.00 4796 2.08 4968 2.30 5141 2.36 5313 2.28 5485 2.10 5657 2.00 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.
Page 12 of l6 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 2.7 Nuclear Enthaloy Rise Hot Channel Factor (FN)
(LCO 3.2.2) 2.7.1 FOM < FrrP[l.0 + PFwi(1.0 - P).
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F
= 1.70 PFAH= 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty. UFH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNH shall be calculated by the following formula:
UF6H = UFMHm where:
Uss,,, = Base F%.1 measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
0N&j Warning Setpoint 2 2% of F",i Margin Fl.H Alarm Setpoint 2 0% of FN" 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 (DNBRApsI) 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
Pape 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power
- 1*
Axial Flux Difference Limits
.with PDMS Inoperable 120 100
-3 cc a:
I-0 LuJ cc
- 4-.0 p-80 60 40
(-15, 10 )
+10,100)
Unac eptable Un cceplable Op ration 0 eratimn A cceptable C perat on 5, 50)
.(+25,
).
I 20 0 40 20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON 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 K1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint T.,, 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 Tavat RTP (indicated) r 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 't1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant t2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT 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 14 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature leadAag time constant '15 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) 'positive' breakpoint shall be +10% Al.
2.10.13 The fl (Al) 'negative' breakpoint shall be -18% Al.
2.10.14 The f, (Al) "positive" slope shall be +3.47% / % Al.
2.10.15 The fI (Al) "negative' slope shall be -2.61
/% Al.
Page 15of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 12 2.11 Reactor Trip Syslem (RTS) Instrumentation (LCO 3.3.1) - OverpowerAT Seipoint Parameter Values 2.11.1 The Overpower AT reactor trip selpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 / 0F for increasing TM.
2.11.3 The Overpower AT reactor trip setpoint Tav, rate/lag coefficient K5 shall be equal to 0 / 0F for decreasing Tan.
2.11.4 The Overpower AT reactor trip setpoint T.vg heatup coefficient K6 shall be equal to 0.00245 /'F when T > T.
2.11.5 The Overpower AT reactor trip setpolnt Tvg heatup coefficient K(6 shall be equal to 0 /'FwhenTsT".
2.11.6 The nominal T,9 at RTP (indicated) T shall be less than or equal to 588.0 OF 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 leadAag time constant 12 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 12 (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.
Page 16of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON 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 1781 ppm (LCO 3.9.1).
2.13.2 To maintain keff S 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:
- a. 1864 ppm prior to Initial criticality.
- b. 2048 ppm at all other times in core life.