Text

Cycle 20 Core Operating Limits Report
	ML16117A106
Person / Time
Site:	Byron
Issue date:	04/26/2016
From:	Kanavos M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BYRON 2016-0035
	Download: ML16117A106 (17)
	v • d • e

Byron Generating Station F

E xeton G enera t I 0 fl wwwexeloncorp.com Rd April 26, 2016 LTR: BYRON 201 6-0035 File: 2.01 .0300 (5A.101) 1.10.0101 (1D.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. STN 50-455

Subject:

Byron Station Unit 2 Cycle 20 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 8, for Cycle 20.

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

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

Attachment:

Byron Station Unit 2 Cycle 20, COLR, Revision 8 MEKIGC/sg cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 2 CYCLE 20 EXELON TRACKING ID:

COLR BYRON 2 REVISION 8

COLR BYRON 2 Revision $

Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON U1.TIT 2 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 20 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 (LCOs) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCD 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCD 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCD 3.1.8 PHYSICS TESTS Exceptions MODE 2 LCD 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCD 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH)

LCD 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCD 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCD 3.3.1 Reactor Trip System (RTS) Instrumentation LCD 3.3.9 Boron Dilution Protection System (BDPS)

LCD 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 (TRM) affected by this report are listed below:

TRM TLCD 3.1.b Boration Flow Paths Operating TRM TLCD 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 TLCD 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 $

Page 2 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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.

U CD CD S.

CD 0

F CD p

CD 0 0.2 0.4 0.6 0. 1 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 2 Revision $

Page 3 of 15 CORE OPERATING LEvIITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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 3DM 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 BOUARO/HZP-MTC upper limit shall be +2.721 x i0 AkIkI°F.

2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x i0 Ak/k/°F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x i0 Ak/kPF.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x i- Ak/kPF.

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 8 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 26.S2%, 224) (76.96%, 224 220 200 7

180

/ 7 (100%, 161) 1160 I(ofhot 163) 140 ________/

a 120 C

0

-100 0

a 7 %KDI_

x C

Cu 0

80

7. /

a: 60 0

40 4 /

20 (30%, 0)],/

0 .n uxftxgggwr nUsoflv UEEI nungrir 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

COLR BYRON 2 Revision $

Page 5 ofl5 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 2.6 Heat Flux Hot Channel Factor (FQfl fLCO 3.2.1) 2.6.1 Total Peaking Factor:

RTP F

FQ(Z) 9-xK(Z) forP0.5 RTP F

FQ(Z) xK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FTF= 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) - Normalized FQfZ) as a Function of Core Height 1.1 0J.0)]

1 (12.0,0.924) 0.9 0.8 0.7 LI.

0.6 oo.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 BOUOM Core Height (ft) TOP

COLR BYRON 2 Revision 8 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20

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 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, 5000, 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 FC0(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 UFQ = Uqu

Ue where:

Uqu = Base F0 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:

F0(Z) Warning Setpoint = 2% F0(Z) Margin F0(Z) Alarm Setpoint = 0% F0(Z) Margin

COLR BYRON 2 Revision 8 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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-1 0216)

Height 150 5000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWD!MTU 0.00 (core bottom) 1.3939 1.5083 1.3877 1.3456 0.20 1.3748 1.4558 1.3691 1.3355 0.40 1.3650 1.4434 1.3592 1.3329 0.60 1.3533 1.4285 1.3438 1.3302 0.80 1.3342 1.4182 1.3007 1.3254 1.00 1.3207 1.4008 1.2896 1.3188 1.20 1.3034 1.3591 1.2861 1.3097 1.40 1.2885 1.3440 1.2774 1.3007 1.60 1.2712 1.3283 1.2621 1.2873 1.80 1.2579 1.3124 1.2477 1.2753 2.00 1.2525 1.2962 1.2336 1.2613 2.20 1.2451 1.2813 1.2239 1.2428 2.40 1.2363 1.2621 1.2152 1.2263 2.60 1.2238 1.2411 1.2037 1.2066 2.80 1.2079 1.2199 1.1932 1.1888 3.00 1.1935 1.2077 1.1849 1.1755 3.20 1.1824 1.1982 1.1762 1.1715 3.40 1.1765 1.1929 1.1679 1.1734 3.60 1.1704 1.1852 1.1577 1.1786 3.80 1.1642 1.1786 1.1512 1.1822 4.00 1.1582 1.1716 1.1505 1.1852 4.20 1.1510 1.1623 1.1475 1.1878 4.40 1.1449 1.1529 1.1445 1.1998 4.60 1.1444 1.1426 1.1405 1.2099 4.80 1.1433 1.1320 1.1428 1.2177 5.00 1.1397 1.1218 1.1481 1.2240 5.20 1.1350 1.1151 1.1524 1.2274 5.40 1.1289 1.1138 1.1568 1.2303 5.60 1.1238 1.1179 1.1646 1.2473 5.80 1.1311 1.1240 1.1830 1.2651 6.00 1.1378 . 1.1281 1.2000 1.2787 6.20 1.1425 1.1308 1.2140 1.2874 6.40 1.1472 1.1360 1.2252 1.2954 6.60 1.1490 1.1411 1.2325 1.2965 6.80 1.1498 1.1434 1.2389 1.2967 7.00 1.1486 1.1461 1.2413 1.2929 7.20 1.1473 1.1511 1.2400 1.2843 7.40 1.1476 1.1550 1.2363 1.2734 7.60 1.1473 1.1605 1.2296 1.2584 7.80 1.1465 1.1664 1.2199 1.2416 8.00 1.1452 1.1660 1.2126 1.2231 8.20 1.1410 1.1658 1.2031 1.2026 8.40 1.1378 1.1653 1.1934 1.1879 8.60 1.1348 1.1646 1.1837 1.1743 8.80 1.1385 1.1660 1.1796 1.1673 9.00 1.1426 1.1661 1.1837 1.1666 9.20 1.1451 1.1790 1.1933 1.1858 9.40 1.1487 1.1996 1.2034 1.2362 9.60 1.1530 1.2183 1.2495 1.2856 9.80 1.1615 1.2370 1.2826 1.3280 10.00 1.1690 1.2536 1.3130 1.3638 10.20 1.1793 1.2690 1.3393 1.4005 10.40 1.1924 1.2849 1.3613 1.4279 10.60 1.2197 1.2948 1.3681 1.4505 10.80 1.2329 1.2962 1.3799 1.4671 11.00 1.2329 1.2890 1.3881 1.4805 1.20 1.2433 1.2698 1.3412 1.4699 1.40 1.2487 1.3068 1.4021 1.4788 1.60 1.2271 1.2748 1.3699 1.4428 1.80 1.2234 1.2788 1.3535 1.4267 12.00 (core top) 1.2244 1.2892 1.3399 1.4205 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWDIMTU to prevent W(Z) function extrapolation

COLR BYRON 2 Revision 8 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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 erWCAP-10216)

Height 18000 20000 23337 (feet) MWDIMTU MWDIMTU MWD1MTU 000 (core bottom) 1.2299 1.2430 1.2430 0.20 1.2130 1.2208 1.2208 0.40 1.2051 1.2127 1.2127 0.60 1.1962 1.2060 1.2060 0.80 1.1846 1.2040 1.2040 1.00 1.1749 1.1879 1.1879 1.20 1.1720 1.1819 1.1819 1.40 1.1677 1.1757 1.1757 1.60 1.1595 1.1660 1.1660 1.80 1.1529 1.1568 1.1566 2.00 1.1459 1.1458 1.1458 2.20 1.1342 1.1317 1.1317 2.40 1.1255 1.1187 1.1187 2.60 1.1179 1.1104 1.1104 2.80 1.1142 1.1065 1.1065 3.00 1.1137 1.1084 1.1084 3.20 1.1141 1.1131 1.1131 3.40 1.1205 1.1267 1.1267 3.60 1.1281 1.1441 1.1441 3.80 1.1356 1.1596 1.1596 4.00 1.1471 1.1745 1.1745 4.20 1.1592 1.1875 1.1875 4.40 1.1705 1.1995 1.1995 4.60 1.1795 1.2095 1.2095 4.80 1.1871 1.2174 1.2174 5.00 1.1936 1.2240 1.2240 5.20 1.1980 1.2274 1.2274 5.40 1.2019 1.2303 1.2303 5.60 1.2151 1.2473 1.2473 5.80 1.2340 1.2651 1.2651 6.00 1.2500 1.2787 1.2767 6.20 1.2617 1.2874 1.2874 6.40 1.2715 1.2954 1.2954 6.60 1.2754 1.2965 1.2965 6.80 1.2785 1.2967 1.2967 7.00 1.2773 1.2929 1.2929 7.20 1.2714 1.2843 1.2843 7.40 1.2630 1.2734 1.2734 7.60 1.2507 1.2584 1.2584 7.80 1.2358 1.2416 1.2416 8.00 1.2216 1.2231 1.2231 8.20 1.2051 1.2026 1.2026 8.40 1.1919 1.1879 1.1879 8.60 1.1794 1.1743 1.1743 8.80 1.1733 1.1673 1.1673 9.00 1.1749 1.1666 1.1666 9.20 1.1897 1.1858 1.1858 9.40 1.2219 1.2362 1.2362 9.60 1.2717 1.2856 1.2856 9.80 1.3110 1.3280 1.3280 10.00 1.3453 1.3638 1.3638 10.20 1.3783 1.4005 1.4005 10.40 1.4037 1.4279 1.4279 10.60 1.4195 1.4505 1.4505 10.80 1.4349 1.4671 1.4671 11.00 1.4472 1.4805 1.4805 11.20 1.4194 1.4699 1.4699 11.40 1.4519 1.4788 1.4786 11.60 1.4176 1.4428 1.4428 11.80 1.3999 1.4267 1.4267 12.00 (core top) 1.3888 1.4205 1.4205 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation

COLR BYRON 2 Revision $

Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 Table 2.6.2.c Penalty Factors in Excess of 2% ier 31 EFPD Cycle Burn up Penalty Factor (MWDIMTU) FCQ(Z) 0 1.0200 853 1.0210 1029 1.0230 1205 1.0410 1381 1.0425 1556 1.0410 1908 1.0360 2436 1.0320 3139 1.0270 3666 1.0200 11929 1.0200 12105 1.0202 12281 1.0200 13336 1.0200 13512 1.0201 13688 1.0205 13863 1.0209 14039 1.0211 14215 1.0205 14391 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 $

Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 2.7 Nuclear Enthalpy Rise Hot Channel Factor (F-,H (LCO 3.2.2) 2.7.1 FH F[1.0 ÷ PFAH(l.O P)] -

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

FRTP PFH = 0.3

2.7.2 Uncertainty

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

UFH = UFHm where:

UF4Hm = Base FNAH measurement uncertainty = 1.04 when PDMS is inoperable (UFHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FH Warning Setpoint = 2% FH 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 MWDIMTU. 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 1.563 The Axial Power Shape Limiting DNBR (DNBRAPSC) 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 $

Page 11 oflS CORE OPERATING LIIvIITS REPORT (COLR) for BYRON UMT 2 CYCLE 20 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 w

o 0

80

-J 60 I-LU I

40 20 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (3/4)

COLR BYRON 2 Revision $

Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 Figure 2.8.1.b:

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

Axial Flux Difference Limits with PDMS Inoperable 120

(-10,100) (+10, 100) 100 7

IL w

Unacceptable UnacceptabIe 0

o 80 Opration Operation

-J Acceptable U Operation i 60 I

U I (-20, 50) (+25, 50) 40 20 0

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

COLR BYRON 2 Revision $

Page 13 ofl5 CORE OPERATING LIIvIITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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 1<1 shall be equal to 1.325.

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

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135/ psi.

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

2.10.7 The measured reactor vessel AT lead/lag time constant r2 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 r5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant r5 shall be less than or equal to 2 sec.

2.10.12 Thef1 (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% / % Al.

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

COLR BYRON 2 Revision 8 Page 14 of 15 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UMT 2 CYCLE 20 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 I F for increasing Tavg 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I F for decreasing Tavg.

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

2.11.5 The Overpower AT reactor trip setpointTavg heatup coefficient K6 shall be equal to 0IFwhenlT.

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 r1 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 r3 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.

COLRBYRON2 Revision 8 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 20 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 (Iavg) 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 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 fIRM 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 (ppm) 2.13.1 a) prior to initial criticality 1733 b) for cycle burnups 0 MWD/MTU 1794 and < 16000 MWD/MTU c) for cycle burnups 16000 MWD/MTU 1387 2.13.2 a) prior to initial criticality 1759 b) for cycle burnups 0 MWD/MTU and < 16000 MWD/MTU 1943 c)forcycleburnups 16000 1480 MWD/MTU