ML031050377
| ML031050377 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/09/2003 |
| From: | Vonsuskil J Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW030028 | |
| Download: ML031050377 (19) | |
Text
h- I ExeklnM Exelon Generation Company, LLC www exeloncorp coM Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel 815-417-2000 April 09, 2003 BW030028 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 Number 4 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 10 Revision Number 4, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)". This revision of the COLR was recently implemented and revises item 2.5.4, item 2.6.2 and corresponding Figures 2.6.2.b through 2.6.2.d, and item 2.13.2.
These changes include: 1) deleting a control bank park position that will not be used, 2) updating W(z) data for burnups of 6,000, 14,000 and 20,000 MWD/MTU, and 3) editorial changes.
If you have any questions regarding this matter, please contact Mr. Scott Butler, Acting Regulatory Assurance Manager at (815) 417-3540.
Respectfully, J es . von Suskil Sl1 Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 2 Cycle 10 Revision Number 4 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station p1~
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 2, Cycle 10, Revision Number 4
CAC-02-48 Rev. 4 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 32.2 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 (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)
I CAC-02-48 Rev. 4 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-*
q> 64 -- ..
64D E
U520
,, 22D0XsX0 600 580- * * * . . * . . . . . * . . , .
- 2' . 8.I .2 Figure 2.1.1: Reactor Core Limits
CAC-02-48 Rev. 4 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 Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOUAROIHZP-MTC upper limit shall be +2.57 x 104 Ak/kPF.
2.3.2 The EOUAROIHFP-MTC lower limit shall be -4.6 x 104 AkkF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be
-3.7 x 10 AWk/kF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 &k/k/0F.
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) 2A.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. 4 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:
Park Position (step) Overlap Limit (step) 225 110 226 - i11 -
227 - 112 228 113
- 229 114
CAC-02-48 Rev. 4 Page 5 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 25.1:
Control Bank Inserbon Units Versus Percent RAt Thenmr 224 (27/q 4) - - (77°, 224
- D- -- _7--
220 _/_
2D0 1(10 0 10 20 30 40 50 60 70 80 90 100 RelatWe Pow (Paect)
CAC-02-48 Rev. 4 Page 6 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.6 Heat Flux Hot Channel Factor (F0(Z)) (LCO 3.2.1) 2.6.1 FQ (Z) - XQxK(Z) for P < 0.5 0.5 FRTP FQ(Z)<-Q XK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FanT'= 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 bumups of 150, 6000,14000, and 20000 MWD/MTU.
Table 2.6.2 shows the Fc%(z) penalty factors that are greater than 2% per 31 Effective Full Power Days. These values shall be used to increase the FWQ(z) as per Surveillance Requirement 3.2.1.2. -A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.
2.6.3 Uncertainty
The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor F0(Z) shall be calculated by the following formula UFQ =Uq, *U.
where:
Uw = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable.
(Uq is defined by PDMS when operable.)
U. = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FQ(Z) Warning Setpoint Ž 2% of Fa(Z) Margin FQ(Z) Alarm Setpoint 2 0% of Fo(Z) Margin
CAC-02-48 Rev. 4 t Page 7 of 17 -
CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height 1.1
(.0 (.1.0)as--0 1 -
1 0.9 7'" ^240.924)
I_
0.8 _I
_ I L _I I p 0.7 a
IL
,, 0.6
. E z- 0.5 N
i27 0.4
_*.. _ I-LOCA LimitingL
___ Envelope__ A 0.3 0.2 0.1 0 -- - - _ _ _ _ - _ -
0 1 2 3 4 5 6 7 8 9 10 111 12 BOTTOM Core Height (if) TOP
CAC-02-48 Rev. 4 Page 8 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Height MAX W(Z)
Feet Braldwood Unit 2 Cycle 10 000 10000 020 Ieooo Figure Z6.2.o 040 I 0000 060 10000 Summary of W(Z) Functon at 150 MWD/MTU 060 1 0000 (Top and Bottom 15% Excluded per WCAP-10216) 100 I 0000 1.20 10000 140 1.0000 1.0 10000 1.35 180 11882 2.00 1 1835 220 1 1684 240 1.1589 260 11489 2.80 1 1399 300 1.1304 3.20 1.1228 1.30 340 1.1286 360 1 1333 380 1.1371 400 1140S 420 1 1445 440 11472 460 1 1479 480 11486 1.25 500 11473 520 1.1450 5.40 1 1437 560 1.148S 580 11548 0 600 1.1656 6.20 1.1803 6&40 1 1920 : 1.20 U.
660 12037 680 - 12125 7.00 1 2203 7.20 12261 7A0 1 2338 760 1 2386 780 12436 1.15 800 12475 8.20 12468 840 12478 8.60 1.2478 880 12489 9.00 12536 920 1.2542 940 1.2545 1.10 960 1.2531 9.80 1 2484 1000 1 2470 1020 1 2530 10.40 1 0000 10.60 10000 1080 10000 1100 I.W000 1.05 _
11.20 1 0000 0.00 DO 6 00 8.00 - 1200 11 40 1.0000 CORE HEIGHT (FEET) 1160 .QOOO -
11 80 -1.0000 1200 1 0000
CAC-02-48 Rev. 4 Page 9 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Heigt MWXW()
Feet BrddccdUrnt2 Cyde 10 OWo I0000 020 I0000 Figxe2 62 b 040 2 0000 060 1 0000 , S umrry of W-)F uxtcn d 600 NMADtA U 080 I 0000 (TcpardBdtwm l5% Exducibde WrCAP-I0216) 1W 10000 1.20 1.0000 1 40 1.0000 1 60 I 0000 1.35 1 80 1.2882 2CO 12648 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _
220 1.2399 2.40 1 2183 2.60 1 2039 280 1.1962 3W 1.1882 320 1.1781 1.30 340 1.1677 360 380 1.1608 1.1547 ___q__-_[_ ___ ____________
4 00 4.20 440 460 11470 1 1382 11303 1 1209
- 1.25 480 1 112
__I___ __ ___ .______ X XX ____ ____
5W 520 1 1034 1 0940
_ _ _ K_ _ _ _ _ _ _ _ _ . _ _
540 1 0857 560 1.0780 z 580 6W 10786 10840 0
F __ __ __ _ _ __ _ . _ _
6.20 1 0971 z D 1.20 640 21t12 IL.
660 1 1232 680 7.00 11354 1.1457 3:
___ .,-_-_- _ - .,o'..n._ __
7.20 7AO 11541 1.1614 __ _ _K _ _ _ _ Q __ _ _ __
760 11670 1.15
__ __ _ ___T______ ._ ________ ___
7.80 1.1716 8OO 11743 820 11750 840 1.1759 860 880 1.1773 1.1796 ___ . __ _ T _ .__
9W 1 1810 _X __ ,wX XX _ _ _ X .
9.20 9AO 1 1795 1 1879 1.10 , _ _ _ _ _ __ _ _ _ _ _ _ _ _
9.60 1.1949 980 10W 1.2030 1.097
__ __-_ .R _- , ___ _ __
1020 1.2135 1040 I o10 1060 I O1OO 1080 1 0000 I 05z; _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
11O 1 0000 0.00 2.00 4.00 . 6.00 8.00 10 00 12.00 11.20 1.0000 11.40 20000 CORE HEIGHT(FEET) 11 60 I oooo 11 80 I cooO 12W I 0000
CAC-02-48 Rev. 4 Page 10 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 Hestd MAXXW(Z)
Feet BrddLoWUrnt2Cyde 1 000 10000 020 1m00 Fkgue2 62.c 0.40 I 0000 060 1 0000 S umay d W(Z) Fdirn cd 14000 MtNDMr U 080 10000 ( cod BoltaTm15% ExdudbdiprWCAP-10216) 100 I 0000 120 1 0000 1 40 I 0000 160 10000 1.40 18O 13766 2.00 13572 220 13321 W -I1 111W 240 13108 2.60 12911 280 12760 300 1 2632 1.35 320 1 2467 340 1.2318 t1f10 1111111181-\1\-1 360 1.2149 380 12043 400 1.1947 420 1 1834 1.30 440 1.1721 460 1.1609 480 11477 500 11341 520 11314 540 1 1287 560 11258 , 1.25 580 11220 2 600 11236 0
_fr :tM 620 11324 z 640 11382 660 1 1427 680 11449 700 1.1464 ?. 1.20 720 11476 740 11464 7.6D 11396 780 8.C 820 8.40 860 11357 1.1306 11207 11131 1 1071 1.15 W illlEl-ll-lulX 880 1.1034 9W0 11050 9.20 1.1087 940 11138 960 1.1139 1.10 980 11285 Fr g1t 1000 11593 1020 11890 1040 1 0000 1060 10000 1080 1)000 11e 10000 1.05 1120 1 000 0.00 ZOO 0 4 00 - 600 8.00 10.00 12.00 1140 10I00 IDOOO CORE HEIGHT (FEET) 1160 11.80 10000 120D IDOOO
CAC-02-48 Rev. 4 Page 11 of 17 CORE OPERATING LIMITS REPORT (cOLR) for BRAIDWOOD UNIT 2 CYCLE 10 Heit MKX W(Z)
Feet BrddgcxdUrwt2 Cyde 10 000 1 0000 020 1 0000 Fkige262d 040 1 0000 0.60 1 0000 SufrnTxy otWC7) Fu~Ccnd 20000 tNDMTU 080 100D (rqcp .dBclan 15% Exdtxc1 WCAP-10216) 100 1 0000 1.20 10000 1 40 1.0000 160 1.0000 1.35 1 80 1.2785 200 1.2583 220 1.2317 240 12124 260 11966 280 11883 3.00 11780 3.20 1 1700 , 1.30 3AO 11691 3.60 11684 380 11670 400t 11657 420 11732 440 11842 460 11914 480 11969 1 25 500 1.2002 520 12004 540 1.1994 4 560 1.1953 z
-580 1.2014 a 600 12165 620 1.2280 z 1.20 640 1.2374 660 112417 680 1.2438 3.
700 1.2437 4 720 1.2387 7.40 1.2326 760 12216 780 12098 1.15 800 1.1955 820 11782 8.40 11633 860 1.1475 880 11435 900 1.1410 920 1.1372 9.40 11349 1.10 960 1 1851 980 1 2267 10.00 12640 10.20 13048 10.40 1 0000 10.60 IDO00 10.80 1 0000 1.00 10000 1 05, 11.20 10000 000 2.00 4.00 6.00 800 1000 12.00 11A0 1.0000 11.60 1 0000 - CORE HEIGHT (FEET) 1180 Lm00 1200 1 0000
CAC-02-48 Rev. 4 Page 12 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE 0o Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor- F9o(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 L
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 bumups.
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. 4 Page 13 of 17 CORE OPERATING LIMITS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN HI (LCO 3.2.2) 2.7.1 FISH
- FRjP1 .0 + PFi,,(1.0 - P)l where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FP= 1.70 PFA= 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFmH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN shall be calculated by the following formula:
UFAH = UF&Hm where:
UQF,,m = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FH Warning Setpoint 2 2% of FNO Margin FNH Alarm Setpoint 2 0% of FNm 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 2 50% RTP when PDMS is OPERABLE.-
2.9.2 PDMS Alarms:
DNBR Warning Selpoint 2 2% of DNBR Margin DNBR Alarmr Setpoint 2 0% of DNBR Margin
CAC-02-48 Rev. 4 Page 14 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE 10 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power xal Rux Oiffesre Units Vth PD SInperabe 120 0
80~
°4,00 60 cc 0 ,
0 40 20 -10 0 10 20)30 40 50
,IALNFLJ (Of(f
)( a (/4
CAC-02-48 Rev. 4 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.
2.10.2 The Overtemperature AT reactor trip setpoint Tavo 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 0.001 81 / psi.
2.10.4 The nominal Tang 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 s1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT leadllag time constant X2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant T3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant 4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant -r5 shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant ecu 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 fT(Al) "negative" slope shall be -2.61 % /% Al.
CAC-02-48 Rev. 4 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 T8,, rate/lag coefficient K5 shall be equal to 0.02 1 OF for increasing Tavg 2.11.3 The Overpower AT reactor trip setpoint Tayg rate/lag coefficient K5 shall be equal to 0/ 'F for decreasing Ta, 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245/ 'IF when T > T'.
2.11.5 The Overpower AT reactor trip setpoint T8 , heatup coefficient Kr, shall be equal to0/'FwhenT<TH.
2.11.6 The nominal Ta.g 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 Ad shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant T2 shall be equal to 3sec.
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 (AI) 'positiver 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.
- W CAC-02-48 Rev. 4 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 (T.,) 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 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 To maintain keff < 0.987 with all shutdown and control rods fully withdrawn in MODES 3,4, or 5 (TRM 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:
- a. 1778 ppm prior to initial criticality
- b. 1990 ppm at all other times in core life