BYRON 2013-0051, Cycle 18 Core Operating Limits Report

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Cycle 18 Core Operating Limits Report
ML13106A063
Person / Time
Site: Byron Constellation icon.png
Issue date: 04/15/2013
From: Kearney F
Exelon Nuclear, Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
BYRON 2013-0051, 1.10.0101, 2.01.0300
Download: ML13106A063 (18)
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Text

April 15, 2013 LTR: BYRON 2013-0051 File: 2.01.0300 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455

Subject:

Byron Station Unit 2 Cycle 18 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," we are submitting the Unit 2 COLR Revision 5 for Cycle 18.

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

Faber A.4Kea Site Vice President Byron Station

Attachment:

Byron Station Unit 2 Cycle 18, COLR, Revision 5 FAK/DG/cy 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 2 Core Operating Limits Report Revision 5 Cycle 18

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 18 EXELON TRACKING ID:

COLR BYRON 2 REVISION 5

COLR BYRON 2 Revision 5 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 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 (F"AH)

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)

COLR BYRON 2 Revision 5 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 Technica l 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.

68 2471 psis 660 2250 psis 640 2000 psis C k_

E 1860 psis t2 W

620 cn 0

600 580 0 .2 .4 . 6 . 8 1 1.

Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 2 Revision 5 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 (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.i and 3.1.j).

2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

"5 2.3.1 The BOUARO /HZP-MTC upper limit shall be +1.839 x 10 Pik/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10 -4 Ak/k/°F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 Ak/k/°F.

2.3.4 The EOL/ARO/HFP- MTC Surveillance limit at 60 ppm shall be -4.3 x 10 -4 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) 231 115

COLR BYRON 2 Revision 5 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (26.52%, 4) (76.96%,224) 220 2

0 ,00 / 0E 1 0 00%, 161)

(0°l0, 163) 1 L-ZL 21 BANK 20 20 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BYRON 2 Revision 5 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 2.6 Heat Flux Hot Channel Factor (FQLZ ,) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

FRTP FQ (Z) <_ Q xK(Z) for P < _ 0.5 0.5 FRTP FQ (Z) <_ Q xK(Z) for P > 0.5 P

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER Fa TP = 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) 0.924) 0.9 0.8 0.7 0.6 0.5

--LOCA Limiting 0.4 Envelope 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 2 Revision 5 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 burnups 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 burnups >_ 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 FcQ(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 FQ(Z) shall be calculated by the following formula UFr) = 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% FQ(Z) Margin FQ(Z) Alarm Setpoint = 0% FQ(Z) Margin

COLR BYRON 2 Revision 5 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bott om 8% Excluded per CAP-1 0216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3284 1.4956 1.3983 1.3198 0.20 1.31 14 1.4525 1.3733 1.3063 0.40 1.2991 1 .43 72 1.3566 1.2990 0.60 1.2869 1.4219 1.3391 1.2946 0.80 1.2691 1.4001 1,3192 1 .2 907 1 00 1.2579 1,3837 1.3045 1,2855 1.20 1.2449 1.3822 1.2911 1.2777 1.40 1,2337 1,3632 1.2783 1.2706 1 .60 1.2255 1.3402 1.2631 1.2610 1.80 1.2195 13210 1.2512 1.2510 2.00 1.2126 1.3000 1,2377 1.2402 2.20 1.2051 1.2 761 t2279 1.2258 2.40 1.2001 1.2548 1.2202 1.2132 2.60 1.19 31 1.2 301 1.2092 1.1970 2.80 1A860 1.2093 1.2002 1.1823 3.00 1.1790 1.1926 1.1913 1.1670 3.20 1.1707 1.1797 1,1828 1.1650 3.40 1.1624 1.1747 1.1739 1.1624 3.60 1.1529 1.1681 1.1635 1.1629 3.80 1.1446 1.1616 1.1551 1.1631 4.00 1.1375 1.1551 1.1508 1.1634 4.20 1.1351 1,1460 1,1445 1,1713 4.40 1.1327 1.1375 1.1389 1.1824 4.60 1.1331 1.1274 1.1311 1.1921 4.80 1.1318 1,1179 1,1259 1.2007 5.00 1.1302 1.1078 1.1286 1.2062 5.20 1 .1266 1,1034 1.1308 1,2114 5.40 1.1222 1.1015 1.1324 1.2149 560 1A206 1.0976 1.1381 1.2146 5.80 1,1280 1.0947 1 .1537 1,2213 6.00 1.1356 1.0913 1.1682 1.2359 6.20 1.1413 1.0991 1.1809 1.2476 6.40 1.1460 1.1078 1.1905 1.2563 6.60 1.148 7 1,1165 1.1983 1,2611 6.80 1.1505 1,1242 1 ,2041 1.2639 7.00 1.1503 1.1309 1 ,2069 1,2637 7120 1,1505 1A377 1 ,2079 1 .2 588 7.40 1A533 1.1444 1.20 58 1.2527 7.60 1.1540 1.1523 1.2018 1 .2418 7.80 1.1543 1.1591 1,1959 1.2299 8.00 1.1576 1.1644 1.1881 12161 8.20 1.1638 1,1682 1.1773 1 .1974 8.40 1.1694 1.1716 1.1684 1,1855 8.60 1.1761 1.1742 1.1635 11707 8.80 1.1803 1.1786 1.1647 1,1661 9.00 1,1835 1.1862 1.1669 1.1672 920 1.1847 1 .2098 1,1695 1.1645 9.40 1.1859 1,2266 1,1755 1.1660 9.60 1.1872 12391 1.1836 1.2 090 9.80 1.1880 1.2513 11920 1.2460 10.00 1.1882 1.2605 1.2185 1.2 790 10.20 1.1861 1.2663 1.2443 1.3090 10.40 1.1859 1 .2719 1,2629 1.3330 10.60 1.1983 1.2789 1.2806 1.3 520 10.80 1.2096 1.2922 1.2944 1.3670 1 1 .00 1.2131 1,3040 1.3033 1.3760 1 1.20 1.2224 1.3216 1.3012 1,3780 11.40 1.2320 1.3485 1.3000 1.3754 11.60 1.2319 1.3543 1.2789 1,3584 11.80 1,2380 1.3636 t2708 1,3523 12.00 (core top) 1.2502 1.3902 1.2676 1,3490 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BYRON 2 Revision 5 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Table 2.6.2.b 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 24302 (feet) MWD/MTU MWD/MTU MWD/MTU 0.00(corebottom) 1.1966 1,1781 1,1781 0.20 1.1834 1.1681 1.1681 0.40 1.1743 1.1626 1.1626 0.60 1.1664 1.1597 1,1597 0.80 1.1590 1.1582 1.1582 1.00 1.1539 1.1552 1.1552 1.20 1.1486 1.1503 1.1503 1.40 1.1464 1.1453 1.1453 1.60 1.1427 1,1388 1.1388 1.80 1.1383 1.1322 1.1322 2.00 1.1350 1.1284 1.1284 2.20 1.1311 1.1252 1.1252 2.40 1.1283 1.1240 1.1240 2.60 1.1263 1.1227 1.1227 2.80 1.1248 1.1214 1.1214 3.00 1.1221 1.1192 1.1192 3.20 1.1188 1,1168 1.1168 3,40 1.1228 1.1275 1.1275 3.60 1.1270 1.1400 1.1400 3.80 1.1345 1.1513 1.1513 4.00 1.1422 1.1604 1.1604 4.20 1.1501 1.1705 1.1705 4.40 1.1584 1.1824 1.1824 4.60 1.1646 1.1921 1.1921 4.80 1.1698 1.2007 1.2007 5.00 1.1744 1.2062 1.2062 5.20 1.1787 1.2114 1,2114 5.40 1.1817 1.2149 1.2149 5.60 1.1848 1.2146 1.2146 5.80 1.1969 1.2213 1.2213 6.00 1,2130 1.2359 1.2359 6,20 1.2256 1.2476 1.2476 6.40 1.2347 1.2563 1.2563 6.60 1.2407 1.2611 1,2611 6.80 1.2446 1.2639 1,2639 7.00 1.2453 1.2637 1.2637 7.20 1.2425 1.2588 1.2588 7.40 1.2374 1, 2527 1.2527 7.60 1.2284 1.2418 1.2418 7.80 1.2181 1.2299 1.2299 8.00 1.2058 1.2161 1.2161 8.20 1.1894 1.1974 1,1974 8,40 1.1778 1.1855 1.1855 8.60 1.1667 1.1707 1,1707 8.80 1.1644 1.1661 1.1661 9.00 1,1655 1,1672 1.1672 9.20 1.1632 1.1645 1.1645 9.40 1,1657 1.1660 1.1660 9.60 1.1931 1.2090 1.2090 9.80 1,2173 1.2460 1.2460 10.00 1.2488 1.2790 1.2790 1020 1.2785 1.3090 1.3090 10.40 1.3012 1.3330 1.3330 10.60 1.3205 1.3520 1.3520 10.80 1.3350 1.3670 1.3670 11.00 1.3437 1.3760 1.3760 11.20 1.3423 1.3780 1.3780 11.40 1, 3379 1.3754 1.3754 11.60 1.3168 1.3584 1.3584 11.80 1.3084 1.3523 1.3523 12.00 (core top) 1.3027 1.3490 1.3490 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BYRON 2 Revision 5 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor (MWD/MTU) Fco(z) 0 1.0200 841 1.0200 1014 1.0206 1186 1.0279 1359 1.0351 1532 1.0422 1705 1.0477 1877 1.0465 2050 1.0448 2223 1.0426 2395 1.0401 2568 1.0373 2741 1.0345 2914 1.0316 3086 1.0286 3259 1.0258 3432 1.0230 3605 1.0204 3777 1.0200 24302 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.

COLR BYRON 2 Revision 5 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FIHI (LCO 322) 2.7.1 F",H s FH,HP[1.0 + PF,H(1.0 - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FRHP - 1.70 PF,H = 0.3

2.7.2 Uncertainty

The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F"4H shall be calculated by the following formula:

UFAH = UFAHm where:

UF,Hm = Base F"H measurement uncertainty = 1.04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

F",H Warning Setpoint = 2 % F"AH Margin F"pH Alarm Setpoint = 0% F",H 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 2 Revision 5 Page I I of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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, 100) 100 Unacc eptable Una ccepta ble Ope ration O peratio n 80 Accepta ble peratic n 60

-3 , 50) (+ 25, 5 40 20  !

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

COLR BYRON 2 Revision 5 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup > 18000 MWD/MTU)

Axial Flux Difference Limits with PDMS Inoperable Unacceptable Unacceptable Operation Operation-,

Operation

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

COLR BYRON 2 Revision 5 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 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 T, 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 r4 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.

2.10.11 The measured reactor vessel average temperature lag time constant T6 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 f, (Al) "negative" breakpoint shall be -18% Al.

2.10.14 The f, (Al) "positive" slope shall be +3.47% / % Al.

2.10.15 The f, (Al) "negative" slope shall be -2.61% / % Al.

COLR BYRON 2 Revision 5 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 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 K4 shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tav9 rate/lag coefficient K5 shall be equal to 0.02 / OF for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Ta vg 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 K6 shall be equal to 0.00245 / OF when T > T".

2.11.5 The Overpower AT reactor trip setpoint Ta vg heatup coefficient K6 shall be equal to 0 / OF when T 5 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 AT lead/lag time constant L, shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant' r2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel AT lag time constant T3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant r6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant T7 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.

COLR BYRON 2 Revision 5 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 18 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 (Tang) 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 applicable value given in the Table below (LCO 3.9.1). The reported "prior to initial criticality" 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 applicable value given in the Table below.

COLR Conditions Boron Concentration Section pm 2.13.1 a) prior to initial criticality 1696 b) for cycle burnups >_ 0 MWD/MTU 1778 and < 16000 MWD/MTU c) for cycle burnups >_ 16000 1393 MWD/MTU 2.13.2 a) prior to initial criticality 1733 b) all other times in life 1953

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