BW030063, Core Operating Limits Report (COLR) Revisions
| ML032250101 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/01/2003 |
| From: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW030063 | |
| Download: ML032250101 (39) | |
Text
xe kn.M Exelon Generation Company, LLC www.exeloncorp.com NucleaT Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 August 1, 2003 BW030063 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457
Subject:
Core Operating Limits Report (COLR) Revisions The purpose of this letter is to transmit revisions to the Braidwood Station, Unit 1 COLR and the Braidwood Station, Unit 2 COLR in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." These revisions of the COLR were recently implemented to increase the COLR limit for the reactor coolant system (RCS) total flow rate from greater than or equal to 380,900 gallons per minute (gpm) to greater than or equal to 386,000 gpm. The RCS total flow rate is being increased to address a core design constraint that 0% of rods experience departure from nucleate boiling for the Locked Rotor event.
If you have any questions regarding this matter, please contact Ms. Kelly Root, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Micha I J. Pacilio Site Vice President Braidwood Station Attachments: : Core Operating Limits Report for Braidwood Unit 1 Cycle 11 (CAD-03-89, Revision 1) : Core Operating Limits Report for Braidwood Unit 2 Cycle 10 (CAC-02-48, Revision 5) cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station 4u1
bcc:
NRC Project Manager, NRR - Braidwood Station Office of Nuclear Facility Safety - IDNS Site Vice President - Braidwood Station Regulatory Assurance Manager - Braidwood Station Director - Licensing, Mid-west Regional Operating Group Manager - Licensing, Braidwood and Byron Stations Nuclear Licensing Administrator - Braidwood Station Nuclear Fuel Management - Robert Lee Exelon Document Control Desk Licensing (Hard Copy)
Exelon Document Control Desk Licensing (Electronic Copy)
ATTACHMENT I Core Operating Limits Report for Braidwood Unit 1 Cycle 11
CAD-03-89, Rev. I CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP
CAD-03-89, Rev. I Page 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to + 10% at 100% RTP 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit I Cycle 11 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 Reor Core Safety Limits (SLs)
LCO 3.1.1 Shutdown Margin (SDM)
LCO 3.1.3 Moderator Temperature Coefficient fMTC)
LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion ULmits 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,)
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 Techrucal Requirements Manual affected by this report are listed below-.
TRM TLCO 3.1.b Boration Flow Paths - Operating TAM 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 keNl 21.0 TRM TLCO 3.1.1 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)
CAD-03-89, Rev. I Page 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 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 I and 2, the combination of Thermal Power, Reactor-Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the lirmits specified In Figure 2.1.1.
680 660 La.
UP 0,
640 a,
I-Q C-Ea,
> 620 U)W C11 600 589 271ps.
2250 psGa
\\00
\\_i 0
.2 -4
.6 8~~~~~~
1.22I Froction of Nominal Power Figure 2.1.1:. Reactor Core Limits
CAD-03-89, Rev. I Page 4 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable APD Limits from -18% to +10% at I100% RTP 2.2 SHUTDOWN MARGIN (SDM)
The SDM lirnit for MODES 1, 2,3, and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3% Aklk (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, 3.1.1, 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% Ek/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.1 and 3.1.).
2.3 Moderator Ternmerature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOLUARO/HZP-MTC upper limit shall be +1.185 x l0' bkk/PF.
2.32 The EOLUARO/HFP-MTC bwer limit shall be -4.6 x 10 4Ak/kPF.
2.3.3 The EOUAR01HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 Ak F.
2.3.4 The EOLUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10, AkIkF.
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 2A Shutdown Bank Insertion Lirnits (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.
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) 225 110 226 111 227 112 228 113 229 114
CAD-03-89, Rev. I Page 5 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -I 8% to +10% at 100% RTP hgure 2.S1:
Co" Bank Inseaon UmtsVersus Percent Fted Thenm I
la 0
10 0-
.x 0
(lMEq 161) 0 10 20 30 40 5D 69 wwwPo (Pernt) 70 80 90 100
CAD-03-89, Rev. I Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 2.6 Heat Flux Hot Channel Factor (Fn(Z)) (LCO 3.2.1) 2.6.1 FRTP FQ(Z)<
xK x
(Z) forP<0.5 0.5 FQ(Z) S-- -xK(Z) forP >0.5 where: P = the ratio of THERMAL POWER lo RATED THERMAL POWER Fp = 2.60 K(Z) Is provided In Figure 2.6.1.
2.6.2 W(Z) Values:
a) When PDMS is OPERABLE. WM =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 Fco(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%A penalty factor shall be used at all cycle bumups that are outside the range of Table 2.6.2.
2.6.3 Uncertainty
The uncertainty, UFO, lo be applied o. the Heat Flux Hot Channel Factor Fo(Z) shall be alculated by the following formula UIe = UV. *U, where:
Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable.
(U. Is defined by PDMS when operable.)
U. = Engineering uncertainty faclor = 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
CAD-03*89, Rev. I Page 7 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Figure 2.6;1 K(Z) - Normalized F0(Z) as.a Function of Core Height 1.1 1
0.9 (0.011.0) l(6.0 1.0) t,,
-r-I.-.-I
-I I
I II I
~~~~~~~~~(12.(
10.924) 0 N
-a 0.8 a
0.7
0.6 0.5a 0___LOCA Linifing 0.4 Envel 0.3 a
a O2 0.1 _
0O 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM Core Height (f)T TOP
CAD-03-89, Rev. 1 Page 8 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable Al D Limits from -18% o +10% at J00% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Height Feel 0.0 020 0.4 0.60 0.80 1.00 1.20 lAO 1.60 1.80 1.1 200 22D 240 260 2.80
&OD 3.00 3.20 3.60 3A0 4.00 420 4.40 4.60 4.80 520 5.16 5.80 6.00 620 6.40 6.60 6.80 7.CO 7.2D 7.40 7.60 7.J0 8.20 8.60 8.8D 9.0D 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 Iuoo p120 11.40 11.60 11.80 12.0D MAX W(ZI 1.0000 la00 1t0w 1U000 3.2450 321333 L.2027 1.1836 1.1321 3.17301
.1.3650 1.1345 1.1248 1.1142 14026 3.0986 1.0983 1.3096 3.1369 1.1263 1.1339 1.1416 1.14S8 3.1620 1.1739
.1.3894 1.1971 1.2024 32102 1211 12317 1.0000 1.0=0 l.0000 3.0000 StokwAoxd hUr I Cycle I1I F~g'e 2.62A Sumaroy cI W(7) Function of 150 MWAD/M11J (Top ard 1of1am 15% Ex'ck3ded pet WCAP-10216) 1.30 125 z
Z 1.20 1.15 1.10 1.05 I*T' 0.00 2.00 4.00 6.00 8.C CORE HEIGHT (FEET)
.0 10.00 12.0O
CAD-03-89, Rev. 1 Page 9of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 1 CYCLE I J Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Heigh1 Feel 020 0.40 0.60 OWS 12D 1.60 1.80 2.O0 Z2.2 22D 260 2.80 3m 3.40 3A0 380 4.00 4.20 4.40 4.60 4.80 5m 5420 5.0 5S.
6.00 6.20 6.40 6.60 68.
7.00 720 7.40 7.60 7.80 8.00 8.20 8.40 8.60 a-so 9.00 9.20 9.40 9.60 9.80 0.00 10.20 10.40 10.60 10.80 110 1120 34AO 1160 11.80 12.00 MAA.XW(Z) 3.0000 l.000 3.0000 L.0000 1.0000o 3.0000 3l000 3I000
)AM0 13113 1US91 132634 12413 132273 32003 1.1934 131f44 3.3760 3.1684 3.1408 3.3515 3.1412 1.3313 3.1190 1.1079 3.0987 1.0931 3.095 3.099 1.13W 3.1102 3.3343 3.3205 3.1342 1.3459 1.1576 3.1698 3.3181 1.1933 1.2031 1.2121 1.2171 3.223 3.2287 3.249 1.2445 5.2630 12750 1.2S8 1204 1.2970 1.3030 1.0000 3.0000 3.000 1.000 3.0000 1.0000 3.0000 3.0000 1.0000 N~dctwood" UIt 1cycle Ii Flgwe 262.b Surnmory d W(D Function at 6000 NMWMIU (Top and Bottom 15% Eaick~ed pef WCAP-102 16)
I I I I I
I I I I I
- I t I
CAD-03-89, Rev. I Page IOof 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -1 8% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP Height feel 0-00 0.20 0>40 OLID 140 1.60 1180 200 220 2A0 26O 2.80 U3.
320 340 3.60 3.80 420 4AO 4.60 4.80
£40 520 5.43 6800 6.20 640 6.60 6.80 7.00 720 7A0 7.6 7.0 8.0 8.20 8.A0 8.60 680 9m 920 9.4 9.60 9.80 10.0 1020 10.40 10.0 10.80 11.O 11.20 1140 11.60 MO.80 12.00 MAX W(Z) 1.0000 1000 1.0000 1.0000 1L0000 13009S Am9 3.0000 33096 1.2769 1.2651 1.2512 1.2422 1.2321 120 1.2084 1.202S LIM 1.1,902 1.1120 131734 1.1639 1.1544 3.3440
'.340,1 1,401 1.140t 1.3452 1.3538 3.1704 3.33DD 1.1365 3.31913 1.1940 3.3927 3.195 3.3796 31.697 1.16Z7 L3627 t~577 1.1561 1.1561 1.1537 1.1524 1.1497 1.20S0 1.2360 1.0000 9M00 2z00 3.0000 1.0000 3.0000 1.0000 Brok1w~ood Unil I Cycle I I I
tIw 2.6.2.c
&owrmory of W(Z Fumcton ot 1400 MWO/MI (IoP mod Botom 15% Enckoded pmtWCAP-10216) 1 I I *1 I I1
CAD-03-89, Rev. I Pagc I I of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD Limils from -1 8% to + 109' at 100% RTP Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Height Fee 1100 Q20 0.60 Q80 I00 120 1.40 leo lJO 120 z40 2,60 2.80 3.0D 3.20.
3.40 3.60 3.80 too 4.20 4.40 4.60 4.80
&aOD 6.20 A40
&60
.80 6.00 6.20 6AO 6.60 b.W0 7.00 7.20
_7.60 7.80 8.00 8.20 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11.60 11.0 12.00 3.0000 3.0000 IW000 J.000 1.2590 1.2390 1.2020 3.19)0 1.1910 1.1892 1.1871 I.IW5 1.20238 1.2089 32309 32125 1.2110
.2-2~0 1-2334 1.2431 1.2501 1.2545 I2563 1.2512 3.2491 1.2430 1.2311 1.2192 3.2061 3.1914 LIMSf 3.3625 3.3644 1.1640 1.1313 1.1702 1.2110 1.2490 3222 1.3142 3.0000 3.000 3.000 ID=0 3.600 I.0OD 3.60000 1.0000 3.0000 1#Oldoodr 1. CyCle 1I Figme 2.62,d Survviory of W(Z) Fun~ction of 20000 MWD/MUl (top ond Bottom 15% Exckxcied pet WCAP..10216) 1.3s 1.30 1.25 z
0 Z 1.20
.R 1.15 I4 4LH1 I
- J..4-5 J..J....4 I
4
444..-4
.-i..I-.-J..
I I
i1
-i-rii-i rrrv iri v i-ii
-LI 1.10
-I.
I I
1.051 O.CDO 2.00 4.00 6.00 8.00 tO.00 12.O0 CORE HEIGHT (FEET)
CAD-03-89, Rev. I Page 12 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -18% to 1J0% at 100% RTI Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor-F'0(z)
(MWD/MTU)
)
495 2.00 839 44A8 1012 5.66 1184 6.58 1356 7.15 1529 7.20 1701 6.97 1874 6A9 2046 5.82 2218 5.10 2563 3.79 2735 3.35 2908 3.10 3080 3.01 3597 3.16 3769 3.09 3942 2.86 4114 2.47 4286 2.01 4459 2.00 Notes:
Linear interpolation Is adequate for Intermediate cycle bumups.
All cycle bumups outside the range of the table shall use a 2% penalty factor for cormpriance with the 3.2.1.2 Surveillance Requirements.
CAD403689: Rev. I Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable forPDMS Inoperabie AFD Limits from -18% to +1O% at I00% RTP 2.7 Nuclear EnthalPy Rise Hot Channel Factor (ETaH) (LCO 3.2.2) 2.7.1 F^H S FZTP[ 1.0 + PFX,,(1.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FZ' = 1.70 PFK = 0.3 2.7.2 Uncertainty when PDMS Is inoperable The uncertainty, UF&H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FHN shall be calculated by the following formula:
UFW4 = UF where:
UxF~= Base F%4 measurement uncertainty =1.04 2.7.3 PDMS Alarms:
F'4H Warning Setpoint a2% dof Fj Margin F ' Alarm Setpoint 2 0% of FNaH Margin 2.8 Axial Flux Difference (AFD) (LCO 32.3) 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 Deparlure from Nucleate Boilino Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRApsL 1.536 The Axdal Power Shape Umiting DNBR (DNBRpsL) 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 > 0% of DNBR Margin
CAD-03-89, Rev. I Page 14 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD limits from -1 8% to + 10% at 100% RTP Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Applicable for PDMS Inoperable AFD Umits from -18% to +10% at 100% RTP Mal FIlux Uffferermx Units vWth
-PONVS Inoperbl 120 I 6(
0200 00-
-.180 W 0 W
0
-i~p allr--
oep 40 20 -10 0 10 20 30 40 50 A)XX fUX OEffERB0i4(0/4
CA U-l3-bsy. Kev. I Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Linits from -18% to +10% at 100% RTP 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip selpoint K, shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpolnt T, coefficient K2 shall be equal to 0.0297/ eF.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient 43 shall be equal to 0.00181 / psig.
2.10.4 The nominal T.,at RTP (indicated) r 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 leadtlag lime constant sr shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant a2 shall be equal to 3 se.
2.10.8 The measured reactor vessel AT lag time constant ? 3 shall be less than or equal to 2 seec 2.10.9 The measured reactor vessel average temperature lead/lag time constant 4 shall be equal 1o 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant Ts shall be equal to 4 sec.
2.10.11. The measured reactor vessel average temperature lag time constant ai shall be-...
less than or equal 1 2 sec.
2.10.12 The 1, (Al) "positive" breakpoint shall be +10/e AI.
2.10.13 The It (Al) "negative' breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive" slope shall be +3.47% 1% Al.
2.10.15 The f1 (A negative slope shall be -2.61% 1% Al.
CAD-03-89. Rev. I Page 16 of 17 CORE OPERATING IUMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -8% to +10% at 100% RTP 2.11 Reactor Trip System (RTS) InsIrumentation (LCO 3.3.1) -Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip selpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint T9 rate/lag coefficient Ks shall be equal to 0.02 / OF for increasing T...
2.11.3 The Overpower AT reactor trip setpoint T,, rate/lag coefficient K5 shall be equal to 0 'F for decreasing T,,
2.11.4 The Overpower AT reactor trip setpolnt Tao heatup coefficient KG shall be equal to 0.00245 / °F when T > To.
2.11.5 The Overpower AT reactor trip setpolnt T,, heatup coefficient Ki shall be equal to0/'FwhenTSTo.
2.11.6 The nominal T, at RTP (indicated) T" shall be less than or equal to 588.0 eF 2.11.7 The measured reactor vessel AT lead/lag time constant so shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant t 2 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 -re shafl be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant a7 -
shall be equal to 10 sec.
2.11.12 The f2 tAl) positive' breakpoint shall be 0 for all Al.
2.11.13 The f2 (Al) negatives breakpoint shall be 0 for all Al.
2.11.14 The f2 (Al) positivde slope shall be 0 for aft Al.
2.11.15 The f2 (Al) "negativeW slope shall be 0 for all Al.
CAD-03-89, Rev. I Page 17 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD Limits from -18% to +10% at 100% RTP 2.12 Reactor Coolant System (RCS) Pressure, Temperature. and Flow Departure from Nucleate Boilina (DNB) Limits (LCO 3A.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 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1701 ppm (LCO 3.9.1).
2.132 To maintain keff 5 0.987 with ell 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) 1733 ppm prior to Initial criticality.
b) 1979 ppm at all other times In core life.
ATTACHMENT 1 Core Operating Limits Report for Braidwood Unit 2 Cycle 10
CAC-02-48 Rev. 5 CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 2 CYCLE 10
CAC-02-48, Rev. 5 PageI of i7 CORE OPERATING LlMITS 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 Not Channel Factor (Fo(Z))
LCO 3:2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,.)
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) Instrunentation 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 3.1tj Shutdown and Control Rods TRM TLCO 3-1.k Position Indication System - Shutdown (Special Test Exception)
CAC-02-48, Rev. 5 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) (S1 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 shalg not exceed the imits specified in Figure 2.1.1.
Sao S650 Lj-.
C70 i..
0-E.
U) 6200 581 247J pmi Frocdion of lNomiol Power Figure 2.1.1: Reactor Core Limits
CAC-02-48, Rev. 5 Page 3 of 17 CORE OPERATING LIMITS REPORTIcOLR) for BRAJDWOOD UNIT 2 CYCLE 10 2.2 Shutdown Marmin (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%/6 Akfk (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.]).
The SDM limit for MODE 5 is:
2.2.2 SDM shag be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1j).
2.3 ModeratorTemperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOIJAROAHZP-MTC upper limit shal be +2.57 x 10r Ak/kIF.
2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 1 Df Ak/klF.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shag be 47 x 1IJ Ak/k/OF.
2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10
~
k/k1F.
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 (LC0 3.1.6) 2.5.1 The control banks, with the Bank A greater than or equal to 224 steps, shall be lirmied in physical insertion as shown h 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 shag be sequenced in reverse order upon insertion.
CAC-02-48, Rev. 5 Page 4 of 17 CORE OPERATING LIMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE IO 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) 225 226 227 228 229 I
Overlap Lnnit (step) t10 11i 112 113 114
CAC-V2-48, iKev. >
Pagc5 of 17 CORE OPERATINGIUMITSREPORT (COLR)forBRAIDWOODUNIT22 CYCLE 10
- Figre 251::
Cor Bank Isrlon Unts Verss Percent PWd Thenal
-Power 224 (nV 22 180 C
'Su 18D CL a) 0 0
. 0 C
0 40-(1%
161) 0 10 20 30
. 40 SD
- 6) 70 OD Relve P w
e) 9D 100
CAC-02-48, Yev.
Page 6 of 17 CORE OPERATING LIMITS REPORT (COLA) for BRAIDWOOD UNIT 2 CYCLE 10 2.6 Heat Flux Hot Channel Factor Fool (LCO 3.2.1) 2.6.1 pRTP FQ(Z)< o-5 xK(Z) forP50.5 FQ(Z) <- Q xK(Z) forP>O.5 P
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FT = 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 Figukes 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 MWDIMTU.
Table 2.6.2 shows the Fca(z) penalty factors that are greater than 2ND per 31 Effective Full Power Days. These values shaD be used to Increase the Fwa(z) as per Surveillance Requirement 3.2.1.2. A 2%/iS penalty factor shall be used at an cycle bumups that are outside the range of Table 2.6.2.
2.6.3 Uncertainty-The uncertainty, UFO, to be applied to the Heat Fkux Hot Channel Factor Fa(Z) shall be calculated by the following formula U, 0 = U.,, *.,
where:
Uq = Base FO 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:
FC(Z) Warning Setpoint > 2% of Fo(Z) Margin FC(Z) Alarm Setpoint > 0% of FO(Z) Margin
CAC-02-48, Rev. 5 Page 7 of 17 CORE OPERATING LIMITS REPORT (couR) for BRAIDWOOD UNIT 2 CYCLE 10
-~~~~~~~~~~~~
Figure 2.6.1 K(Z) - Normalized Fa(Z) as a Function of Core Height 0
0Z 0
1 2
3 4
5 6
7 8
9 10 11 12 BOTTOM Core Height (ft)
,TOP
CAC-0248, Rev. 5 Page 8 of J7 CORE OPERATING LIMITS REPORT (COlR) for BRAIDWOOD UNIT 2 CYCLE I 0 Height Feet 0.0D 0.20 Q40 0.60 C8o 1.CO 1.20 1.40 1.60 1.80 200 2.20 2.40 2.60 2z0 ao.
3.20 314 16O 380 400 a.20 44D 4.60 4.80 500
&2D 640 a60 5.8 6.CO 6.20 6.4D 6.60 6.80 7.OD 720 7.40 7.60 7AO 8.00 B.20 8S.
860 8.80 9.0D 9.20 9AO 9.60 9.80 10.00 10.20 10.4O 10.60 10.80 11.00 11.20 IAdO 11.60 MSD 1ZO MAXWa) 1.0000 1.0000 3.00WD 1.00W lOW 8.1882 1.18S2 1.1684 3.3589 1.1489 1.1399 3.1304 3.1228 1.1333 1340t 1.1445 1.1472 1.3479 1.1486 1.1473 1.1450 1.1437 1.1433 1.1548 1.1656 1.1803 1.1920 1.2037 1.2125 1.2203 12261 1.2338 1.236 1.2436 1.2475 1.2463 1.247S 1.2473 1.2419 1.2536 1.2545 1.2531 1.2484 12470 1.2530 IJOW 8.0000 1.0000 1.0000 3.0000 1.0000 1.0000 1 eoo Stoidwood Unl 2 Cycle 10 Flgur 26.62 SumTmwy ot W(a) Fundon at lSO MWK/VMU (rop ond 1ot*om IS% fxcbded pet WCAP-10216) 1.35 1.30 1.25 1.15 1.10 V
I is 1.C 0.0D 2.00 4.00 6.00 8.00 t0.00 12.00 CORE HEIGHT (FEET)
CAC-02-48, Rev. 5 Page90of ]7 CORE OPERATING LTMITS REPORT (coLR) for BRAIDWOOD UNIT 2 CYCLE J 0 HdV W3 War)
F ee.
Bldd.cUrfl 2 Cyde 10 0.00 3.0000 0.20 1.0000 Flfe2A2.b 040 5.0000 0.60 I.00o0 Suvnray dW() Furacncgi60D MADMI U 0.8o 3.00o0 CcprdBdtclm 15% Exedubdcjer WCP-0 3216) 1.00 3.0o0 1.20 1.00D 1.40 I.0 l10 l.000 1.35 1.80 1.2t82 2.eo 1IS64 2.20 1.236n t
2.40 1.21_3 2.60 1.2079 2.80 MM96
-&OD L)"?R
~w 10.00
).ecoo 3.20 1.791 1.30 3ADo :.-3oo6nD 40 60
.0 OOO 10 11.40 1.1OR6HIGT FET 3.60
-,GM
,eo O1O1547
.ZOD 1-3470 4.20 1-:333 4.40 I' 303 4.80 3.127 12 5.8 1.0O3 0
6.00 3.0313 640
.3.1131m 6.60 12332 6.80 1.3354 7.00 I' 457 7.20 3.3541 7.60 3.I.6I 4 7.60 3.17671 8.20 335 SAO0 1.3759 8.60 L3.37 8.80 3.1796 9.00 1.1330 9.20 1.37p5 1.30 9.40 3.179M 9.60 3.1949 9.80 1.2030 F
10.0 J.2097 10.20 32135-------
10.60 1l000 31.00 1.000 o.oo 2.00 4.00 s.oo a.oo 10.Oo 12.00 11.20 3.0000 11.40 1.000 CORE HEIGHT (FEET) 11.60 3.0A0 12.0 3.0000
CAC-0248, Rev: 5 Page 10 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 H1p M
Wa)
Feet 0.00 1.0000 D.20 I.oo00 0.40 L.0ooO 0.60 1.000 0.80 1.0000 L.OD 000o 7.20 1.0000 1.40
.000W 1.60 1.000D L.80 1.3766 2.00 13572 7.20 1.3321 2.40 1.310t Z60 3.293 I z28 3.276 3.00 1.2632 3.20 1.2467 3.40 1.2318 3b60 1.2140 3.0 13.2043 4.0D 1.1947 4.20 3.1834 4.4D 1.1721 4hD 1.1609 4.80 1.1477 5.00 3.1341 5.20 1.1314 5.40 3.1237 5.6b 1.325 s58 1.122.
6.OO 1.1236 6.20 1.1324 6.4) 1.1382 6.60 1.1427 6.80 1.1449 7M 1.1464 7.20 1.1476 7.40 3.1464 7.60 1.1396 r7.8D
-1.357.
8.OO 1.1306
&20 1.1207 8.40 1.3 131 8.60 1.1073 8.80 1.1034 9.0D 3.1050 9.20 1.1017 9.40 1.1133 9.60 1.1139 9.80 3.12S5 tOO 1.1593 3020 1.3890 10.40 3.0000 10.60 1.000 30.80 3.0000 l1.00 I.0000 1120 1.0000 11.40 1.000 11.60 1.000D 11.80 1.0o0 12.OD 1.000D Blddt7Urd32Cyde 10 Fi9e2.2.c Sutrray et W(Z)Fuic~m d 14000 MvNOP U (rcpid Beffcn 15% ExduXedw WCAP-10216)
I I.
.1
.1 _.1 I
A -I t
I1 I I.i I
I.I f 4113 I I I.
I I I I i-I I I I
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CAC-02-4S, Rev. 5 Page II of 17 CORE OPERATING LlMlTS REPORT (CoLR) for BRAIDWOOD UNIT 2 CYCLE Io Hvt Feel a0.0 Q20 0.40 0.60 0.80 1.00 120 VAD 1.60 2JO 2.20 2AD 2.60 2.a0 3.00 3.20 3A0 3.60
.00 420 4A0 480 5.00 5430 360D 5.80 6.20 6Ao
&.60 SSOD am 7.20 740 7.0 7.80 8.00 8.40 8.60 8.80 9.CO 9.2D 9.40 9.60 980 10.00 10.20 10.0 10.60 108o 11.O0 11.20 1U.40 11.60 11.80 12.00 mkxw~z) 130000 1.8000 1.8000D L.0000 1.80000 I.8000 I.C00D 1.CODD 1.25t3 1.7317 1.2124 1.1966 1.1SS3 1.170D 1.161 1.1670 1.1657 1.732 1.1842 1.1914 1.1969 12 1.2004 1.2165 1.22S0 1.2374 12417 12433 1243?
1.23S7 1 2326 122216 1
6 1,.1955 1.1732 t.1633 1.1475 1.1435 1.1410 1.1833 IJ1349 1.1151 1.2267 1640 1.3048 I.0000
.0000 1.0000 l.OOOD 1.000M I.OCOD l.0000 I.OOOD 1.0000 Brdd..dUrit 2 Cyde 0 Figpxe26.2.d Surrroy diW(Z)Ftrdlmn d 2000 &ROMrU 1cpid~cila Sn1% ExduxbpsWCAP-1 0216)
I I I t
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1.
CAC-02-48, Rev. 5 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 Bumup Penally Factor - Fco(z)
(MWD/MTlU)
%)
2038 2.00 3068 3.13 3239 3.24 3411 3.30___
3583 3.28 3754 3.18 3926 3_00 4612 _
2.04 10791 2.00 10963 2.08 11477 2.32 116-49 2.38 11821 2.41 11992 2.46 12164 2.47 42336 2-45 12507 2.41 12679 2.27 12850 2.00 Notes-LUnear Interpolation is adequate for intermediate cycle bumups.
All cycle burnups outsidd 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. S Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.7 Nuclear Enthaloy Rise Hot Channel Factor (F!M) (LCO 3.2.2) 2.7.1 FN. S F^,1.O + PFH(1.0 - P)j where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
~~~Fr,"HP 1.70 PF
= 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFaH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor Fm shall be calculated by the following formula:
UFdH = UF',.m where:
U&*,,= Base F'H measurement uncertainty =1.04 2.7.3 PDMS Alarms:
FKH Warning Selpoint 2 2% o F" 6 Margin F:, Alarm Setpoint 2 0% of FON Margin 2.8 Axial Flux Dilference (AFDI (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 DNBRAmPS 21.536 The Axial Power Shape Limiting DNBR fDNBRpW is applicable with THERMAL POWER 2 50% RTP when PDUS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint 2Ž2% of DNBR Margin DNBR Alarm Selpoint 2 Ž0% of DNBR Margin
CAC-o2-48, Rev. 5 Page 14of17 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
CAC-02-4 8, Rev. 5 a
1 Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 10 2.10 Reactor rno 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 seipoint Tw coefficient K2 shall be equal to 0.0297/ /F.
2.10.3 The Overiemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 /psi.
2.10.4 The nominal T., at RTP (indicated) T' shall be less than or equal to 588.0 -F.
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~ag time constant r, shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant r2shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant r3shal 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 leadtlag tirme constant T.
shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant Ts shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) 'positive breakpoint shag be +10/ Al.
2.10.13 The 1s (A1) 'negative' breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positives slope shall be +3.47% 1 % Al.
2.10.15 The f (Al) 'negative slope shag be -2.61%I % Al.
CAC 4 S, Rev. 5
_.CAC-)2-48, Rev. 5 Pg 6f1 Page 16 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE I0 2.11 Reactor TriP Svstem fATS) 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 T>, rate/lag coefficient Ks shall be equal to 0.021 °F for increasing T, 2.11.3 The OverpowerAT reactor trip setpoint T., ratellag coefficient Ks shall be equal to 01 OF for decreasing T..
2.11.4 The Overpower AT reactor trip setpoint T,, heatup coefficient K6 shall be equal to 0.002451 'F when T > T.
2.11.5 The Overpower AT reactor trip setpoint T9heatup coefficient K6shall be equal toO IF when T:5 T.
2.11.6 The nominal T.> 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 t, shall be equal to 8 see.
2.11.8 The measured reactor vessel AT leadlag tire constant x2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant vr shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperaturelag time constant 'sshall fU less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant s7 shall be equal to 10 sec.
2.11.12 The 12 (A) 'posftive' 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 12 (A) 'positivf' slope shall be 0 for all Al.
2.11.15 The 2(Al) 'negative slope shall be 0 for all Al.
CAC-02-48 Rev. 5 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 Boilina (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 386,000 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 31.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.