BYRON 2012-0104, Cycle 19 Core Operating Limits Report

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Cycle 19 Core Operating Limits Report
ML12265A033
Person / Time
Site: Byron Constellation icon.png
Issue date: 09/20/2012
From: Tulon T
Exelon Nuclear, Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
BYRON 2012-0104
Download: ML12265A033 (18)
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Text

September 20, 2012 LTR:

BYRON 2012-0104 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 19 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 8 for Cycle 19.

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

Respectfully, Timhy J. Tulon Site Vice President Byron Station

Attachment:

Byron Station Unit 1 Cycle 19, COLR, Revision 8 TJT/DG/JEL/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 1 Core Operating Limits Report Revision 8 Cycle 19

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 19 EXELON TRACKING ID:

COLR BYRON 1 REVISION 8

COLR BYRON 1 Revision 8 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 19 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 (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 TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.i TRM TLCO 3.1.j TRM TLCO 3.1.k Boration Flow Paths - Operating Charging Pumps - Operating Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff >_ 1.0 Shutdown Margin (SDM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)

COLR BYRON 1 Revision 8 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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.

2471 psis 2250 psis 2000 psis 1860 psis 0

.2

. 4

. 6

. 8 1

1.

Fraction of Nominal Power 68 2

660 cry 2

600 580 640 620 Figure 2.1.1: Reactor Core Limits

COLR BYRON I Revision 8 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +1.481 x 10.5 Ak/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 EOL/ARO/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) 231 Overlap Limit (step) 115

COLR BYRON I Revision 8 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power

COLR BYRON I Revision 8 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 2.6 Heat Flux Hot Channel Factor (FQL (LCO 3.2.1) 2.6.1 Total Peaking Factor:

F RTP FQ (Z) <_ Q xK(Z) for P:5 0.5 0.5 F RTP FQ (Z) 5 P xK(Z) for P > 0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FQ 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 (0.0, 1.0 1.

(12.0,0.924) 0.9 0.8 f 0.7 0.3 0.2 0.1 0

1 2

4 5

6 7

8 9

10 11 12 BOTTOM Core Height (ft)

TOP

COLR BYRON I Revision 8 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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

=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 I Revision 8 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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 Bottom 8% Excluded per WCAP-10216)

Height (feet) 150 MWD/MTU 6000 MWD/MTU 14000 MWD/MTU 20000 MWD/MTU 0.00 (core bottom) 1.3429 1.4557 1.3978 1.3385 020 1.3249 1.4211 1.3675 1.3197 0.40 1.3131 1.4076 1.3582 1.3076 0.60 1.3029 1.4062 1.3563 1.3006 0.80 1.2993 1.3639 1.3220 1.2947 1.00 1.2848 1.3469 1.3112 1.2900 1.20 1.2651 1.3277 1.2908 1.2827 1.40 1.2533 1.3135 12777 1.2749 1.60 1.2460 1.2942 1.2621 1.2642 1.80 1.2388 1.2779 1.2490 1.2544 2.00 1.2284 1.2628 1.2356 1.2439 2.20 1.2176 1.2456 12188 1.2298 2.40 1.2102 1.2323 1.2103 1.2174 2.60 1.1998 1.2154 1.2033 1.2013 2.80 1.1915 1.2017 1.1991 11873 3.00 1.1841 11993 1.1941 1.1743 3.20 11755 1.1954 1.1865 11701 140 1.1678 1.1904 1.1795 1.1693 3.60 11615 11831 1.1709 1.1689 3.80 11562 1.1770 1.1626 1.1681 4.00 1.1498 11697 1.1541 1.1662 4.20 1.1452 1.1611 11435 1.1759 4.40 1.1448 1.1522 1.1335 1.1867 4.60 1.1431 1.1413 11349 1.1962 4.80 1.1402 1.1314 1.1367 1.2027 5.00 1.1376 1.1210 1.1378 1.2082 5.20 11346 1.1089 1.1368 1.2120 5.40 1.1304 1.1163 1.1378 1.2147 5.60 1.1301 1.1227 1.1396 1.2317 5.80 1.1376 1.1286 1.1569 1.2486 6.00 11433 1.1329 1.1716 1.2615 6,20 1.1471 1.1354 1.1842 1.2716 6.40 1.1497 1.1384 1.1952 1.2783 6.60 1.1502 1.1397 1.2043 1.2800 680 11500 1.1412 1.2102 1.2808 700 1.1496 1.1437 1.2137 1.2776 7.20 1.1508 1.1473 1.2141 1.2695 7.40 1.1511 1.1510 1.2129 1.2606 7.60 1.1482 1.1533 1.2089 12461 7.80 11448 1.1566 1.2037 1.2315 8.00 1.1401 11605 1.1954 1.2178 8.20 1.1340 1.1633 1.1872 1.2003 8.40 1.1430 1.1640 1.1875 11884 8.60 1.1555 1.1618 1.1904 1.1878 8.80 1.1646 1.1591 1.1917 1.1881 9.00 1.1670 1.1641 1.1925 11872 9.20 1.1661 1.1693 1.1909 1.1831 9.40 1.1589 1.1726 1.1897 1.2132 9.60 1.1618 1.1820 1.1878 1.2587 9.80 1.1643 1.1915 1.2061 1.2987 10.00 1.1659 1.2009 1.2342 1.3371 10,20 1.1661 1.2106 1.2593 1.3746 10.40 1.1808 1.2197 1.2801 1.4061 10.60 1.2015 1.2289 1.2970 1.4312 10.80 1.2172 1.2391 1.3108 1.4498 11.00 1.2288 1.2445 1.3207 1.4613 1110 1.2110 1.2613 1.3139 1.4499 11.40 1.2335 1.2734 1,3173 1.4347 11.60 1.2398 1.2797 1.2907 1.4163 11.80 1.2468 1.2874 1,2792 1.4026 12.00 (core top) 1.2580 1.3041 1,2733 1.3924 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 I Revision 8 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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-1 0216)

Height (feet) 18000 MWD/MTU 20000 MWD/MTU 24301 MWD/MTU 0.00 (core bottom) 1.2119 1.1887 1.1887 0.20 1.1953 1.1839 1.1839 0.40 1.1855 1.1766 1.1766 0.60 1.1813 1.1716 1.1716 0.80 1.1718 1.1704 1.1704 1.00 1.1682 1.1677 1.1677 1.20 1.1596 1.1640 1.1640 1.40 1.1522 1.1590 1.1590 1.60 1.1418 1.1511 1.1511 1.80 1.1361 1.1447 1.1447 2.00 1.1324 1.1375 1.1375 2.20 1.1271 1.1282 1.1282 2.40 1.1218 1.1196 1.1196 2.60 1.1178 1.1135 1.1135 2.80 1.1153

1. 1088 1.1088 3.00 1.1150 1.1083 1.1083 3.20 1.1171 1.1135 1.1135 3.40 1.1213 1.1237 1.1237 3.60 1.1298 1.1383 1.1383 3.80 1.1393 1.1517 1.1517 4.00 1.1496 1.1640 1.1640 4.20 1.1597 1.1759 1.1759 4.40 1.1683 1.1867 1.1867 4.60 1.1755 1.1962 1.1962 4.80 1.1805 1.2027 1.2027 5.00 1.1844 1.2082 1.2082 5.20 1.1861 1.2120 1.2120 5.40 1.1872 1.2147 1.2147 5.60 1.1970 1.2317 1.2317 5.80 1.2144 1.2486 1.2486 6.00 1.2276 1.2615 1.2615 6.20 1.2383 1.2716 1.2716 6.40 1.2471 1.2783 1.2783 6.60 1.2524 1.2800 1.2800 6.80 1.2556 1.2808 1.2808 7.00 1.2555 1.2776 1.2776 7.20 1.2509 1.2695 1.2695 7.40 1.2451 1.2606 1.2606 7.60 1.2347 1.2461 1.2461 7.80 1.2236 1.2315 1.2315 8.00 1.2114 1.2178 1.2178 8.20 1.1969 1.2003 1.2003 8.40 1.1903 1.1884 1.1884 8.60 1.1914 1.1878 1.1878 8.80 1.1924
1. 1881 1.1881 9.00 1.1920 1.1872 1.1872 9.20 1.1885 1.1831 1.1831 9.40 1.2049 1.2132 1.2132 9.60 1.2292 1.2587 1.2587 9.80 1.2606 1.2987 1.2987 10.00 1.2956 1.3371 1.3371 10.20 1.3286 1.3746 1.3746 10.40 1.3565 1.4061 1.4061 10.60 1.3788 1.4312 1.4312 10.80 1.3957 1.4498 1.4498 11.00 1.4068 1.4613 1.4613 11.20 1.3952 1.4499 1.4499 11.40 1.3884 1.4347 1.4347 11.60 1.3638 1.4163 1.4163 11.80 1.3492 1.4026 1.4026 12.00 (core top) 1.3388 1.3924 1.3924 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 I Revision 8 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup (MWD/MTU)

Penalty Factor FcQ(z) 0 1.0320 150 1.0320 496 1.0420 669 1.0460 842 1.0465 1015 1.0455 1188 1.0435 1361 1.0400 2052 1.0202 15888 1.0200 16061 1.0201 17099 1.0260 17272 1.0270 17964 1.0288 18482 1.0294 18828 1.0287 19347 1.0269 19866 1.0245 20039 1.0200 24301 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 1 Revision 8 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH (LCO 3.2.2) 2.7.1 FNaH <_ FRHP[1.0 + PF,H(1.0 - P)]

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

2.7.2 Uncertainty

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

UFAH = UFAHm where:

UFJH, = Base FNaH measurement uncertainty = 1.04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN,H Warning Setpoint = 2 % FNOH Margin FNaH Alarm Setpoint = 0% FNOH 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 8 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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 120 100 Unacc ptable 80 Ope ation 60 t

4cepta le dperation Una' ceptable Oeratioi 40

(-3^, 50)1

+25, 91 20 40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON I Revision 8 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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 120 100 0,100)

(+10,100)

Unacceptable Unacceptable Operation Operation Acceptable Operation

(-20, 50)

(+25, 50) 80 60 40 I

20 0

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON I Revision 8 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 19 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 T4 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 1 Revision 8 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 Tavg rate/lag coefficient K5 shall be equal to 0.02 / °F for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / °F for decreasing Tavg.

2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / °F when T > T".

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 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 Tj shall be equal to 8 sec.

2.11.8 The measured reactor vessel AT lead/lag time constant T2 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 T6 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 1 Revision 8 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 19 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 (Tavg) 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 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 Section Conditions Boron Concentration gpm) 2.13.1 Refueling (prior to initial criticality) 1693 2.13.2 a) prior to initial criticality 1772 2.13.2 b) all other times in life 1987

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