ML18291B090

Submittal of Core Operating Limits Report, Braidwood Unit 2 Cycle 21

ML18291B090
Person / Time
Site:	Braidwood
Issue date:	10/18/2018
From:	Marchionda-Palmer M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW180107
Download: ML18291B090 (17)

Text

Exelon Generation LLC Braklwood Station 35100 Sou!h Route 53, Suite 84 Braceville, IL 00407-9619 WWil!.exeloncom.com October 18, 2018 BW180107 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Renewed Facility Operating License No. NPF-77 NRC Docket No. STN 50-457

Subject:

Core Operating Limits Report, Braidwood Unit 2 Cycle 21 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 21 in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 2 Cycle 21 COLR, Revision 11 was implemented during Braidwood Unit 2 Refueling Outage 20 (A2R20) in support of Cycle 21 operation. Note that the revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLR, i.e., Braidwood Unit 2 Cycle 20, Revision 10.

If you have any questions regarding this matter, please contact Mr. Francis Jordan, Regulatory Assurance Manager, at (815) 417-2800.

Sincerely,

/Auw.J ~*/(}Jr-Marri Marchionda-Palmer Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 21, Revision 11 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector- Braidwood Station NRC Project Manager, NRR - Braidwood and Byron Stations

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 21 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 11

COLR BRAIDWOOD 2 Revision 11 Page 1of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 21 has been prepared in accordance with the requirements of Technical Specification 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)

LCO 3.1.1 SHUTDOWN MARGIN (SOM)

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 (F0 (Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)

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 (BOPS)

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 (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 (SOM) - MODE 1 and MODE 2 with keff ~ 1.0 TRM TLCO 3.1.i Shutdown Margin (SOM) - MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1.k Position Indication System - Shutdown (Special Test Exception)

COLR BRAIDWOOD 2 Revision 11 Page2 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 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 Safetv Limits CSLs) (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.

660 2471 psia t:="

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(1) 0 Q) lo- 640

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0 0.2 0.4 Q.6 Q.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 2 Revision 11 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.2 SHUTDOWN MARGIN (SOM)

The SOM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SOM 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 SOM limit for MODE 5 is:

2.2.2 SOM 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 CMTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOUARO/HZP-MTC upper limit shall be +1.406 x 10-5 Ak/k/°F.

2.3.2 The EOUARO/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 EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be-4.3x10-4 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) 226 111 227 112 228 113 229 114

COLR BRAIDWOOD 2 Revision 11 Page4 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Figure 2.5.1 :

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) r r 220 200 /

/ /

v 180 ~

VcsANKB I

~

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- ./

c

~ 160

/ (100%, 161) i SI: 140 1(0%, 162)

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v /

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60 40

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• '"ICO%, 47> I ~

v 20

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

COLR BRAIDWOOD 2 Revision 11 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.6 Heat Flux Hot Channel Factor (Fg,{Zll (LCO 3.2.1) 2.6.1 Total Peaking Factor:

pRTP FQ(Z) ~-Q-xK(Z) forP ~0.5 0.5 pRTP FQ (Z) ~ _Q_xK(Z) for P > 0.5 p

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~TP = 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) - Normalized Fa(Z) as a Function of Core Height 1.1 I I Ico.o, 1.0) I I(6.o, 1.0) I 1

c12.o,o.924) I

~

0.9 0.8 N" 0.7

,,~

-~ 0.6 ii E0 0.5 z

8: ..,._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 BRAIDWOOD 2 Revision 11 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 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, 5000, 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, 5000, 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 Fea(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fwa(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, UFa. to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula where:

Uqu = Base Fa 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:

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

COLR BRAIDWOOD 2 Revision 11 Page 7 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Table 2.8.2.a W(Z) varaua Cora Haight for Nonna! AFD Accaptable Operation Umlta In Figura 2.8.1.a (Top and Bottom 8% Excluded perWCAP-10216)

Haight 150 5000 14000 20000 (fHt) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2041 1.3414 1.2543 1.2321 0.20 1.1972 1.3126 1.2303 1.2159 0.40 1.1924 1.2975 1.2273 1.2015 0.60 1.1839 1.2816 1.2158 1.1943 0.80 1.1754 1.2853 1.1983 1.1921 1.00 1.1631 1.2504 1.1865 1.1880 1.20 1.1630 1.2416 1.1621 1.1822 1.40 1.1584 1.2270 1.1no 1.1761 1.60 1.1460 1.2102 1.1704 1.1667 1.80 1.1367 1.1955 1.1643 1.1580 2.00 1.1358 1.1807 1.1582 1.1476 2.20 1.1330 1.1633 1.1495 1.1351 2.40 1.1311 1.14n 1.1411 1.1239 2.60 1.1273 1.1313 1.1307 1.1219 2.80 1.1235 1.1294 1.1223 1.1198 3.00 1.1196 1.1266 1.1181 1.1178 3.20 1.1138 1.1240 1.1123 1.1148 3.40 1.1090 1.1221 1.1105 1.1252 3.60 1.1093 1.1182 1.1161 1.1403 3.60 1.1133 1.1153 1.1204 1.1546 4.00 1.1171 1.1104 1.1236 1.1677 4.20 1.1199 1.1065 1.1278 1.1797 4.40 1.1226 1.1049 1.1302 1.1903 4.60 1.1243 1.1030 1.1324 1.1980 4.60 1.1249 1.1013 1.1341 1.2054 5.00 1.1252 1.0994 1.1364 1.2100 5.20 1.1248 1.0956 1.1362 1.2134 5.40 1.1235 1.0929 1.1396 1.2148 5.60 1.1211 1.0692 1.1481 1.2325 5.60 1.1178 1.0857 1.1637 1.2488 6.00 1.1217 1.0945 1.1783 1.2615 6.20 1.1284 1.1041 1.1870 1.2711 6.40 1.1352 1.1128 1.1966 12n0 6.80 1.1389 1.1205 1.2024 1.2796 6.80 1.1427 1.1282 1.2062 1.2794 7.00 1.1445 1.1339 1.2081 1.2762 7.20 1.1459 1.1408 1.2050 1.2681 7.40 1.1494 1.1489 1.2019 1.2581 7.60 1.1522 1.1562 1.1921 1.2432 7.80 1.1551 1.1625 1.1851 1.2283 8.00 1.1609 1.1673 1.1782 1.2105 8.20 1.1687 1.1711 1.1703 1.1888 8.40 1.1715 1.1739 1.1690 1.1780 8.80 1.1758 1.1748 1.1861 1.1868 8.80 1.1791 1.1880 1.1861 1.1846 9.00 1.1814 1.1978 1.1846 1.1629 9.20 1.1655 1.2123 1.1606 1.1637 9.40 1.2038 1.2284 1.1868 1.2010 9.80 1.2189 1.2401 1.1880 1.2460 9.80 1.2222 1.2525 1.2220 1.2860 10.00 1.2228 1.2595 1.2520 1.3200 10.20 1.2200 1.2851 1.2780 1.3510 10.40 1.2164 1.2715 1.2890 1.3770 10.60 1.2350 1.2794 1.3041 1.4on 10.60 1.2463 1.2850 1.3199 1.4305 11.00 1.2515 1.2896 1.3307 1.4473 11.20 1.2515 1.2987 1.3305 1.4332 11.40 1.2569 1.3114 1.3294 1.4211 11.60 1.2598 1.3145 1.3163 1.4191 11.80 1.2647 1.3193 1.3083 1.4179 12.00 (core top) 1.2743 1.3330 1.3030 1.4147 Note: W(Z) values at 20000 MWD/MTU may be appUed to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) fUncUon extrapolation

COLR BRAIDWOOD 2 Revision 11 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Table 2.B.2.b W(Z) ve111ua Core Height for Expanded AFD Acceptable Ope111tlon Umtts In Ftgu... 2.8.1.b ffop and Bottom 8% Excluded parWCAP-10218)

Height 150 5000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom\ 1.3854 1.4825 1.4049 1.3397 0.20 1.3550 1.4482 1.3782 1.3343 0.40 1.3492 1.4305 1.3724 1.3287 0.80 1.33n 1.4108 1.3581 1.3230 0.80 1.3282 1.3934 1.3383 1.3185 1.00 1.3098 1.3758 1.3211 1.3121 1.20 1.3073 1.3851 1.2982 1.3037 1.40 1.3008 1.3474 1.2791 1.2953 1.60 1.2843 1.3280 1.2611 1.2830 1.80 1.2697 1.3074 1.2459 1.2718 2.00 1.2543 1.2878 1.2308 1.2583 2.20 1.2370 1.2843 1.2192 1.2422 2.40 1.2215 1.2427 1.2081 1.2281 2.80 1.2041 1.2192 1.2024 1.2079 2.80 1.1883 1.2002 1.1971 1.1902 3.00 1.1n3 1.1830 1.1911 1.1759 3.20 1.1887 1.1782 1.1823 1.1729 3.40 1.1818 1.1722 1.1750 1.1788 3.80 1.1524 1.1883 1.1854 1.1822 3.80 1.1469 1.1806 1.1554 1.1858 4.00 1.1420 1.1537 1.1469 1.1881 4.20 1.1357 1.1460 1.1415 1.1875 4.40 1.1294 1.1376 1.1359 1.1906 4.80 1.1291 1.1290 1.1363 1.1982 4.80 1.1296 1.1199 1.1365 1.2057 5.00 1.1292 1.1109 1.1384 1.2102 5.20 1.1278 1.1003 1.1382 1.2134 5.40 1.1252 1.0929 1.1398 1.2148 5.80 1.1218 1.0892 1.1481 1.2325 5.80 1.1178 1.0857 1.1837 1.2488 6.00 1.1217 1.0945 1.1763 1.2615 6.20 1.1284 1.1041 1.1870 1.2711 6.40 1.1352 1.1128 1.1988 1.2n8 6.80 1.1389 1.1205 1.2024 1.2796 6.80 1.1427 1.1282 1.2082 1.2794 7.00 1.1445 1.1339 1.2081 1.2762 7.20 1.1459 1.1408 1.2050 1.2881 7.40 1.1494 1.1489 1.2019 1.2581 7.80 1.1522 1.1582 1.1921 1.2432 7.80 1.1551 1.1625 1.1851 1.2283 8.00 1.1609 1.1673 1.1782 1.2105 8.20 1.1887 1.1711 1.1703 1.1888 8.40 1.1715 1.1739 1.1690 1.1780 8.60 1.1758 1.1748 1.1661 1.1668 8.80 1.1791 1.1880 1.1661 1.1846 9.00 1.1814 1.1978 1.1846 1.1829 9.20 1.1855 1.2123 1.1606 1.1837 9.40 1.2038 1.2284 1.1688 1.2010 9.80 1.2189 1.2401 1.1880 1.2460 9.80 1.2222 1.2525 1.2220 1.2880 10.00 1.2228 1.2595 1.2520 1.3200 10.20 1.2200 1.2851 1.2780 1.3510 10.40 1.2184 1.2715 1.2890 1.3nO 10.80 1.2350 1.2794 1.3041 1.4on 10.80 1.2463 1.2850 1.3199 1.4305 11.00 1.2515 1.2898 1.3307 1.4473 11.20 1.2515 1.2967 1.3305 1.4332 11.40 1.2569 1.3114 1.3294 1.4211 11.80 1.2598 1.3145 1.3183 1.4191 11.80 1.2847 1.3193 1.3063 1.4179 12.00 I core tool 1.2743 1.3330 1.3030 1.4147 Note: W(Z) values at 20000 MWD/MTU may be applied to cycla bumups greater than 20000 MWD/MTU to prevent W{Z) function extrapolation

COLR BRAIDWOOD 2 Revision 11 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor (MWD/MTU) F 'a(z) 150 1.0200 676 1.0370 1027 1.0450 1377 1.0490 1728 1.0450 2780 1.0200 13826 1.0200 14001 1.0214 14352 1.0215 14527 1.0215 15404 1.0210 15755 1.0208 16105 1.0208 16631 1.0212 16982 1.0217 17508 1.0225 18034 1.0225 18385 1.0218 18735 1.0205 18911 1.0200 Notes:

Linear interpolation is adequate for intermediate cycle bumups.

All cycle bumups 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 BRAIDWOOD 2 Revision 11 Page 10of15 CORE OPERATING LOOTS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.7 Nuclear Enthalpy Rise Hot Channel Factor CFNllli.l (LCO 3.2.2) 2.7.1 FNAH ~ F~;r[1.o + PFAH(1.0- P)]

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

F~;r =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:

where:

UFfrlm = Base FNaH measurement uncertainty = 1.04 when PDMS is inoperable (UFaHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

=

FNAH Warning Setpoint 2% FNAH Margin FNAH Alarm Setpoint = 0% FNAH Margin 2.8 AXIAL FLUX DIFFERENCE CAFD) (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 Normal AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.a. Prior to 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.

2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.

2.9 Departure from Nucleate Boiling Ratio CDNBR) (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 BRAIDWOOD 2 Revision 11 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Figure 2.8.1.a:

Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits with PDMS Inoperable 120 I (-10, 100) 1 I(+10, 100) I 100

/ \

a:

w 3: u ~accept< ble 0 Una cceptab e

a. 80

.... 1Dperatic n I \

01 >eration c:c

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w Acce1 1table \

c 60 Q

I Oper ation

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w i I I 40 I (-20, SO) I I (+2S, SO) I 0

~

20 0

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

COLR BRAIDWOOD 2 Revision 11 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Figure 2.8.1.b:

Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits with PDMS Inoperable 120 I (-1s, 100) I I (+10, 100) 1 100 a:

LI.I

~A. I I \ U1 accept; ble v

Una cceptab e 80

..... Jperatic n cc

E a:

01 1eration

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LI.I 60 Acce1 1table \

c Q

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\

LI.I

....~0 40 II (-35 SO) II I

I I I (+25, so) I

~

20 0

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

COLR BRAIDWOOD 2 Revision 11 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.10 Reactor Trip System CRTS> Instrumentation (LCO 3.3.1) - Overtemperature LiT Setpoint Parameter Values 2.10.1 The Overtemperature LiT reactor trip setpoint K1 shall be equal to 1.325.

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

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

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 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 LiT lead/lag time constant i:1 shall be equal to 8 sec.

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

2.10.8 The measured reactor vessel LiT lag time constant i:3 shall be less than or equal to 2 sec.

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

2.10.10 The measured reactor vessel average temperature lead/lag time constant i:5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant i:6 shall be less than or equal to 2 sec.

2.10.12 The f 1 (Lil) "positive" breakpoint shall be +10% Lil.

2.10.13 The f 1 (Lil) "negative" breakpoint shall be -18% Lil.

2.10.14 The f 1 (Lil} "positive" slope shall be +3.47% I % Lil.

2.10.15 The f 1 (Lil} "negative" slope shall be -2.61 % I % Lil.

COLR BRAIDWOOD 2 Revision 11 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.11 Reactor Trip System CRTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint ~ shall be equal to 1.072.

2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing T avg.

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

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

2.11.5 The Overpower AT reactor trip setpoint T avg heatup coefficient Ka shall be equal to 0 I °F whenTST".

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 i;1 shall be equal to 8 sec.

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

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

2.11.1 O The measured reactor vessel average temperature lag time constant i;6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant i;7 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 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 BRAIDWOOD 2 Revision 11 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.12 Reactor Coolant System CRCS} 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 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.

2.13.2 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 values given in the Table below.

COLR Boron Concentration Conditions Section (ppm) 2.13.1 a) prior to initial criticality 1705 b) for cycle bumups ~ 0 MWD/MTU and < 16000 MWD/MTU 1814 c) for cycle bumups ~ 16,000 MWD/MTU 1445 2.13.2 a) prior to initial criticality 1768 b) for cycle bumups ~ 0 MWD/MTU and <

2028 16000 MWD/MTU c) for cycle bumups ~ 16000 MWD/MTU 1583