BYRON 2019-0040, Cycle 22 Core Operating Limits Report

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Cycle 22 Core Operating Limits Report
ML19105A023
Person / Time
Site: Byron Constellation icon.png
Issue date: 04/15/2019
From: Kanavos M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2019-0040
Download: ML19105A023 (17)
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Text

Byron Generating Station

. 4450 North German Church Road Exe[onGeneration

,ZEE April 15, 2019 LTR: BYRON 2019-0040 File: 2.01.0300 (5A.101) 1.10.0101 (YD.101)

United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 2 Renewed Facility Operating License No. NPF-66 NRC Docket No. SIN 50-455

Subject:

Byron Station Unit 2 Cycle 22 Core Operating Limits Report In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR),

we are submiffing the Unit 2 COLR, Revision 1 1 for Cycle 22.

Should you have any questions concerning this report, please contact Mr. Jonathan Cunzeman, Regulatory Assurance Manager, at (81 5) 406-2800.

Respectfully, Mark E. Kanavos Site Vice President Byron Generating Station

Attachment:

Byron Station Unit 2 Cycle 22, COLR, Revision 11 M EKWG/rm cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 22 EXELON TRACKING ID:

COLR BYRON 2 REVISION II

COLR BYRON 2 Revision 1 1 Page 1 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 to CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 22 has been prepared in accordance with the requirements of Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCO5) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (5DM)

LCO 3.1 .3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod GroupAlignment 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 (FH)

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 T echnical Requirements Manual (TRM) 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 (5DM) MODE I and MODE 2 with keff I .0 TRM TLCO 3.1.i Shutdown Margin (5DM) 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 11 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 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 I 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.

fl O) 2471 psia

%&D 2250 psia ...

c. . . ... .:... * . .

2000 pia o psii 5?

(2)

(12  :::::

6 J c  ! t I 1 0.2 3.4 O% 0.8 1 1.2 f:rac ion of NcrrinI Poer Figure 2.1 .1 : Reactor Core Limits

COLRBYRON2 Revision I 1 Page3 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.2 SHUTDOWN MARGIN (5DM)

The 5DM hmit for MODES I 2, 3, and 4 is:

2.2.1 The 5DM shall be greaterthan or equal to I .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 5DM limit for MODE 5 is:

2.2.2 SDM shall be greater than or equal to I .3% Ak/k (LCO 3.1 .1 LCO 3.3.9; TRM TLCOs 3.1 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 BOL/ARO/HZP-MTC upper limit shall be +1.605 x io AkIkJ°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 1O Ak/kI°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1O AkIkI°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x iO 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 (LCD 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

2.5 Control Bank Insertion Limits (LCD 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)J 228 113 I

COLR BYRON 2 Revision 1 1 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Figure %51:

Control Bank Insertion UmEts Versus Percent Rated Thermal Power (27%, 224) (77%, 224) 220 200 180 16O (100%, 161)

-C i4o I

100 0

0 120

-x C

80 C

0 60 20 0

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

The bank position is given as follows:

Control Bank D: (161170) (P-100) + 161 (for 30 P 100)

Where P is defined as the core power (in percent).

COLR BYRON 2 Revision 1 1 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.6 Heat Flux Hot Channel Factor (FQ(Z)) (LCO 32.1) 2.6.1 Total Peaking Factor:

RIP F

FQ(Z) xK(Z) forPO.5 RTP F

FQ(Z) xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FcTF= 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 1

(12.0,0.924) I 0.9 0.8 RI 0.7 a

U-

-C 0.6 0.5 LOCA Limiting 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 2 Revision 1 1 Page 6 of I 5 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (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 that correspond to the NORMAL 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. The Normal AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.
2) Table 2.6.2.b are the Expanded normal operation W(Z) values that correspond to the EXPANDED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1 .b. The Expanded normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU. The Expanded AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

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 (ff9 Uq,j

  • Ue where:

Uqu Base FQ measurement uncertainty = I .05 when PDMS is inoperable (Uqu 5 defined by PDMS when OPERABLE.)

Ue Engineering uncertainty factor = I .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 1 1 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Table 2.6.2.a W(Z) versus Core Height for Normal AFD Acceptable Operation Limits in Figure 2.8.1 a (Top and Bottom 8% Excluded per WCAP-1 0216)

Height 150 6000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWD/MTU 0.00(corebottom) 1.2169 1.3243 1.2310 1.1912 0.20 1.2037 1.2989 1.2109 1.1861 0.40 1.1976 1.2896 1.2025 1.1854 0.60 1.1900 1.2782 1.1927 1.1846 0.80 1.1835 1.2347 1.1672 1.1865 1.00 1.1744 1.2164 1.1576 1.1831 1.20 1.1642 1.2298 1.1545 1.1780 1.40 1.1581 1.2157 1.1514 1.1720 1.60 1.1532 1.1998 1.1473 1.1629 1.80 1.1483 1.1857 1.1432 1.1544 2.00 1.1460 1.1726 1.1398 1.1449 2.20 1.1451 1.1570 1.1342 1.1321 2.40 1.1410 1.1439 1.1291 1.1195 2.60 1.1370 1.1300 1.1241 1.1047 2.80 1.1330 1.1222 1.1214 1.1017 3.00 1.1290 1.1210 1.1186 1.1057 3.20 1.1250 1.1184 1.1128 1.1088 3.40 1.1230 1.1151 1.1107 1.1128 3.60 1.1210 1.1111 1.1139 1.1227 3.80 1.1231 1.1074 1.1194 1.1373 4.00 1.1268 1.1033 1.1237 1.1510 4.20 1.1294 1.1017 1.1313 1.1653 4.40 1.1320 1.1003 1.1392 1.1768 4.60 1.1327 1.0984 1.1460 1.1886 4.80 1.1333 1.0966 1.1509 1.1969 5.00 1.1327 1.0937 1.1552 1.2032 5.20 1.1313 1.0908 1.1575 1.2086 5.40 1.1287 1.0869 1.1588 1.2107 5.60 1.1252 1.0838 1.1594 1.2303 5.80 1.1217 1.0815 1.1612 1.2479 6.00 1.1246 1.0911 1.1748 1.2635 6.20 1.1313 1.1006 1.1865 1.2742 6.40 1.1370 1.1102 1.1962 1.2819 6.60 1.1417 1.1178 1.2020 1.2846 6.80 1.1445 1.1245 1.2068 1.2854 7.00 1.1433 1.1314 1.2086 1.2822 7.20 1.1420 1.1394 1.2056 1.2742 7.40 1.1463 1.1478 1.2045 1.2662 7.60 1.1486 1.1546 1.2004 1.2541 7.80 1.1503 1.1609 1.1964 1.2431 8.00 1.1511 1.1662 1.1914 1.2292 8.20 1.1498 1.1721 1.1855 1.2123 8.40 1.1481 1.1770 1.1828 1.1965 8.60 1.1492 1.1793 1.1808 1.1815 8.80 1.1549 1.1812 1.1810 1.1836 9.00 1.1592 1.1853 1.1792 1.1838 9.20 1.1644 1.1980 1.1759 1.1801 9.40 1.1672 1.2182 1.1829 1.2188 9.60 1.1700 1.2373 1.1873 1.2605 9.80 1.1733 1.2561 1.2150 1.3001 10.00 1.1816 1.2726 1.2390 1.3367 10.20 1.1900 1.2870 1.2630 1.3694 10.40 1.1968 1.3015 1.2770 1.3991 10.60 1.2076 1.3141 1.2873 1.4229 10.80 1.2174 1.3236 1.3002 1.4387 11.00 1.2215 1.3305 1.3100 1.4485 11.20 1.2307 1.3378 1.3088 1.4474 11.40 1.2345 1.3516 1.3057 1.4403 11.60 1.2315 1.3536 1.2807 1.4113 11.80 1.2328 1.3568 1.2676 1.3972 1 2.00 (core top) 1 .2394 1 .3705 1 .2593 1.3870 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 1 1 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-1 0216)

Height 150 6000 14000 20000 (feet) MWD/MTU MWDIMTU MWDIMTU MWD/MTU 0.00 (core bottom) 1.3680 1.4936 1.3837 1.3263 0.20 1.3510 1.4604 1.3583 1.3182 0.40 1.3430 1.4477 1.3480 1.3165 0.60 1.3330 1.4341 1.3357 1.3144 0.80 1.3230 1.3833 1.3056 1.3152 1.00 1.3110 1.3588 1.2916 1.3098 1.20 1.2970 1.3698 1.2666 1.3017 1.40 1.2840 1.3503 1.2534 1.2934 1.60 1.2690 1.3279 1.2380 1.2813 1.80 1.2680 1.3084 1.2312 1.2701 2.00 1.2680 1.2879 1.2257 1.2579 2.20 1.2800 1.2635 1.2176 1.2411 2.40 1.2430 1.2429 1.2108 1.2252 2.60 1.2250 1.2186 1.2022 1.2065 2.80 1.2080 1.1994 1.1941 1.1896 3.00 1.1910 1.1841 1.1850 1.1760 3.20 1.1767 1.1789 1.1735 1.1622 3.40 1.1732 1.1739 1.1654 1.1626 3.60 1.1681 1.1678 1.1618 1.1673 3.80 1.1635 1.1618 1.1603 1.1702 4.00 1.1579 1.1547 1.1593 1.1730 4.20 1.1509 1.1461 1.1567 1.1747 4.40 1.1443 1.1381 1.1539 1.1768 4.60 1.1357 1.1280 1.1491 1.1886 4.80 1.1333 1.1184 1.1509 1.1969 5.00 1.1327 1.1083 1.1552 1.2032 5.20 1.1313 1.0968 1.1575 1.2086 5.40 1.1287 1.0869 1.1588 1.2107 5.60 1.1252 1.0838 1.1594 1.2303 5.80 1.1217 1.0815 1.1612 1.2479 6.00 1.1246 1.0911 1.1748 1.2635 6.20 1.1313 1.1006 1.1865 1.2742 6.40 1.1370 1.1102 1.1962 1.2819 6.60 1.1417 1.1178 1.2020 1.2846 6.80 1.1445 1.1245 1.2068 1.2854 7.00 1.1433 1.1314 1.2086 1.2822 7.20 1.1420 1.1394 1.2056 1.2742 7.40 1.1463 1.1478 1.2045 1.2662 7.60 1.1486 1.1546 1.2004 1.2541 7.80 1.1503 1.1609 1.1964 1.2431 8.00 1.1511 1.1662 1.1914 1.2292 8.20 1.1498 1.1721 1.1855 1.2123 8.40 1.1481 1.1770 1.1828 1.1965 8.60 1.1492 1.1793 1.1808 1.1815 8.80 1.1549 1.1812 1.1810 1.1836 9.00 1.1592 1.1853 1.1792 1.1838 9.20 1.1644 1.1980 1.1759 1.1801 9.40 1.1672 1.2182 1.1829 1.2188 9.60 1.1700 1.2373 1.1873 1.2605 9.80 1.1733 1.2561 1.2150 1.3001 10.00 1.1816 1.2726 1.2390 1.3367 10.20 1.1900 1.2870 1.2630 1.3694 10.40 1.1968 1.3015 1.2770 1.3991 10.60 1.2076 1.3141 1.2873 1.4229 10.80 1.2174 1.3236 1.3002 1.4387 11.00 1.2215 1.3305 1.3100 1.4485 11.20 1.2307 1.3378 1.3088 1.4474 11.40 1.2345 1.3516 1.3057 1.4403 11.60 1.2315 1.3536 1.2807 1.4113 11.80 1.2328 1.3568 1.2676 1.3972 12.00(coretop) ,..-. 1.2394 1.3705 1.2593 1.3870 Note: W(Z) values at uuuu ivivvuiivi I U may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BYRON 2 Revision I 1 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Table 2.6.2.c Penalty Factors in Excess of 2% er 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FCQ(Z) 150 1.0200 676 1.0340 1027 1.0400 1203 1.0413 2080 1.0290 2957 1.0370 3133 1.0360 3659 1.0310 4185 1.0200 11555 1.0200 11906 1.0226 13485 1.0269 14186 1.0270 15064 1.0255 16116 1.0230 17520 1.0305 18047 1.0336 18573 - 1.0335 19099 1.0285 19801 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

COLR BYRON 2 Revision I 1 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH) (LCO 3.22) 2.7.1 FNAH F[1.O + PFAH(1.O - P)]

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F= 1.70 PFAH = 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:

UFziHm = Base FNAH measurement uncertainty = I .04 when PDMS is inoperable (UFAHm 5 defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FH Warning Setpoint = 2% FNAH Margin FNAH Alarm Setpoint = 0% FNAH Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 The AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below.

a) Figure 2.8.1 .a is the Normal AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.a. Priorto changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.

b) Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.b.

2.9 Departure from Nucleate Boilinci Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL 1.563 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 I 1 Page H of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits 120 100 w

-I 60 I-w I-0 40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)

COLR BYRON 2 Revision 1 1 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits 120 100 LU 80 60 I-40 I

0 20 0

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

COLR BYRON 2 Revision 1 1 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature zT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactortrip setpoint Ki shall be equalto 1325.

2. 1 0.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature AT reactortrip setpoint pressure coefficientK3 shall be equal to 0.00135 I psi.

2.10.4 The nominal Tavgat RTP (indicated) T shall be less than or equalto 583.5 °F.

2.10.5 The nominal RCS operating pressure (indicated) P shall be equal to 2235 psig.

2.10.6 The measured reactor vessel z\T lead/lag time constant -ci shall be equal to 8 sec.

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

2. 1 0.8 The measured reactor vessel AT lag time constant t shall be less than or equal to 2 sec.
2. 1 0.9 The measured reactor vessel average temperature lead/lag time constant t4 shall be equal to 33 sec.
2. 1 0. 1 0 The measured reactor vessel average temperature lead/lag time constant t5 shall be equal to 4 sec.
2. 1 0. 1 1 The measured reactor vessel average temperature lag time constant t6 shall be less than or equal to 2 sec.

2.10.12 The fi (Al) positive breakpoint shall be +10% zl.

2.10.13 The fi (Al) negative breakpoint shall be -18% Al.

2.10.14 The fi (Al) positive slope shall be +3.47% / % Al.

2.10.15 The fi (Al) negative slope shall be -2.61% / % Al.

COLR BYRON 2 Revision 1 1 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 2.11 Reactor Trip System (RIS) Instrumentation (LCO 3.3.1) - Overpower XT Setpoint Parameter Values 2.11.1 The OverpowerAT reactortrip setpoint K4 shall be equalto 1.072.

2. 1 1 .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 z\T reactortrip setpoint Tavg rate/lag coefficient K shall be equal to 0 I °F for decreasing Tavg.

2. 1 1 .4 The Overpower z\T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245/°Fwhen T>T.

2.1 1 .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 583.5 °F.

2.11.7 The measured reactor vessel AT lead/lag time constant ri 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. 1 1 .9 The measured reactor vessel z\T 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. 1 1 I I

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

2. 1 1 I 2

. The f2 (Al) positive breakpoint shall be 0 for all Al.

2. 1 1 .1 3 The f2 (Al) negative breakpoint shall be 0 for all Al.

2.11.14 The f2(AI) positive slope shall be 0 forall Al.

2.11 .1 5 The f2 (Al) negative slope shall be 0 for all Al.

COLR BYRON 2 Revision 1 1 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 22 212 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 p51g.

2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 588.6 °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 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.

2.1 3.2 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 values given in the Table below.

COLR Boron Concentration

. Conditions Section (ppm)

2. 1 3. 1 a) prior to initial criticality 1729 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 1815 c) for cycle burnups 16,000 MWD/MTU 1426 2.13.2 a) priorto initial criticality 1769 b) for cycle burnups 0 MWD/MTU and <

2008 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1545

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