BYRON 2011-0059, Submittal of Cycle 18 Core Operating Limits Report, Revision 7

Submittal of Cycle 18 Core Operating Limits Report, Revision 7

ML110970511
Person / Time
Site:	Byron
Issue date:	04/07/2011
From:	Tulon T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2011-0059
Download: ML110970511 (18)

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\ci. r Nliiciear 79 April 7, 2011 LTR: BYRON 2011-0059 File: 2.01.0300 1.10.0101 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 18 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 7 for Cycle 18.

Should you have any questions concerning this report, please contact Mr. David Gudger, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, T othyJ.Tulon Site Vice President Byron Station

Attachment:

Byron Station Unit 1 Cycle 18, COLR, Revision 7 TJT/DG/J E LJcy cc: Regional Administrator NRC Region Ill 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 7 Cycle 18

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 18 EXELON TRACKING ID:

COLR BYRON I REVISION 7

COLR BYRON 1 Revision 7 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit I Cycle 18 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 (FQ(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FtH)

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, Tempe rature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affecte d 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)

COLR BYRON 1 Revision 7 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 18 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.

680 660 S

620 600 580 2

Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 1 Revision 7 Page3ofls CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 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 (LCO5 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.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 BOLJARO/HZP-MTC upper limit shall be +1.679 x i0 tk/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 Ak/k/°F.

2.3.3 The EOL/AROIHFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10 Ak/k/°F.

2.3.4 The EOLJARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x Ak/k/°F.

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

COLR BYRON 1 Revision 7 Page 4 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 1 CYCL E 18 Figure 25.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 200 180 160 (100%, 161) 140 a.

120 c 100 0

C 0

0 60 40 20 0

0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BYRON 1 Revision 7 Page 5 of 15 CORE OPERATING LiMiTS REPORT (COLR) for BYRON UNIT 1 CYCL E 18 2.6 Heat Flux Hot Channel Factor (Fj (LCO 3.2.1) 2.6.1 Total Peaking Factor:

RTP F

FQ(Z) --xK(Z) forP O.5 FRTP F

(

0 Z) 9 -

-xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTP= 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0 1.0) 1 12 ,0.924) 0.9 0.8 0.7 a

U 0.6 gO.5 0.4 Envelope I

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

COLR BYRON 1 Revision 7 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 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 as:

1) Table 2.6.2.a are the normal operation W(Z) values for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1 .a. The normal operation W(Z) values have been determined at bumups of 150, 6000, 14000, and 20000 MWD/MTU.

2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle bumups 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOL-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c 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 FWQ(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.c.

2.6.3 Uncertainty

The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor F (Z) shall be 0

calculated by the following formula U-Q Uq,

• U where:

Uqu = 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% F (Z) Margin 0

F

(

0 Z) Alarm Setpoint = 0% F (Z) Margin 0

COLR BYRON 1 Revision 7 Page7ofl5 CORE OPERATING LIMiTS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 Table 2.6.2.a Full Cycle W(Z) versus Core Height for .FD Pcceptabie Operation Limits in Figure 2 8 1 a (Top and Bottom 8% Excluded per WCAP-l 0216)

Height 150 6000 14000 20000 (feet) MWDIMTU MWD/MTU MWDIMTU MWDIMTU 0.00 (core botlom) 13700 1.4891 1.4083 1.3376 0.20 1.3550 1.4423 1.3734 1.3155 0.40 1.3460 1.4238 1.3570 1.3039 0.60 1.3350 1,4063 1.3395 1.2952 0.80 1,3070 1.3831 1.3183 1.2909 1.00 1.2970 1.3646 1.3048 1.2864 1.20 1.2950 1.3610 1.2796 1.2792 1.40 1.3090 1.3425 1.2670 12718 1.60 1.2930 1.3172 1.2587 1.2615 1.80 1.2790 1.2967 1.2462 1 2532 2.00 1.2650 12753 1.2338 1.2429 2.20 1.2490 1.2511 1.2176 1.2289 2.40 1.2340 12296 1.2127 1.2158 2,80 1.2170 1.2063 1.2062 12008 2.80 1.2020 1.1911 1.2001 1.1848 3.00 1.1860 1.1860 1.1928 1.1705 3.20 1.1758 1.1790 1.1840 1,1662 3.40 1.1710 1.1743 1.1757 1.1700 3.60 1.1655 1.1678 1.1657 l.1737 3.80 1.1598 1.1822 1.1630 1.1763 4.00 1.1532 1.1552 1.1610 1.1779 4.20 1.1450 1.1461 1.1571 1.1785 4.40 1.1382 1.1386 1.1531 1,1829 4.60 I.1297 1,1280 1.1464 1.1922 4,80 1.1211 1.1189 1.1498 1.2005 5.00 1.1162 1.1088 1.1524 12064 520 1,1138 1.0972 1.1549 1.2099 5.40 1.1114 1.0875 1.1564 1.2124 5.60 1.1069 1.0839 1.1550 1.2300 5.80 1.1029 1.0884 1.1586 1.2466 6.00 1.0995 1.0971 1.1712 1.2591 6.20 1.1105 1.1048 1.1829 1.2687 6.40 1.1212 1.1116 1.1916 1,2753 6.60 1.1310 1.1174 1.1974 1.2770 6.80 1.1397 1.1250 1.2021 1.2768 7.00 1.1466 1.1314 1,2039 1.2736 7.20 1.1504 1.1395 1.2028 1.2654 7.40 1.1567 1.1478 1,1998 1.2564 7.60 1.1619 1.1551 1.1938 1.2415 7.80 1,1662 1.1610 1.1869 1.2276 8.00 1.1686 1.1663 1.1771 12098 8.20 1,1699 1.1696 1 1653 1.1890 8.40 1.1703 1.1729 1.1584 1.1713 8.60 1.1698 1.1801 1.1574 1.1525 8.80 1.l690 1,1951 1.1606 1.1458 9.00 1,1726 12108 1.1621 1.1440 9.20 1.1795 1.2249 1.1623 1.1580 9.40 1.1959 1.2387 1.1692 1.2030 9,60 12047 12512 1,1900 1.2460 9.80 1.2076 12641 1.2220 1.2840 10.00 1.2075 1.2685 1.2510 1.3180 10.20 1.1916 1.2726 1 2780 1,3470 10.40 1.1835 1.2828 12990 1.3710 10.60 1.1750 1.2954 1 3080 1.3929 1080 1.1850 1.3081 1.3120 1.4117 11.00 1.2254 1.3198 1.3109 1.4225 1120 1.2268 1,3192 1.3180 1.4080 11,40 1.2334 1.3320 1.3180 1.3950 11.60 1.2345 1.3366 1 .2860 1.3693 1180 1.2402 1.3438 1.2585 1.3642 12.00 (core top) 1.2527 1.3610 1.2613 1 3630 Note: W(Z) values at 20000 MrND/MTU may be applied to cycle burnups greater than 20000 MvVDIMTU to prevent W(Z) function extrapolation

COLR BYRON 1 Revision 7 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 Table 2.6.2rnb EOL-only W(Z) versus Core Height for AFD Acceptable Operation Limits In Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-10216)

Height 18000 20000 24205 (feet) MWDIMTU MWDIMTU MWDIMTU 0.00 (core bottom) 1.2259 1.2095 1.2095 0.20 1.2010 1.1862 1.1862 0.40 1.1880 1.1733 1,1733 0.60 1,1798 1,1694 1.1694 0.80 1.1717 1.1680 1.1680 1.00 1.1655 1.1650 1.1650 120 1.1583 1.1606 1.1606 1.40 1.1559 1.1554 1.1554 1.60 1.1519 1.1480 1,1480 1.80 1,1475 1.1418 1.1418 2.00 1.1418 1.1341 11341 220 1.1342 1.1239 1.1239 2.40 1.1269 1.1139 1.1139 2.60 1.1203 1.1068 1.1068 2.80 1,1177 1.1074 1.1074 3.00 1.1168 1.1105 1.1105 3.20 1.1159 1.1137 1,1137 3.40 1.1195 1.1195 1.1195 3.60 1.1287 1.1338 1.1338 3.80 1.1371 1.1471 1,1471 4.00 1.1463 1.1593 1,1593 4.20 1.1574 1.1721 1.1721 4.40 1.1671 1.1829 1.1829 4.60 1.1756 1.1922 1.1922 4.80 1.1828 1.2004 1.2004 5.00 1.1877 1.2064 1.2064 5.20 1.1913 1.2099 1.2099 5.40 1.1938 1.2124 1.2124 5.60 1.2033 1.2300 1.2300 5.80 1.2142 1.2466 1.2466 6.00 1.2269 1.2591 1.2591 6.20 1.2378 1.2687 1.2687 6.40 1.2455 1.2753 1.2753 6.60 1.2490 1.2770 1.2770 6.80 1.2507 1.2768 1.2768 7.00 1.2493 1.2736 1.2736 7.20 1.2434 1.2654 1.2654 7.40 1.2361 1.2564 1.2564 7.60 1.2240 1.2415 1.2415 7.80 12121 1.2276 1.2276 8.00 1.1965 1.2098 1,2098 8,20 1.1784 1.1890 1.1890 8.40 1.1645 1.1713 1.1713 8.60 1,1527 1.1525 1.1525 8.80 1.1492 1.1458 1.1458 9.00 1.1476 1.1440 1.1440 9.20 1.1545 1.1580 1.1580 9.40 1.1824 1.2030 1.2030 9.60 1.2164 1.2460 1,2460 9.80 1.2532 1.2840 1.2840 10.00 1,2870 1.3180 1.3180 10.20 1.3169 1.3470 1.3470 10.40 1.3403 1.3710 1.3710 10.60 1.3562 1.3929 1.3929 10,80 1.3678 1.4117 1.4117 11.00 1.3726 1.4225 1.4225 11.20 1.3681 1.4080 1.4080 11.40 1.3597 1.3950 1.3950 11.60 1.3283 1.3693 1.3693 11.80 1.3158 1.3642 1.3642 12.00 (core top) 1.3099 1.3630 1.3630 Note: W(Z) values at 20000 MND/MTU may be applied to cycle bumups greater than 20000 v?vVDfMTU to prevent W(Z) function extrapdation

COLR BYRON I Revision 7 Page9ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor (MWD/MTU) (z) 0 FC 0 1.0240 150 1.0240 842 .0485 1188 1.0495 1534 1.0475 1707 1.0448 1879 1.0415 2744 1.0214 2917 1.0200 14678 1.0200 14851 1.0205 15024 1.0207 15370 1.0210 16061 1.0214 16407 1.0212 16580 1.0210 16753 1.0207 16926 1.0204 17099 1.0200 24205 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle bumups.

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.

COLR BYRON 1 Revision 7 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN) (LCO 3.2.2) 2.7.1 FH F[1.O + PFH(l.O P)]

where: P the ratio of THERMAL POWER to RATED THERMAL POWER RTP PFH = 0.3

2.7.2 Uncertainty

The uncertainty, UFH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN,\H shall be calculated by the following formula:

UFAH UFAHm where:

UFm = Base FH measurement uncertainty = 1.04 when PDMS is inoperable (UFHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

Warning Setpoint = 2% FtH Margin FH Alarm Setpoint = 0% FH 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 the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6,2.b. Prior to changing to Figure 2.8.1 .b, confirm that the plant is within the specified AFD envelope.

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 1.539 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% DNBR Margin DNBR Alarm Setpoint =0% DNBR Margin

COLR BYRON 1 Revision 7 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 Figure 2.8.1.a:

Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)

Axial Flux Difference Limits with PDMS Inoperable 120

(-15 100) 10, 00) 100 w

\\ UnaceptaIe 0

0 80

-I UflaCTl//_  ::ra$

uJ 60 LU 40 (-3 5, 50: (+

20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 1 Revision 7 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup 18000 MWDIMTU)

Axial Flux Difference Linits with PDMS Inoperable 120

(-10, 100) (--1O 100) 100 LU UnacePtabI4 unaQDep a

t bjl 0

0 80

-J AccptabIe LU Op ration -_____

60 I

LU I ( 20, 50) +25) 40 0

20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 1 Revision 7 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 2.10 Reactor Triø System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K 1 shall be equal to 1.325.

2.10.2 The Overtemperature AT reactor trip setpoint Ta coefficient K 2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00181 / psi.

2.10.4 The nominal Tavg at RTP (indicated) V 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 1 t shall be equal to 8 sec.

2.10.7 The measured reactor vessel AT lead/lag time constant 2 t shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant t 3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant 4 t shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant t shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant t shall be less 6

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% I % Al.

2.10.15 The f1 (Al) negative slope shall be -2.61% 1% Al.

COLR BYRON I Revision 7 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 18 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 K 4 shall be equal to 1.072.

2.11 .2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K 5 shall be equal to 0.02 I °F for increasing Tavg 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K 5 shall be equal to 0 I °F for decreasing Tavg.

2.11 .4 The Overpower AT reactor trip setpoint Tayg heatup coefficient K 6 shall be equal to 0.00245/FwhenT>T.

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K 6 shall be equal to 0 / °F when 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 1 t shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant t 2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel AT lag time constant t 3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant t shall be less 6

than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant 7 t shall be equal to 10 sec.

2.11 .12 The f 2 (Al) positive breakpoint shall be 0 for all Al.

2.11 .13 The f 2 (Al) negative breakpoint shall be 0 for all Al.

2.11.14 The 2 (fAl) positive slope shall be 0 for all Al.

2.11.15 The f 2 (Al) negative slope shall be 0 for all Al.

COLRBYRON 1 Revision 7 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 18 212 Reactor Coolant System (RCS) Pressure. Tempe rature, and Flow Departure from Nucleate BoiIinQ (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 (Ta) 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 require ments for the previous cycle.

2.13.2 To maintain keff 0.987 with all shutdown and control rods fully withdr awn 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 1701 2 13 2 a) pnor to initial cnticality 1782 2 13 2 b) all other times in life 2009