BW190021, Core Operating Limits Report Mid-Cycle Revision

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Core Operating Limits Report Mid-Cycle Revision
ML19066A022
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 03/07/2019
From: Marchionda-Palmer M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW190021
Download: ML19066A022 (34)
v • d • e


Text

March 7, 2019 BW190021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Core Operating Limits Report Mid-Cycle Revision

References:

1) Letter from D.M. Gullatt (Exelon Generation Company, LLC) to U.S. NRC, "License Amendment Request to Revise Technical Specification 3.2.3, 'Axial Flux Difference,"' dated April 2, 2018
2) Letter from U.S NRC to B.C. Hanson (Exelon Generation Company, LLC),

"Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 -

Issuance of Amendments Regarding Axial Flux Difference Technical Specifications (EPID L-2018-LLA-0098)," dated December 12, 2018 The purpose of this letter is to transmit mid-cycle Core Operating Limits Reports (COLRs) for Braidwood Station, Units 1 and 2 in accordance with Technical Specification (TS) 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 1 Cycle 21 COLR, Revision 15 and Braidwood Unit 2 Cycle 21 COLR, Revision 12 were implemented mid-cycle in support of Braidwood Station TS Amendment No. 200, issued December 12, 2018 with a 90-day implementation period (Reference 2). TS Amendment No. 200 addresses a nonconformance (i.e., a modeling error) discovered in the Fuel Rod Design (FRO) performance criteria verification analysis. To address this nonconformance, axial flux difference must be maintained within the limits specified in the COLR regardless of Power Distribution Monitoring System operability. Thus, the COLRs have been updated accordingly.

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

Sincerely, illPJW~~

Marri Marchionda-Palmer Site Vice President Braidwood Station Attachments: Core Operating Limits Report (COLR) for Braidwood Unit 1 Cycle 21, Revision 15 Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 21, Revision 12

cc:

NRG Regional Administrator, Region Ill NRG Senior Resident Inspector-Braidwood Station NRG Project Manager, NRR - Braidwood and Byron Stations

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 1 CYCLE 21 EXELON TRACKING ID:

COLR BRAIDWOOD 1REVISION15

COLR BRAIDWOOD 1 Revision 15 Page 1of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 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 (Fa(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN 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 (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 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 (SOM) - MODE 1 and MODE 2 with keff ~ 1.0 Shutdown Margin (SOM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)

COLR BRAIDWOOD 1 Revision 15 Page 2of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 Safety Limits (SLs) (SL 2.1.1) w_

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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 psia 660 640 620 600 580-1--'----'~...._-+-__..~...__----+----'~-'-......... -+~'------'---+~,__......... _._---I,.__...__,__,___,

0 0.2 0.4 0.6 0.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 1 Revision 15 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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 +1.884 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 -4.3 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) 226 111 227 112 228 113 229 114

COLR BRAIDWOOD 1 Revision 15 Page 4of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%, 224)

(77%, 224)

~

220 200 180 c

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(100%, 161) 20 1<30%.0)v 0

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

COLR BRAIDWOOD 1 Revision 15 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.6 Heat Flux Hot Channel Factor (Fa@ (LCO 3.2.1) 2.6.1 Total Peaking Factor:

pRTP F0 (Z) ~ xK(Z) for P ~ 0.5 0.5 pRTP F0 (Z) ~ 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.

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Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height (O.C 1.0)

(6.0 1.0)

(12.C 0.924)

...,_LOCA Limiting Envelope 0

1 2

3 4

5 6

7 8

9 10 11 12 BOTTOM Core Height (ft)

TOP

COLR BRAIDWOOD 1 Revision 15 Page 6of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 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, 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 Fe 0(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fw 0(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 F0(Z) shall be calculated by the following formula UFQ =Uqu *U.

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:

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

COLR BRAIDWOOD 1 Revision 15 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 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 perWCAP-10216)

Height 150 5000 14000 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.1893 1.2974 0.20 1.1798 1.2733 0.40 1.1767 1.2638 0.60 1.1717 1.2527 0.80 1.1355 1.2206 1.00 1.1284 1.1894 1.20 1.1539 1.2214 1.40 1.1529 1.2089 1.60 1.1443 1.1928 1.80 1.1367 1.1777 2.00 1.1297 1.1616 2.20 1.1216 1.1435 2.40 1.1145 1.1289 2.60 1.1064 1.1133 2.80 1.0993 1.0997 3.00 1.0927 1.0977 3.20 1.0878 1.0994 3.40 1.0877 1.1002 3.60 1.0885 1.1009 3.80 1.0934 1.1016 4.00 1.0983 1.1023 4.20 1.1024 1.1010 4.40 1.1055 1.1007 4.60 1.1086 1.0993 4.80 1.1107 1.0979 5.00 1.1 lll 1.0965 5.20 1.1114 1.0941 5.40 1.1197 1.0908 5.60 1.1273 1.0932 5.80 1.1339 1.0977 6.00 1.1406 1.1024 6.20 1.1453 l.1060 6.40 1.1491 l.1192 6.60 1.1517 1.1337 6.80 1.1525 1.1475 7.00 1.1524 1.1604 7.20 1.1527 1.1717 7.40 1.1663 1.1838 7.60 1.1789 l.1942 7.80 1.1908 1.2037 8.00 1.2018 1.2125 8.20 1.2118 1.2200 8.40 1.2219 1.2265 8.60 1.2294 1.2331 8.80 1.2369 1.2433 9.00 1.2444 1.2533 9.20 1.2492 1.2612 9.40 1.2546 1.2710 9.60 1.2576 1.2786 9.80 1.2564 1.2780 10.00 1.2485 1.2794 10.20 1.2428 1.2792 10.40 1.2312 1.2775 10.60 1.2201 1.2722 10.80 1.2260 1.2743 11.00 1.2297 1.2848 11.20 1.2460 1.2912 11.40 1.2565 1.3052 11.60 1.2573 1.3124 11.80 1.2599 1.3197 12.00 (core tool 1.2713 1.3389 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 1.2778 1.2629 1.2619 1.2509 1.2330 1.2207 1.2021 1.1909 1.1744 1.1725 1.1695 1.1686 1.1627 1.1557 1.1468 1.1379 1.1303 1.1255 1.1187 1.1190 1.1224 1.1267 1.1298 1.1319 1.1328 1.1344 1.1363 1.1385 1.1480 1.1645 1.1781 1.1888 1.1974 1.2032 1.2079 1.2097 1.2076 1.2036 1.1966 1.1887 1.1798 1.1679 1.1559 1.1504 1.1511 l.1518 l.1508 1.1559 1.1880 1.2220 1.2530 1.2810 1.3030 1.3220 1.3380 1.3410 1.3400 1.3320 1.3090 1.2923 1.2829 20000 MWD/MTU 1.2199 1.2129 1.2061 1.2054 1.2031 1.1997 1.1941 1.1874 1.1778 1.1688 1.1588 1.1452 1.1328 1.1172 1.1029 1.1017 1.1072 1.1175 1.1318 1.1451 1.1580 1.1709 1.1816 1.1912 1.1987 1.2045 1.2106 1.2142 1.2327 1.2493 1.2629 1.2715 1.2791 1.2808 1.2806 1.2775 1.2693 1.2603 1.2453 1.2304 1.2126 1.1908 1.1779 1.1737 1.1710 l.1679 1.1707 1.2050 1.2510 1.2910 1.3270 1.3590 1.3850 1.4107 1.4325 1.4463 1.4342 1.4221 1.4141 1.4099 1.4057

COLR BRAIDWOOD 1 Revision 15 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 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 perWCAP-10216)

Height 150 5000 14000 (feet}

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom}

1.3362 1.4231 0.20 1.3171 1.3949 0.40 1.3138 1.3847 0.60 1.3077 1.3726 0.80 1.2546 1.3375 1.00 1.2437 1.3068 1.20 1.2757 1.3357 1.40 1.2733 1.3206 1.60 1.2579 1.3001 1.80 1.2442 1.2811 2.00 1.2305 1.2611 2.20 1.2140 1.2368 2.40 1.1992 1.2160 2.60 1.1821 1.1934 2.80 1.1681 1.1764 3.00 1.1602 1.1721 3.20 1.1526 1.1678 3.40 1.1463 1.1635 3.60 1.1414 1.1578 3.80 1.1371 1.1519 4.00 1.1323 1.1456 4.20 1.1339 1.1374 4.40 1.1346 1.1296 4.60 1.1349 1.1204 4.80 1.1343 1.1116 5.00 1.1321 1.1032 5.20 1.1293 1.0990 5.40 1.1257 1.0943 5.60 1.1273 1.0932 5.80 1.1339 1.0977 6.00 1.1406 1.1024 6.20 1.1453 1.1060 6.40 1.1491 1.1192 6.60 1.1517 1.1337 6.80 1.1525 1.1475 7.00 1.1524 1.1604 7.20 1.1527 1.1717 7.40 1.1663 1.1838 7.60 1.1789 1.1942 7.80 1.1908 1.2037 8.00 1.2018 1.2125 8.20 1.2118 1.2200 8.40 1.2219 1.2265 8.60 1.2294 1.2331 8.80 1.2369 1.2433 9.00 1.2444 1.2533 9.20 1.2492 1.2612 9.40 1.2546 1.2710 9.60 1.2576 1.2786 9.80 1.2564 1.2780 10.00 1.2485 1.2794 10.20 1.2428 1.2792 10.40 1.2312 1.2775 10.60 1.2201 1.2722 10.80 1.2260 1.2743 11.00 1.2297 1.2848 11.20 1.2460 1.2912 11.40 1.2565 1.3052 11.60 1.2573 1.3124 11.80 1.2599 1.3197

12. 00 I core tool 1.2713 1.3389 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 1.4130 1.3940 1.3920 1.3790 1.3570 1.3420 1.3200 1.3060 1.2820 1.2690 1.2560 1.2400 1.2240 1.2093 1.1985 1.1876 1.1775 1.1718 1.1703 1.1683 1.1664 1.1629 1.1585 1.1535 1.1476 1.1406 1.1363 1.1385 1.1480 1.1645 1.1781 1.1888 1.1974 1.2032 1.2079 1.2097 1.2076 1.2036 1.1966 1.1887 1.1798 1.1679 1.1559 1.1504 l.15ll 1.1518 1.1508 1.1559 1.1880 1.2220 1.2530 1.2810 1.3030 1.3220 1.3380 1.3410 1.3400 1.3320 1.3090 1.2923 1.2829 20000 MWD/MTU 1.3383 1.3307 1.3298 1.3279 1.3232 1.3184 1.3098 1.3011 1.2885 1.2768 1.2642 1.2467 1.2320 1.2125 1.1949 1.1806 1.1688 1.1731 1.1764 1.1797 1.1810 1.1817 1.1816 1.1912 1.1987 1.2045 1.2106 1.2142 1.2327 1.2493 1.2629 1.2715 1.2791 1.2808 1.2806 1.2775 1.2693 1.2603 1.2453 1.2304 1.2126 1.1908 1.1779 1.1737 1.1710 1.1679 1.1707 1.2050 1.2510 1.2910 1.3270 1.3590 1.3850 1.4107 1.4325 1.4463 1.4342 1.4221 1.4141 1.4099 1.4057

Notes:

COLR BRAIDWOOD 1 Revision 15 Page 9of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU)

Fca(Z) 150 1.0200 500 1.0370 675 1.0460 851 1.0520 1027 1.0570 1201 1.0610 1376 1.0580 2602 1.0200 13460 1.0200 13635 1.0203 13986 1.0218 14162 1.0213 14861 1.0200 15387 1.0202 16613 1.0216 16963 1.0220 17488 1.0223 17663 1.0223 18014 1.0219 18714 1.0200 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 BRAIDWOOD 1 Revision 15 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21

2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN Atl1 (LCO 3.2.2) 2.7.1 FNAH ~ F~~P[1.0 + PFAH(1.0- P)]

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

F~~P = 1.70 PFAH = 0.3

2.7.2 Uncertainty

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

where:

UF&1m = Base FN AH measurement uncertainty = 1.04 when PDMS is inoperable (UFAHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN AH Warning Setpoint = 2% FN AH Margin FNAH Alarm Setpoint = 0% FN AH 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. 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.

2.9 Departure from Nucleate Boiling 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 BRAIDWOOD 1 Revision 15 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.a:

120 100 a::

LU

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a::

LU 60

c I-c LU ti a::

40 0

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20 0

-50 Una 01 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits I

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COLR BRAIDWOOD 1 Revision 15 Page 12of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 Figure 2.8.1.b:

120 100 a::

LU ;:

0 80

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LU 60

c I-c LU tt 40 a::....

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I Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits I

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COLR BRAIDWOOD 1 Revision 15 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 2.10 Reactor Trip System (RTS) Instrumentation {LCO 3.3.1) - Overtemperature fl T Setpoint Parameter Values 2.10.1 The Overtemperature fl T reactor trip setpoint K1 shall be equal to 1.325.

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

2.10.3 The Overtemperature fl T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I 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

  • 1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel AT lead/lag time constant *2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel AT lag time constant

  • 3 shall be less than or equal to 2 sec.

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

2.10.10 The measured reactor vessel average temperature lead/lag time constant *s shall be equal to 4 sec.

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

2.10.12 The f1 {Ill) "positive" breakpoint shall be +10% Ill.

2.10.13 The f1 {Ill) "negative" breakpoint shall be -18% Ill.

2.10.14 The f1 {Ill) "positive" slope shall be +3.47% I% Al.

2.10.15 The f1 {Al) "negative" slope shall be -2.61 % I% Ill.

COLR BRAIDWOOD 1 Revision 15 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 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 Ki 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 / °F for increasing Tavg*

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

2.11.4 The Overpower AT reactor trip setpoint T avg 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 when T :5: T".

2.11.6 The nominal T avg 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 -r7 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 BRAIDWOOD 1 Revision 15 Page 15of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE 21 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 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 (ppm) 2.13.1 a) prior to initial criticality 1700 b) for cycle burnups ~ 0 MWD/MTU 1799 and < 16000 MWD/MTU c) for cycle burnups ~ 16000 MWD/MTU 1448 2.13.2 a) prior to initial criticality 1767 b) for cycle burn ups ~ 0 MWD/MTU and < 16000 MWD/MTU 2028 c) for cycle burnups ~ 16000 1594 MWD/MTU

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 21 EXELON TRACKING ID:

COLR BRAIDWOOD 2 REVISION 12

COLR BRAIDWOOD 2 Revision 12 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 (SDM)

LCO 3.1.3 Moderator Temperature Coefficient {MTG)

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 (FN 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 (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 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 (SOM) - MODE 1 and MODE 2 with keff ~ 1.0 Shutdown Margin (SOM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)

COLR BRAIDWOOD 2 Revision 12 Page 2of15 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 NRG-approved methodologies specified in Technical Specification 5.6.5.

2.1 Reactor Core Safety Limits (SLs) (SL 2.1.1) l.J._

O"l Q) 0 ill

J

-I-'

a Q.)

o_

E Q.)

I-(])

CJ' 0

Q.)

-<(

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.

680 2471 psia 660 640 620 600 58Q-+--'--'--'--+--'----'----1.--f~'--.__..__+-......__.__._-+-_,__.__,_-+___..__..__.__,

0 0.2 0.4 Q.5 Q.8 1.2 Fraction of ~Jominol Power Figure 2.1.1: Reactor Core Limits

COLR BRAIDWOOD 2 Revision 12 Page 3of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.2 SHUTDOWN MARGIN (SOM)

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 (MTG) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTG) 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 104 Ak/k/°F.

2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak/k/°F.

2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 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 12 Page 4of15 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) 220 200 180 c ;: 160 "Cl

.c -

3: 140 U) a.

Cll -

!!!. 120 c

0

l "iii 0 100
a.

~

c RI Ill 80 "Cl 0 a:

60 40 20

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~

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r110%. 47) I

~

~v

,(30%.0)v (100%, 161) 0 0

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

COLR BRAIDWOOD 2 Revision 12 Page 5of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.6 Heat Flux Hot Channel Factor (Fg@ (LCO 3.2.1) 2.6.1 Total Peaking Factor:

1.1 1

0.9 0.8

- 0.7

~

a

u.

'tJ 0.6 cu

.~

iii E 0.5 0 z -

~ 0.4

~

0.3 0.2 0.1 0

FRTP FQ (Z) :$; _Q_x.K(Z) for P :$; 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 F~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 I

I co.o, 1.0) I 0

1 2

3 4

BOTTOM I

I (6.o, 1.0) I c12.o.o.924) I

-+-LOCA Limiting 5

6 7

Core Height (ft) 8 Envelope -

9 10 11 12 TOP

COLR BRAIDWOOD 2 Revision 12 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 Fe 0(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the Fw 0(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 UFQ=Uqu*U.

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:

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

COLR BRAIDWOOD 2 Revision 12 Page 7of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 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 perWCAP-10216)

Height 150 5000 14000 lfeetl MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2041 1.3414 0.20 1.1972 1.3126 0.40 1.1924 1.2975 0.60 1.1839 1.2816 0.80 1.1754 1.2653 1.00 1.1631 1.2504 1.20 1.1630 1.2416 1.40 1.1584 1.2270 1.60 1.1460 1.2102 1.80 1.1367 1.1955 2.00 1.1358 1.1807 2.20 1.1330 1.1633 2.40 1.1311 1.1477 2.60 1.1273 1.1313 2.80 1.1235 1.1294 3.00 1.1196 1.1266 3.20 1.1138 1.1240 3.40 1.1090 1.1221 3.60 1.1093 1.1182 3.80 1.1133 1.1153 4.00 1.1171 1.1104 4.20 1.1199 1.1065 4.40 1.1226 1.1049 4.60 1.1243 1.1030 4.80 1.1249 1.1013 5.00 1.1252 1.0994 5.20 1.1248 1.0956 5.40 1.1235 1.0929 5.60 1.1211 1.0892 5.80 1.1178 1.0857 6.00 1.1217 1.0945 6.20 1.1284 1.1041 6.40 1.1352 1.1128 6.60 1.1389 1.1205 6.80 1.1427 1.1282 7.00 1.1445 1.1339 7.20 1.1459 1.1408 7.40 1.1494 1.1489 7.60 1.1522 1.1562 7.80 1.1551 1.1625 8.00 1.1609 1.1673 8.20 1.1667 1.1711 8.40 1.1715 1.1739 8.60 1.1758 1.1748 8.80 1.1791 1.1860 9.00 1.1814 1.1978 9.20 1.1855 1.2123 9.40 1.2038 1.2264 9.60 1.2189 1.2401 9.80 1.2222 1.2525 10.00 1.2226 1.2595 10.20 1.2200 1.2651 10.40 1.2164 1.2715 10.60 1.2350 1.2794 10.80 1.2463 1.2850 11.00 1.2515 1.2896 11.20 1.2515 1.2987 11.40 1.2569 1.3114 11.60 1.2598 1.3145 11.80 1.2647 1.3193 12.00 !core tool 1.2743 1.3330 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 1.2543 1.2303 1.2273 1.2158 1.1983 1.1865 1.1821 1.1770 1.1704 1.1643 1.1582 1.1495 1.1411 1.1307 1.1223 1.1181 1.1123 1.1105 1.1161 1.1204 1.1238 1.1278 1.1302 1.1324 1.1341 1.1364 1.1382 1.1396 1.1481 1.1637 1.1763 1.1870 1.1966 1.2024 1.2062 1.2081 1.2050 1.2019 1.1921 1.1851 1.1782 1.1703 1.1690 1.1661 1.1661 1.1646 1.1606 1.1668 1.1880 1.2220 1.2520 1.2760 1.2890 1.3041 1.3199 1.3307 1.3305 1.3294 1.3163 1.3063 1.3030 20000 MWD/MTU 1.2321 1.2159 1.2015 1.1943 1.1921 1.1880 1.1822 1.1761 1.1667 1.1580 1.1476 1.1351 1.1239 1.1219 1.1198 1.1178 1.1148 1.1252 1.1403 1.1546 1.1677 1.1797 1.1903 1.1980 1.2054 1.2100 1.2134 1.2148 1.2325 1.2488 1.2615 1.2711 1.2778 1.2796 1.2794 1.2762 1.2681 1.2581 1.2432 1.2283 1.2105 1.1888 1.1780 1.1668 1.1646 1.1629 1.1637 1.2010 1.2460 1.2860 1.3200 1.3510 1.3770 1.4077 1.4305 1.4473 1.4332 1.4211 1.4191 1.4179 1.4147

COLR BRAIDWOOD 2 Revision 12 Page 8of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Table 2.6.2.b W(Z) versus Core Haight for Expanded AFD Acceptable Operation Limits In Figura 2.8.1.b (Top and Bottom 8% Excluded PerWCAP-10216)

Haight 150 5000 14000 I feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 !core bottoml 1.3654 1.4825 1.4049 0.20 1.3550 1.4482 1.3762 0.40 1.3492 1.4305 1.3724 0.60 1.3377 1.4108 1.3581 0.80 1.3262 1.3934 1.3363 1.00 1.3098 1.3758 1.3211 1.20 1.3073 1.3651 1.2982 1.40 1.3006 1.3474 1.2791 1.60 1.2843 1.3260 1.2611 1.80 1.2697 1.3074 1.2459 2.00 1.2543 1.2878 1.2308 2.20 1.2370 1.2643 1.2192 2.40 1.2215 1.2427 1.2081 2.60 1.2041 1.2192 1.2024 2.80 1.1883 1.2002 1.1971 3.00 1.1773 1.1830 1.1911 3.20 1.1687 1.1762 1.1823 3.40 1.1618 1.1722 1.1750 3.60 1.1524 1.1663 1.1654 3.80 1.1469 1.1606 1.1554 4.00 1.1420 1.1537 1.1469 4.20 1.1357 1.1460 1.1415 4.40 1.1294 1.1376 1.1359 4.60 1.1291 1.1290 1.1363 4.80 1.1296 1.1199 1.1365 5.00 1.1292 1.1109 1.1364 5.20 1.1276 1.1003 1.1382 5.40 1.1252 1.0929 1.1396 5.60 1.1216 1.0892 1.1481 5.80 1.1178 1.0857 1.1637 6.00 1.1217 1.0945 1.1763 6.20 1.1284 1.1041 1.1870 6.40 1.1352 1.1128 1.1966 6.60 1.1389 1.1205 1.2024 6.80 1.1427 1.1282 1.2062 7.00 1.1445 1.1339 1.2081 7.20 1.1459 1.1408 1.2050 7.40 1.1494 1.1489 1.2019 7.60 1.1522 1.1562 1.1921 7.80 1.1551 1.1625 1.1851 8.00 1.1609 1.1673 1.1782 8.20 1.1667 1.1711 1.1703 8.40 1.1715 1.1739 1.1690 8.60 1.1758 1.1748 1.1661 8.80 1.1791 1.1860 1.1661 9.00 1.1814 1.1978 1.1646 9:20 1.1855 1.2123 1;1606 9.40 1.2038 1.2264 1.1668 9.60 1.2189 1.2401 1.1880 9.80 1.2222 1.2525 1.2220 10.00 1.2226 1.2595 1.2520 10.20 1.2200 1.2651 1.2760 10.40 1.2164 1.2715 1.2890 10.60 1.2350 1.2794 1.3041 10.80 1.2463 1.2850 1.3199 11.00 1.2515 1.2896 1.3307 11.20 1.2515 1.2987 1.3305 11.40 1.2569 1.3114 1.3294 11.60 1.2598 1.3145 1.3163 11.80 1.2647 1.3193 1.3063 12.00 !core too\\

1.2743 1.3330 1.3030 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 20000 MWD/MTU 1.3397 1.3343 1.3267 1.3230 1.3185 1.3121 1.3037 1.2953 1.2830 1.2716 1.2583 1.2422 1.2261 1.2079 1.1902 1.1759 1.1729 1.1786 1.1822 1.1856 1.1881 1.1875 1.1906 1.1982 1.2057 1.2102 1.2134 1.2148 1.2325 1.2488 1.2615 1.2711 1.2778 1.2796 1.2794 1.2762 1.2681 1.2581 1.2432 1.2283 1.2105 1.1888 1.1780 1.1668 1.1646 1.1629 1.1637 1.2010 1.2460 1.2860 1.3200 1.3510 1.3770 1.4077 1.4305 1.4473 1.4332 1.4211 1.4191 1.4179 1.4147

Notes:

COLR BRAIDWOOD 2 Revision 12 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 Burnup 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 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 BRAIDWOOD 2 Revision 12 Page 10of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21

2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN AH) (LCO 3.2.2) 2.7.1 FNe.H:::;;F~~p[1.0+PFe.H(1.0-P)]

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

F~~P = 1.70 PFe.H = 0.3

2.7.2 Uncertainty

The uncertainty, UFe.H. to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN aH shall be calculated by the following formula:

where:

UFtJHm = Base FNe.H measurement uncertainty = 1.04 when PDMS is inoperable (UFaHm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN aH Warning Setpoint = 2% FN aH Margin FN aH Alarm Setpoint = 0% FN aH 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. 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.

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL;::::: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPsd 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 12 Page 11of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 Figure 2.8.1.a:

120 100 a:

LI.I 3:

0 80 a.. _,

<(

?

a:

LI.I 60

c I-c LI.I

~

a:

40 -

0

~

20 0

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

-*-1

~-

l 1 (-10, 100) I 1 (+10, 100) 1 Una cceptab e

~

-~

U1 **cc*p*r*-

..,.;t;O-nr 01 I

i Dperati n I

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I I

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I I

I I

I j I (-20, 5o) I I (+25, 50) I I

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-10 0

10 20 30 40 so AXIAL FLUX DIFFERENCE (%)

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

120 100 a:

LLI

~

0 80 CL. _,

<C a:

LLI 60 J:

I-Q LLI t:c a:

40 0

~

20 0

-50 Una 01 Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits I (-15, 100) I I (+10, 100) I v I

\\

I ceptab e I 1eration I I

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I !

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Acee >table

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I I I

I

-40

-30

-20

-10 0

10 20 30 40 so AXIAL FLUX DIFFERENCE (%)

COLR BRAIDWOOD 2 Revision 12 Page 13of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 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 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 AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 /psi.

2.10.4 The nominal T avg 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 AT lead/lag time constant -r1 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 -r3 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 -rs shall be equal to 4 sec.

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

2.10.12 The f1 (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% I% Al.

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

COLR BRAIDWOOD 2 Revision 12 Page 14of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower~ T Setpoint Parameter Values 2.11.1 The Overpower ~ T reactor trip setpoint Kt shall be equal to 1. 072.

2.11.2 The Overpower ~ T reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0.021 °F for increasing Tavg.

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

2.11.4 The Overpower ~ T reactor trip setpoint T avg heatup coefficient Ks shall be equal to 0.00245 / °F when T > T".

2.11.5 The Overpower~ T reactor trip setpoint Tavg heatup coefficient Ks shall be equal to 0 I °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 ~ T lead/lag time constant *1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel ~ T lead/lag time constant, 2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel ~ T lag time constant, 3 shall be less than or equal to 2 sec.

2.11. 10 The measured reactor vessel average temperature lag time constant *a shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant *1 shall be equal to 10 sec.

2.11.12 The f2 (~I) "positive" breakpoint shall be 0 for all ~I.

2.11.13 The f2 (~I) "negative" breakpoint shall be 0 for all ~I.

2.11.14 The f2 (~I) "positive" slope shall be 0 for all ~I.

2.11.15 The f2 (~I) "negative" slope shall be 0 for all ~I.

COLR BRAIDWOOD 2 Revision 12 Page 15 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 21 2.12 Reactor Coolant System (RCS) Pressure. Temperature. and Flow Departure from Nucleate Boiling CDNB) 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 (T avg) 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 Section Conditions (ppm) 2.13.1 a) prior to initial criticality 1705 b) for cycle bum ups ~ 0 MWD/MTU 1814 and < 16000 MWD/MTU c) for cycle bumups :2: 16,000 MWD/MTU 1445 2.13.2 a) prior to initial criticality 1768 b) for cycle bum ups ~ 0 MWD/MTU and <

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

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