BYRON 2002-0074, Cycle 12 Core Operating Limits Report, Revision 2
| ML022270660 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/06/2002 |
| From: | Lopriore R Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.01.0700, BYRON 2002-0074 | |
| Download: ML022270660 (19) | |
Text
Exelon Generation Company, LLC Exekon.
Byron Station www exeloncorp.com Nuclear 4450 North German Church Road Byron, IL61010-9794 August 6, 2002 LTR: BYRON 2002-0074 File: 2.01.0700 United States Nuclear Regulatory Commission Attention: 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 12 Core Operating Limits Report, Revision 2
Reference:
Letter from R.L. Lopriore (Exelon Generating Company, LLC) to the NRC, "Byron Station, Unit 1, Cycle 12 Core Operating Limits Report, Revision 1," dated March 22, 2002.
In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the revised COLR for Byron Station, Unit 1 Cycle 12. The Unit 1 COLR was revised to specify the power distribution transient function (i.e., W(Z)) for cycle burnup of 1737 MWD/MTU and beyond.
Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 234-5441, extension 2800.
pecifully, rd P. Lopriore Site Vice President Byron Nuclear Generating Station
Attachment:
Byron Station, Unit 1, Cycle 12 COLR, Revision 2 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Byron Station NRC Project Manager - NRR - Byron Station O \ý Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
ATTACHMENT I Byron Station, Unit 1, Cycle 12 Core Operating Limits Report Revision 2
CAC-02-34, Rev. 1 CORE OPERATING LIMITS REPORT (COLR)
FOR BYRON UNIT 1 CYCLE 12 Revision 2
CAC-02-34, Rev. 1 Page 1 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 1.0 CORE OPERATING LIMITS REPORT in This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 12 has been prepared 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 (FN H)
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 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)
CAC-02-34, Rev. I Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 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 247i psi 660 2250 psia 640 L..
E 520 0
600 580
.4 .6 .8 2 Froction of Nominol Power Figure 2.1.1: Reactor Core Limits
CAC-02-34, Rev. 1 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 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 3.1.1j).
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 BOL/ARO/HZP-MTC upper limit shall be +2.11 x 10s Ak/k/OF.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 Ak/k/oF.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be
-3.7 x 10e Ak/k/oF.
2.3.4 The EOL/ARO/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 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 113 Step overlap limit.
CAC-02-34, Rev. 1 Page 4 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 Figure25.1:
Control Bank Insertion Units Versus Percert Rated Themal Power A, (2"PX; 224) ("M'., 224) 180 0 (800/, 161)
S140 CL
~1o S12D 0
0.
S100 0 80 W60 0
70 80 90 100 0 10 20 30 40 50 60 Rdeafe Powe (Permt)
CAC-02-34, Rev. 1 Page 5 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 2.6 Heat Flux Hot Channel Factor (FZc) (LCO 3.2.1) 2.6.1 FQ(Z)< 5Q 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 RTP FOT= 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 1737, 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. 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 U FQ = Uq .U, where:
Uq, = Base FQ 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:
FQ(Z) Warning Setpoint > 2% of Fo(Z) Margin FQ(Z) Alarm Setpoint > 0% of Fo(Z) Margin
CAC-02-34, Rev. 1 Page 6 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height 1.1
.924) 0.9 0.8 N 0.7 L
am A 0.6 to 0 0.5 z
N,==
0.4 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
CAC-02-34, Rev. I Page 7 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 HeiV MAX W(Z)
Feet Byron Urlt I Cyde 12 0.00 1.0000 0.20 1.0000 FIgure 2.6.2.o 0.40 1.0000 0.60 1.0000 ct W(Z) Furchcn c 1737 VADMT U Sumncy 0.80 1.0000 (Tcpnd Botta 15% Exdicldlar WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.40 1.80 1.1111 2.00 1.0999 2.20 1.0886 2.40 1.0794 2.60 S0"742 2.80 1.0743 3.00 1.0753 1.35 3.20 1.0762 3.40 1.0788 3.60 1.0802 3.80 1.0818 4.00 1.0830 4.20 1.0834 4.40 1.0837 1.30 4.60 1.0831 4.80 1.0837 5.00 1.0883 5.20 1.0941 5.40 1.0993 5.60 1.1073 1.25 5.80 1.1212 0 6.00 1.1340 6.20 1.1447 z 6.40 1.1529 6.60 1.1596 1.20 6.80 1.1661 7.00 1.1755 7.20 1.1881 7.40 1.1992 7.60 1.2073 7.80 L2171 8.00 1.2295 8.20 1.2422 8.40 1.2523 1.15 8.60 1.2636 8.80 1.2781 9.00 1.2937 9.20 1 3135 9.40 1.3289 9.60 1.3390 9.80 1.3493 10.00 1.3558 10.20 1.3764 1040 1.0000 10,60 1.0000 10.80 1.0000 11.00 1.0000 1120 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 CORE HEIGHT (FEET) 1.0000 1180 1.0000 12.00 1.0000
CAC-02-34, Rev. 1 Page 8 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 HeiVt MAX W(Z)
Feet Byron Urnt I Cyde 12 0,00 1.0000 0.20 1.0000 Figje 2.6.2.b 0.40 1.0000 0.60 1.0000 S uTTm y cdW(Z) Funcn ct 6000 IWDvMT U 0.80 1.0000 iopondBotlcm 15% E xdudl per WCAP-10216)
(T 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.00[00 1.45 1 1.80 1.1300 2.00 1.1188 2.20 1.1056 2.40 1.0991 2.60 1.0935 2.80 1.0911 1.40 3.00 1.0919 3.20 1.0930 3.40 1.0935 3.60 1.0919 3.80 1.0919 4.00 1.0909 1.35 4.20 1.0885 4.40 1.0849 4.60 1.0798 4.80 1.0761 5.00 1.0787 5.20 1.0812 5.40 1.0!41 5.60 1.0858 5.80 1.0955 0 6.00 1.1087 z
6.20 1.1202 6.40 1.1319 6.60 1.1418 6.80 1.1515 120 7.00 1.1623 7.20 1.1770 7.40 1.1906 7.60 1.2014 I1 F 7.80 1.2127 800 1.2316 I T 8.20 1.2536 8.40 1.2734 8.60 1.2908 8.80 1.3063 9.00 1.3240 9.20 1.3413 940 1.3578 9.60 1.3705 9.80 1.3842 10.00 1.3956 10.20 1.4111 10.40 1.000 10.60 1.000 10.80 1.0000 11.00 1.0000 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 100000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000
CAC-02-34, Rev. 1 Page 9 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 HeiV MAX W(Z)
Feet Byron Urlt I Cyde 12 0.00 1.0000 Figjre2.62c 0.20 1.0000 0.40 1.0000 S u-rim y d W(Z) F uncn d 14000 IDvAIT U 0.60 (T opcldBottan 15% E xduibdpel WCAP-10216) 080 1.0000 1.00 1.20 1.0000 1.40 1.0000 1.0000 -
1.60 135---------------------------------------------------------
1.80 1.3097 2.00 1.2901 2.20 1.2636 240 1.2531 2.60 1.2389 2.80 1.2274 3.00 1.2133 3.20 1.1983 1.30 3.40 1.1883 3.60 1.1818 3.80 1.1744 4.00 4.20 1.1662 1.1576 n Hil.11
~ ~ ~ 1.0 I 11 1.1473 4.40 1.1358 IIl 4.60 4.80 1.1240 5.00 1.1206 5.20 1.1164 5.40 1.1140 5.60 1.1103 z 5.80 1.1058 6.00 11130 6.20 1.1212 U.
640 1.1277 6.60 1.1328 6.80 1.1363 7.00 1.1409 1.20 7.20 1.1432 7.40 1.1440 7.60 1.1432 7.80 1 1423 8.00 1.1400 8.20 11374 8.40 1 1346 8.60 1.1318 1.15 8.80 1.1335 9.00 1 1345 9.20 1.1344 9.40 1.1391 9.60 11438 9.80 1.1482 10.00 1.1689 1020 1.1964 10,40 1.*0000 10.60 1.0000 10.80 1.0000 1.05. 1 1 1 11.00 1.0000 1120 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1 0000 1.0000 CORE HEIGHT (FEET) 1160 1180 1.0000 1200 1.0000
CAC-02-34, Rev. 1 Page 10 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 H*i*t MAX W(Z)
Feet I ByonUnt Cye 12 0.00 "1.000 0.20 1.0000 Figije 2.6.2.d 0.40 1.0000 0.60 10000 SLfTTUay of W(Z) Fu-gc~o, dt 2c0x1 tvDAMt U 0.80 1.0000 (1opcnd~Bona.15% ExdLKJdpe WCAP-10216) 1.00 1.0000 1.20 1.0000 1.60 1.0000 1.80 1.35 ] I I I I 1.2787 I I I 1 11 2.00 1.2686 2.20 1.2546 I I I I a I I I I I I I ttýv -! T9 2.40 1.2420 2.60 1.2257 2.80 1.2116 3.00 1.2006 3.20 1.1882 1.30 3.40 1.1778 3.60 1.1739 3.80 1.1726 4.00 1.1705 4.20 1*1677 4.40 1.1629 4.60 1.1577 4.80 1.1624 1.25 5.00 1.1663 5'20 1.1675 5.40 1.1691 5.60 1.1797 1.19 z
5.80 0 6.00 I.2087 z 6.20 1.2196 1.2276 a 1.20 6.40 U.
6.60 1.2316 6.80 1.2333 7.00 1.2330 7.20 1.2283 7.40 1.2236 7.60 1.2147 7.80 1.2060 1.15 8.00 1.1940 8.20 1.1790 8.40 1.1636 8.60 1.1448 8.80 1.1270 9,00 1.1149 9.20 1.1143 9.40 1.1154 1.10 9.60 1.1442 9.80 1.1818 10.00 1.2154 10.20 1.2481 10.40 1.0000 10.60 1.0000 10,80 1.0000 11.00 1.0000 1.05 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 1.0000 CORE HEIGHT (FEET) 11.60 11.80 1.0000 12.00 1.0000
CAC-02-34, Rev. 1 Page 11 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor - F';o(z)
(MWD/MTU) (%)
837 2.00 1009 2.78 1524 3.76 1695 3.90 1867 3.91 2039 3.81 2554 3.33 2726 3.33 2897 3.47 3584 4.67 3756 4.76 3928 4.66 4786 2.09 4958 2.00 13716 2.00 14231 2.67 14402 2.75 14574 2.75 14746 2.66 15433 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.
CAC-02-34, Rev. 1 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNfH._ (LCO 3.2.2)
N RT 2.7.1 F,. <_FAH [1.0 + PFH(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, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FHNN shall be calculated by the following formula:
UFjH = UFAHm where:
UFAHrn = Base F NH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNH Warning Setpoint >_2% of FNAH Margin FANHAlarm Setpoint > 0% of FN HMargin 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 > 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER
> 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
CAC-02-34, Rev. 1 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Mal Flux DNfferee Urnits with PIMSiE lnopae 120 W0 (-1 0:1) (+10,100) 4-80 -
e 0*4 11-; 01, UM Ile,-'o w60 "20 I
i40 - 9R n) 0 0~20 0
40 20 -10 0 10 20 30 40 50 A)AL .X M F ,JC (O/,y
CAC-02-34, Rev. 1 Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 AT Setpoint 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature 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 / OF.
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 oF.
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 tishall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant 2shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant Tshall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant T shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant T5 shall be equal to 4 sec.
be 2.10.11 The measured reactor vessel average temperature lag time constant tBshall less than or equal to 2 sec.
2.10.12 The f1 (AI) "positive" breakpoint shall be +10% Al.
2.10.13 The f1 (AI) "negative" breakpoint shall be -18% Al.
2.10.14 The f1 (Al) "positive" slope shall be +3.47% / % Al.
2.10.15 The f1 (AI) "negative" slope shall be -2.61% / % Al.
CAC-02-34, Rev. 1 Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 AT Setpoint 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
equal 2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be to 0.02 / OF for increasing Tavg.
be equal 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall to 0 / oF for decreasing Tavg.
The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal 2.11.4 to 0.00245 / oF when T > T".
shall be equal 2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 to 0 / OF when T < T".
oF.
2.11.6 The nominal Tag at RTP (indicated) T" shall be less than or equal to 588.0 equal to 2.11.7 The measured reactor vessel AT lead/lag time constant r shall be 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant T2 shall be equal to 3 sec.
equal 2.11.9 The measured reactor vessel AT lag time constantT3 shall be less than or to 2 sec.
shall be 2.11.10 The measured reactor vessel average temperature lag time constant 6 less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant T shall be equal to 10 sec.
2.11.12 The f2 (AI) "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.
CAC-02-34, Rev. 1 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 12 from 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure 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 OF.
2.12.3 The RCS total flow rate shall be greater than or equal to 380,900 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1756 ppm (LCO 3.9.1).
or equal 2.13.2 The Reactor Coolant System boron concentration shall be greater than 2042 to 1831 ppm prior to initial criticality of Cycle 12, or greater than or equal to ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1 .g and 3.1 .k).