ML021540206

Core Operating Limits Report, Braidwood, Unit 2 Cycle 10, Revision 3

ML021540206
Person / Time
Site:	Braidwood
Issue date:	05/16/2002
From:	Vonsuskil J Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BW020047 CAC-02-48, Rev 3
Download: ML021540206 (19)

Text

Exelon.

Exelon Generation Company, LLC www.exeloncorp.com Nuclear BTaidwood Station 35100 South Rt 53, Suite 84 Braceville, IL60407-9619 Tel. 815-417-2000 May 16, 2002 BW020047 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 10 Revision 3 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 10 (Revision 3), in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." This revision of the COLR was recently implemented in support of a reload cycle.

If you have any questions regarding this matter, please contact Ms. A. Ferko, Regulatory Assurance Manager at (815) 417-2699.

Respectfully, Vice Presiden t Braidwood Station

Attachment:

Core Operating Limits Report, Braidwood Unit 2 Cycle 10 Revision 3 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station

ATTACHMENT I Core Operating Limits Report Braidwood Unit 2, Cycle 10 Revision 3

CAC-02-48 Rev. 3 Page I of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 10 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specifications 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 (FO(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 (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 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)

CAC-02-48 Rev. 3 Page 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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 2471 psia 660 - "__

2250 psi3 640 L.

E 1860 psia 0-- 620 *

). 50 58 O LL6.. .L.. LL.

S -3 V.0 - 2 Froction of .Nominol Power Figure 2.1.1: Reactor Core Limits

CAC-02-48 Rev. 3 Page 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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 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 Temrperature Coefficient (MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.57 x 10- Ak/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10.4 Ak/k/oF.

2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be

-3.7 x 10-4 Ak/k/°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10A 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 the 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.

CAC-02-48 Rev. 3 Page 4 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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:

CAC-02-48 Rev. 3 Page 5 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 FigureZ&1:

Control Bank Insertion Units Versus brcen Rited Thenml 224 (27%1. 224) (770/q 224) 22D 200 180 C

S160 (100D/c 161)

= 140

• 0 5

0~

80 S100 60 40 20 0

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

CAC-02-48 Rev. 3 Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.6 Heat Flux Hot Channel Factor (FfZ)) (LCO 3.2.1) 2.6.1 F RTP FQ(Z) Q xK(Z) forP<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 F0TP= 2.60 K(Z) is provided in Figure 2.6.1.

2.6.2 W(Z) Values:

a) When PDMS is OPERABLE, W(Z) = 1.00000 for all axial points.

b) When PDMS is Inoperable, W(Z) is provided in Figures 2.6.2.a through 2.6.2.d.

The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.

Table 2.6.2 shows the Fca(z) penalty factors that are greater than 2% per 31 Effective Full Power Days. 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.

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 UFQ = Uq, 0 U, where:

Uqu = Base FQ 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:

FQ(Z) Warning Setpoint > 2% of FO(Z) Margin FQ(Z) Alarm Setpoint >_0% of Fo(Z) Margin

CAC-02-48 Rev. 3 Page 7 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height 1 .1 (0.0 1.0) (6.0 1.0)

"1(12A

,0.924) 0 .9 0.8 0

0 .7 L.

"a, 0 .6 0 0 Z

.4. - - -LOCA Limiting-1 0

.34 0.

0..2

0. 1 0- -  : - --

0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP

CAC-02-48 Rev. 3 Page 8 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 W.~ Height MAX W(Z)

Feet Braidwood Unit 2 Cycle 10 0.00 1.0000 0.20 1.0000 Figure 2.6.2-a 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 150 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.35 '

1.80 1.1882 2.00 1.1835 2.20 1.1684 i* l i l It 2.40 2.60 1.1589 1.1489 1.30*  ! ' . .

2.80 1.1399 3.00 1.1304 3.20 1.1228 3.40 1.1286 3.60 1.1333 3.80 1.1371 4.00 1.1408 4.20 1.1445 4.40 1.1472 4.60 1.1479 4.80 1.1486 1.25 5.00 1.1473 5.20 1.1450 5.40 1.1437 5.60 1.1488 5.80 1.1548 z 0

6.00 1.1656 F-6.20 1.1803 6.40 1.1920 = 1.20 IL 6.60 1.2037 6.80 1.2125 7.00 1.2203 7.20 1.2261 7.40 1.2338 7.60 1.2386 7.80 1.2436 8.00 1.15 1.2475 8.20 1.2468 8.40 1.2478 8.60 1.2478 8.80 1.2489 9.00 1.2536 9.20 1.2542 9.40 1.2545 1.10 9.60 1.2531 9.80 1.2484 10.00 1.2470 10.20 1.2530 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 L 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

CAC-02-48 Rev. 3 Page 9 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Height MAX W(Z)

Feet Braidwood Unit 2 Cycle 10 0.00 1.0000 0.20 1.0000 Figure 2.6.2.b 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 6000 MWD/MTU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.80 1.35 1.2058 200 1.1873 2.20 1.1672 2.40 1.1501 2.60 1.1399 2.80 1.1361 3.00 1.1323 3.20 1.1267 1.30 3.40 1.1209 3.60 1.1188 3.80 1.1175 4.00 1.1149 4.20 1.1113 4.40 1.1086 4.60 1.1044 4.80 1.1014 1.25 5.00 1.0972 5.20 1.0928 5.40 1.0894 5.60 1.0864 5.80 1.0916 z 6.00 1.1016 0 6.20 1.1194 6.40 1.1380 =z 1.20

!t.

6.60 1.1547 6.80 1.1714 7.00 1.1861 7.20 1.1989 7.40 1.2106 7.60 1.2205 7.80 1.2294 1.15 8.00 1.2363 8.20 1.2413 8.40 1.2466 8.60 1.2526 8.80 1.2596 9.00 1.2658 9.20 1.2689 9.40 1.2827 1.10 9.60 1.2949 9.80 1.3080 10.00 1.3192 10.20 1.3264 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.0000 1.05 1 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

CAC-02-48 Rev. 3 Page 10 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Height MAX W(Z)

Feet Braidwood Unit 2 Cycle 10 0.00 1.0000 0.20 1o0000 Figure 2.62.c 0.4O 1.0000 0.60 .o0000 Summary ol W(Z) Function at 14000 MWD/MTU 0.80 I.0000 (Top and Bottom 15% Excluded per WCAP- 10216) 1.00 1.0000 1.20 I.O00O 1.40 1.0000 1.60 1.80 1.0000 1.3060 1.5 I l - - - - -I , ,

2100 1.2890 2.20 1.2670 2.40 1.2490 2.60 1.2330 2.80 1.2217 3.00 1I I I 1.2130 3.20 1.2010 1.3 ,I. 1-i I . I ,

3.40 1.1908 3.60 1.1788 3.80 1.1731 4.00 1.1685 4.20 1.1624 4.40 1.1563 4.60 1.1502 4.80 1.1421 1.25 5.00 1.1335 5.20 1.1356 5.40 1.1376 5.60 1.1392 5.80 1.1396 z 6.00 1.1454 6.20 1.1582 6.40 1.1677 Z 1.20 6.60 1.1756 6.80 1.1808 7.00 1.1849 7.20 1.1883 7.40 1.1888 7.60 1.1831 7.80 1.1801 8.00 1.15 1.1754 8.20 1.1654 8.40 1.1574 8.60 1.1509 8.80 1.1465 9.00 1.1475 9.20 1.1504 9.40 1.1547 1.10 9.60 1.1539 9.80 1.1680 10.00 1.1990 10.20 1.2290 10.40 1.0000 10.60 1.0000 10.80 I.OO0O 11.80 1.0000 1.05 "

11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 11.40 1.0000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.00 1.0000

CAC-02-48 Rev. 3 Page II of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Height MAX W(Z)

Feet Braldwood Unit 2 Cycle 10 0.00 1.0000 0.20 1.0000 Figure 2.6.2.d 0.40 1.0000 0.60 1.0000 Summary of W(Z) Function at 20000 MWD/MrU 0.80 1.0000 (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 1.0000 1.35 1.80 1.2791 2.00 1.2611 2.20 1.2365 2.40 1.2153 2.60 1.1971 2.80 1.1873 3.00 1.1766 3.20 1.1690 3.40 1.1688 3.60 1.1689 + I+

3.80 1.1681 4.00 1.1670 4.20 1.1746 4.40 1.1856 4.60 1.1932 4.80 1.1998 1.25 hm T ,

5.00 1.2052 5.20 1.2084 5.40 1.2108 5.60 1.2092 5.80 1.2150 z 0

6.00 1.2295 6.20 1.2402 6.40 1.2488 zi- 1.20 6.60 I .2525 6.80 1.2543 700 1.2541 7.20 1.2491 7.40 1.2430 7.60 1.2320 1.15 7.80 1.2201 8.00 1.2054 #1 8.20 1.1876 8.40 1.,720 8.60 1.1553 8.80 1.1504 9.00 1.1471 9.20 1.1426 9.40 1.10 1.1398 9.60 1.1900 9.80 1.2320 10.00 1.2700 10.20 1.3120 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 2.0000 1.05 7 11.20 1.0000 0.00 2.00 4.00 6.00 8. 00 10.00 12.00 11.40 11.60 1.0000 CORE HEIGHT FEET) 11.80 1.0000 12.00 1.0000

CAC-02-48 Rev- 3 Page 12 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor - Fuo(z)

(MWD/MTU) (%)

2038 2.00 3068 3.13 3239 3.24 3411 3.30 3583 3.28 3754 3.18 3926 3.00 4612 2.00 10791 2.00 10963 2.08 11306 2.24 11477 2.32 11649 2.38 11821 2.43 11992 2.46 12164 2.47 12336 2.45 12507 2.41 12679 2.27 12850 2.00 Notes:

Linear Interpolation is adequate for intermediate cycle burnups.

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

CAC-02-48 Rev. 3 Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAJDWOOD UNIT 2 CYCLE 10 2.7 Nuclear EnthalDy Rise Hot Channel Factor (FNNA) (LCO 3.2.2)

RTP 2.7.1 FANH< FAH [1.0 + PFIH(1.0- P)J where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RTP

,= 1.70 PFAH = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNH shall be calculated by the following formula:

UFAH = UFAHm where:

UFAHm = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:

FIN Warning Setpoint _>2% of FNAH Margin FNH Alarm Setpoint _> 0% of FNAH 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 Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.

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 > 1.536 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% of DNBR Margin DNBR Alarm Setpoint Ž_0% of DNBR Margin

CAC-02-48 Rev. 3 Page 14 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 2.8.1 Axial Flux Difference Limits as 2 Function of Rated Thermal Power Axal Flux Difference Units with PDIVS Inoperable 120 -

cc 00 -15~ui .. .

-- 1 80 Op*io Pet0 c.. * .~

0+0 6..1Z 0 ........

020 ............:

cc

. . .. ... .. S 0

40-30 10 0 10 20 30 40 50 ANAL RMx DIF N (o/4

CAC-02-48 Rev. 3 Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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 K shall be equal to 1.325.

1 2.10.2 The Overtemperature AT reactor trip setpoint Ta, coefficient K2 shall be equal to 0.0297 / OF.

2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K 3 shall be equal to 0.00181 / psi.

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 OF.

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 Tj 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 T4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant T5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant T6 shall be less than or equal to 2 sec.

2.10.12 The f, (Al) "positive" breakpoint shall be +10% Al.

2.10.13 The f, (Al) "negative" breakpoint shall be -18% Al.

2.10.14 The f, (Al) "positive" slope shall be +3.47% / % Al.

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

CAC-02-48 Rev. 3 Page 16 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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 / OF for increasing Tavg.

2.11.3 The Overpower AT reactor trip setpoint Tag rate/lag coefficient K shall 5 be equal to 0 / OF for decreasing Tavg.

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

2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / OF when T < 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 AT lead/lag time constant -l shall be equal to 8 sec.

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

2.11.9 The measured reactor vessel AT lag time constant T3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant T6 shall be less than or equal to 2 sec.

2.11.11 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 (AI) "positive" slope shall be 0 for all Al.

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

CAC-02-48 Rev. 3 Page 17 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 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 380,900 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1733 ppm (LCO 3.9.1).

2.13.2 The Reactor Coolant System boron concentration, with all shutdown and control rods fully withdrawn, shall be greater than or equal to 1778 ppm prior to initial criticality of Cycle 10, or greater than or equal to 1990 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1.g and 3.1 .k.2).