ML14136A127

Core Operating Limits Report Cycle 18

ML14136A127
Person / Time
Site:	Braidwood
Issue date:	05/16/2014
From:	Kanavos M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW140049
Download: ML14136A127 (17)

Text

May 16, 2014 BW140049 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457

Subject:

Core Operating Limits Report, Braidwood Unit 2 Cycle 18 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 18, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)."

Braidwood Unit 2 Cycle 18 COLR, Revision 8 was implemented to support Braidwood Unit 2 Cycle 18 operation. Note: The revision number is based on a numbering convention that continues from the previous revision of the COLA.

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

Sincerely,

~L--

Mark E. Kanavos Site Vice President Braidwood Station

Attachment:

Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 18, Revision 8 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BRAIDWOOD UNIT 2 CYCLE 18 EXELON TRACKING 10:

COLR BRAIDWOOD 2 REVISION 8

COLR BRAIDWOOD 2 Revision 8 Page 1 of 15 CORE OPERATING LlMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 18 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 (MTC)

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

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN L'.H)

LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

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

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual (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 (SDM) - MODE 1 and MODE 2 with keff;,: 1.0 TRM TLCO 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 BRAIDWOOD 2 Revision 8 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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.

680.---------~--------~--------~--------~--------~--------,

1471 psia 6604---------r-~----~---------+--------~--------4-------~

22:50 psia 6404---------+---------+=~------+---------+---~~--+--------4

J  ::000 psia 15 I-

~

6004---------~---------+---------+------~~~--------~--~--~

5804-~~--~-r~--~~-+~~~~-+--~~~~r-~~~--r-~~~~

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

COLR BRAIDWOOD 2 Revision 8 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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% ~k/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% ~k1k (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 BOLIARO/HZP-MTC upper limit shall be +2.132 x 10-5 ~k1k1°F.

2.3.2 The EOLIARO/HFP-MTC lower limit shall be -4.6 x 10-4 ~k1k10F.

The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10- ~k1k1°F.

4 2.3.3 2.3.4 The EOLIARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 ~k1k1°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 8 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 Figure 2.5.1:

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

I I I 220 Y

I I

I

! /

V 200

~

VcsA~KB i

I I! ~

V 180 C

~

... 160

/1 I I

V (100%,161)

LI /

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'0

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~ 140 IBANKe I

/ ,/1i til Q.

.e I

!!!. 120 I

/~

c i

/1 0 I E

til 0 100 Q.

.lII: V V IBANKO I C

I'G Ql 80 /  ! /

'0 0

a:: / 1/

60 / /

/

V I

'I (0%,47) 1 ,/ I 40 20

/

1(3O%,0)VI I I o

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

COLR BRAIDWOOD 2 Revision 8 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 2.6 Heat Flux Hot Channel Factor (FQ,(Zll (LCO 3.2.1) 2.6.1 Total Peaking Factor:

F RTP FQ(Z) ~ -Q-xK(Z) for P ~0.5 0.5 F RTP FQ(Z) ~-Q-xK(Z) forP >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 1.1 1(0.0, 1.0) I 1(6.0, 1.0) I 1

(12.0,0.924) I 0.9 0.8 E!0 0.7 LL "C

Q) 0.6 ni

...0E 0.5 z

~

N

~ 0.4

_LOCA Limiting Envelope 0.3 0.2 0.1 o

o 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (tt) TOP

COLR BRAIDWOOD 2 Revision 8 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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 burn ups of 150,6000, 14000, and 20000 MWD/MTU.

2) The EOl-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups ;:::: 18000 MWD/MTU. The EOl-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOl-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOl-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.

Table 2.6.2.c shows the Fe o(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWo(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, UFO, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula U FQ =Uqu eU e where:

Uqu =Base Fo measurement uncertainty = 1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)

Ue = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:

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

COLR BRAIDWOOD 2 Revision 8 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 Table 2.6.2.a Full Cycle W(ZI 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 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3587 1.4515 1.4339 1.4310 0.20 1.3389 1.4142 1.4073 1.4050 0.40 1.3285 1.4008 1.3925 1.3903 0.60 1.3162 1.3837 1.3749 1.3780 0.80 1.2995 1.3716 1.3597 1.3551 1.00 1.2882 1.3457 1.3507 1.3396 1.20 1.2735 1.3316 1.3314 1.3198 1.40 1.2603 1.3291 1.3206 1.3049 1.60 1.2629 1.3198 1.3034 1.2830 1.80 1.2644 1.3017 1.2888 1.2649 2.00 1.2522 1.2826 1.2723 . 1.2453 2.20 1.2363 1.2599 1.2504 1.2293 2.40 1.2203 1.2399 1.2320 1.2163 2.60 1.2024 1.2180 1.2091 1.2007 2.80 1.1871 1.1979 1.1984 1.1880 3.00 1.1727 1.1872 1.1913 1.1750 3.20 1.1614 1.1812 1.1825 1.1768 3.40 1.1557 1.1756 1.1741 1.1851 3.60 1.1507 1.1686 1.1635 1.1930 3.80 1.1461 1.1616 1.1634 1.1978 4.00 1.1405 1.1541 1.1619 1.2006 4.20 1.1339 1.1445 1.1601 1.2017 4.40 1.1348 1.1355 1.1565 1.1999 4.60 1.1354 1.1250 1.1543 1.2054 4.80 1.1348 1.1154 1.1591 1.2130 5.00 1.1341 1.1064 1.1627 1.2193 5.20 1.1324 1.1033 1.1645 1.2234 5.40 1.1288 1.1003 1.1665 1.2259 5.60 1.1272 1.0969 1.1743 1.2447 5.80 1.1356 1.1014 1.1909 1.2621 6.00 1.1433 1.1092 1.2055 1.2765 6.20 1.1491 1.1179 1.2172 1.2872 6.40 1.1538 1.1267 1.2269 1.2949 6.60 1.1576 1.1345 1.2326 1.2977 6.80 1.1594 1.1412 1.2364 1.2985 7.00 1.1602 1.1472 1.2372 1.2953 7.20 1.1606 1.1540 1.2341 1.2863 7.40 1.1629 1.1623 1.2300 1.2763 7.60 1.1637 1.1671 1.2230 1.2624 7.80 1.1644 1.1724 1.2160 1.2456 8.00 1.1638 1.1768 1.2081 1.2287 8.20 1.1616 1.1787 1.1981 1.2060 8.40 1.1593 1.1820 1.1882 1.1863 8.60 1.1611 1.1838 1.1841 1.1685 8.80 1.1600 1.1866 1.1816 1.1635 9.00 1.1657 1.1886 1.1899 1.1628 9.20 1.1724 1.2100 1.1983 1.1990 9.40 1.1771 1.2304 1.2060 1.2490 9.60 1.1814 1.2493 1.2480 1.3000 9.80 1.1857 1.2673 1.2820 1.3410 10.00 1.1894 1.2829 1.3120 1.3770 10.20 1.1987 1.2938 1.3410 1.4140 10.40 1.2102 1.3073 1.3640 1.4420 10.60 1.2330 1.3141 1.3820 1.4730 10.80 1.2500 1.3217 1.3970 1.4940 11.00 1.2550 1.3153 1.4060 1.5100 11.20 1.2650 1.2742 1.3720 1.4890 11.40 1.2690 1.3470 1.4070 1.5050 11.60 1.2450 1.3200 1.3910 1.4890 11.80 1.2350 1.3118 1.3820 1.4810 12.00 (core top) 1.2460 1.3142 1.3660 1.4810 Note: W(Z) values at 20000 MWOIMTU may be applied to cycle burnups greater than 20000 MWO/MTU to prevent W(Z) function extrapolation

COLR BRAIDWOOD 2 Revision 8 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 Table 2.G.2.b EOl-only W(ZI versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-1 0216)

Height 18000 20000 23271 (feet) MWD/MTU MWDfMTU MWDfMTU 0.00 (core bottom) 1.2754 1.2791 1.2791 0.20 1.2539 1.2556 1.2556 0.40 1.2400 1.2404 1.2404 0.60 1.2248 1.2244 1.2244 0.80 1.2157 1.2172 1.2172 1.00 1.2047 1.2008 1.2008 1.20 1.1837 1.1764 1.1764 1.40 1.1705 1.1607 1.1607 1.60 1.1556 1.1461 1.1461 1.80 1.1493 1.1410 1.1410 2.00 1.1459 1.1342 1.1342 2.20 1.1396 1.1237 1.1237 2.40 1.1350 1.1155 1.1155 2.60 1.1299 1.1091 1.1091 2.80 1.1300 1.1095 1.1095 3.00 1.1329 1.1170 1.1170 3.20 1.1392 1.1311 1.1311 3.40 1.1434 1.1414 1.1414 3.60 1.1468 1.1517 1.1517 3.80 1.1491 1.1590 1.1590 4.00 1.1528 1.1679 1.1679 4.20 1.1657 1.1817 1.1817 4.40 1.1761 1.1936 1.1936 4.60 1.1856 1.2031 1.2031 4.80 1.1927 1.2109 1.2109 5.00 1.1993 1.2191 1.2191 5.20 1.2030 1.2234 1.2234 5.40 1.2057 1.2259 1.2259 5.60 1.2206 1.2447 1.2447 5.80 1.2387 1.2621 1.2621 6.00 1.2537 1.2765 1.2765 6.20 1.2651 1.2872 1.2872 6.40 1.2737 1.2949 1.2949 6.60 1.2775 1.2977 1.2977 6.80 1.2794 1.2985 1.2985 7.00 1.2774 1.2953 1.2953 7.20 1.2702 1.2863 1.2863 7.40 1.2617 1.2763 1.2763 7.60 1.2498 1.2624 1.2624 7.80 1.2362 1.2456 1.2456 8.00 1.2222 1.2287 1.2287 8.20 1.2040 1.2060 1.2060 8.40 1.1875 1.1863 1.1863 8.60 1.1751 1.1685 1.1685 8.80 1.1708 1.1635 1.1635 9.00 1.1745 1.1628 1.1628 9.20 1.1975 1.1990 1.1990 9.40 1.2279 1.2490 1.2490 9.60 1.2768 1.3000 1.3000 9.80 1.3160 1.3410 1.3410 10.00 1.3504 1.3770 1.3770 10.20 1.3854 1.4140 1.4140 10.40 1.4120 1.4420 1.4420 10.60 1.4384 1.4730 1.4730 10.80 1.4574 1.4940 1.4940 11.00 1.4717 1.5100 1.5100 11.20 1.4460 1.4890 1.4890 11.40 1.4667 1.5050 1.5050 11.60 1.4516 1.4890 1.4890 11.80 1.4431 1.4810 1.4810 12.00 (core top) 1.4347 1.4810 1.4810 Note: W(l) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(l) function extrapolation

COLR BRAIDWOOD 2 Revision 8 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) FeQ(z) 0 1.0200 326 1.0200 502 1.0202 678 1.0309 854 1.0340 1030 1.0358 1206 1.0372 1382 1.0374 1557 1.0328 1733 1.0278 1909 1.0231 2085 1.0200 23271 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 BRAIDWOOD 2 Revision 8 Page 10 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 N

2.7 Nuclear Enthalpy Rise Hot Channel Factor (F AHl (LCO 3.2.2) 2.7.1 FN 6H S F~~P[1.0 + PF 6H(1.0 - P)]

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

=

F~~P 1.70 PF 6H = 0.3

2.7.2 Uncertainty

The uncertainty, UF6H , to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN 6H shall be calculated by the following formula:

where:

UFtJHm = Base FN6H measurement uncertainty = 1.04 when PDMS is inoperable (U F6Hm is defined by PDMS when OPERABLE.)

2.7.3 PDMS Alarms:

FN 6H Warning Setpoint =2% FN 6H Margin FN 6H Alarm Setpoint = 0% FN6H Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.

a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.

b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.

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

2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBR APsL ;::: 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 8 Page 11 of15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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 i I I

I I I

(-15 100) (+10, ~OO) 100 0:::

w

~

Unacc eptabh Ope ation I \ Una pcepta ole 01 )eratio 1

,v 0 80 I a.

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w I A~cepta pie dperati< n r

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60 I J:

~

C w

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(-3 P, 50\I

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0~

0 40 I

20 i I

I o

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

COLR BRAIDWOOD 2 Revision 8 Page 12 of 15 CORE OPERATfNG LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 Figure 2.8.1.b:

Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup ~ 18000 MWD/MTU)

Axial Flux Difference Limits with PDMS Inoperable 120  !

I I

100

_L____________ _ : (-10, :100) (+10,1100)

I

&Z; I ,

w I I 3: Unaciceptabl~ I I

I Unacceptabl~

~ 80 - Op~ratton L- - -t-- Operation L----

..J  !

i c( ,

AccJptable

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I Operation:

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e W

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________ L _______ .

40 o

?fl.

20---

o

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

COLR BRAIDWOOD 2 Revision 8 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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/ of.

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

2.10.4 The nominal Tavgat RTP (indicated) l' shall be less than or equal to 588.0 oF.

2.10.5 The nominal RCS operating pressure (indicated) pI 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 '5 shall be equal to 4 sec.

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

2.10.12 The f1 (AI) "positive" breakpoint shall be +10% AI.

2.10.13 The f1 (AI) "negative" breakpoint shall be -18% AI.

2.10.14 The f1 (AI) "positive" slope shall be +3.47% / % AI.

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

COLR BRAIDWOOD 2 Revision 8 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower ~T Setpoint Parameter Values 2.11.1 The Overpower ~ T reactor trip setpoint ~ shall be equal to 1.072.

2.11.2 The Overpower ~ T reactor trip setpoint T avg rate/lag coefficient K5 shall be equal to 0.02/ of for increasing Tavg.

2.11.3 The Overpower ~T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to o / of for decreasing Tavg.

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

2.11.5 The Overpower ~ T reactor trip setpoint T avg heatup coefficient Ks shall be equal to 0 / of when T:s; T".

2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 of 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 '6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant '7 shall be equal to 10 sec.

2.11.12 The f2 (~I) "positive" breakpoint shall be 0 for all ~1.

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

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

2.11.15 The f2 (~I) "negative" slope shall be 0 for all ~1.

COLR BRAIDWOOD 2 Revision 8 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 18 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 OF.

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 :s; 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 1677 b) for cycle burnups;::: 0 MWD/MTU and < 16000 MWD/MTU 1743 c) for cycle burnups;::: 16,000 MWD/MTU 1354 2.13.2 a) prior to initial criticality 1728 b) all other times in life 1912