ML032681094
| ML032681094 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/17/2003 |
| From: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW030074 CAD-03-89, Rev 1 | |
| Download: ML032681094 (19) | |
Text
ExelonS.
Exelon Generation Company, LLC Braidwood Station www.exeloncorp.com Nuclear 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 September 17, 2003 BW030074 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456
Subject:
Core Operating Limits Report, Braidwood Unit 1 Cycle 11 The purpose of this letter is to transmit a recently implemented, previously approved version of the Braidwood Station Unit 1 Cycle 11 Core Operating Limits Report (COLR) in accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR)." Two versions of the COLR specifying different axial flux difference (AFD) limits with the Power Distribution Monitoring System (PDMS) inoperable were approved for Braidwood Unit 1 Cycle 11. The originally implemented COLR for Braidwood Unit 1 Cycle 11 specified AFD limits from -18% to +10% at 100% rated thermal power (RTP) with PDMS inoperable and provided a minimum 2% AFD margin to address potential Axial Offset Deviation issues at the beginning of the cycle. The attached version of the COLR supersedes the originally implemented version of the COLR for Braidwood Unit 1 Cycle 11 and specifies AFD limits from -16% to +10% at 100% RTP with PDMS inoperable. Braidwood Station has elected to implement this previously approved version of the COLR at this time based on core performance. This change is expected to improve margins to peaking factor limits.
If you have any questions regarding this matter, please contact Ms. Kelly Root, Regulatory Assurance Manager, at (815) 417-2800.
Michael J. Pacilio Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report, Braidwood Unit 1 Cycle 11 (CAD-03-89, Rev. 1) cc: Regional Administrator - NRC Region IlIl 0 NRC Senior Resident Inspector - Braidwood Station
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 1, Cycle 11 (CAD-03-89, Rev. 1)
CAD-03-89, Rev. I CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP
CAD-03-89, Rev. I Page 2 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAJDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -16% to + 10% at 100% RTP 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 1 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 Reator 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 EnIhalpy Rise Hot Channel Factor (F',)
LCO 3.2.3 Axial Flux Difference (AFD)
LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
J LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCO 3A.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 Techur4al 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 TCO 3.1.h Shutdown Margin (SDM) - MODE 1 and MODE 2 with keff 21.0 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)
CAD-03-89, Rev. I Page 3 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 1 Applicable for PDMS Inoperable AFD Limits from -16% 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 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.
£80 2471 psia 660-2250 psla 64) 620~
CD 600 58!
.. I ' .v .
Froction of Nominol Power Figure 2.1.1: Reactor Core Limits
CAD-03-89, Rev. 1 Page4of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP 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) imits are:
2.3.1 The BOUAROIHZP-MTC upper limit shall be +1.1 85 x 10'5 Ak/kfPF. -
2.3.2 The EOUAROIHFP-MTC lower limit shall be -4.6 x 1044k/kI0 F.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 104 ak/krF.
2.3.4 The EOlARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 104 Ak/kF.
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 nphysical 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 nsertion.
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
Page 5 of 17 CAD-03-89, Rev. I CYCLE II CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP igtre,251:
Conlro Bank Inserlion Units Versus Percent Rated Thenmi (Z r/2 24) (7rIob 23 224 22 (Urx4 161)
IC la 3
a-0
_~~
C 0
1~~
4-0 Ix C
x 0
0 10 20 30 40 59 60 70 8) 90 100 RPeaieRr( (Pwt)
CAD-03-89, Rev. I Page 6 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP 2.6 Heat Flux Hot Channel Factor (E(Z)) (LCO 3.2.1) 2.6.1 FR7P FQ(Z) - 9 Q5 xK(Z) forP<0.5 0.5 FRT1 FQ(Z) < Q xK(Z) for P>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F."= 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 FWa(z) as per Surveillance Requirement 3.2.1.2. A 2% 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, UFr, to be applied to the Heat Flux Hot Channel Factor F0 (Z) shall be dclculated by the following formula U,, 0 =U* .U.
where:
Uq = Base FO measurement uncertainty = 1.05 when PDMS is inoperable.
(Uqu is defined by PDMS when operable.)
U., = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
FQ(Z) Warning Setpoint 2 2% of Fa(Z) Margin FQ(Z) Alarm Setpoint 2 0% of F0 (Z) Margin
CAD-03-89, Rev. I Page 7 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height N
1+/-
AL lS E
0 z
N Ad 0 1 2 3 4 5 6 7 8 9 10 11 12
.. BOTTOM CoPre Helqpt ft) 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 AFD Limits from -1 6% to + 10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Height MAX W(Z)
Feet Brodklwoo Unit 1 Cycle 11 0.00 3.0D0 0.20 1.0000 Figwe 2.6.2.o 0.40 1.0000 0.60 1.0000 9STxyiy of W(Z) Function ot 150 MWOIMIU 0.80 3.0000 (Top ond Bottom 15% Excled per WCAP-10216) 1.00 3.0000 1.20 1.0000 1.4 1.0000 1.60 1.0000 t.35 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
C5 1.80 12060 2.00 1.2012 2.20 1.1954 Ir 2A0 2.60 1.1904 1.1834 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ III 2.80 1.1766 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 11 3.00 3.20 1.1698 1.1615 1.30 , -r 3.40 1.1535 3.60 1.1435 3.80 1.1352 4.00 1.1261 4.20 1.153 4.40 4.60 4.80 S5 1.1061
.11041 1.1022 1.0999 1.25 .1- - - - ----- - - - -_--1--- - --
520 3.0977 5.40 1.1012 5.60 1.1094 580 1.1179 O 6.00 1.1262 620 1.133S E . .. . 9 X 1.1405 Z 1.20 6.40 6.60 1.1459 R .-
6.80 1.1533 .> .
7.00 1.1639 720 1.1738 7.40 l.1l42 7.60 1.1916 7.80 1.19S7 1.15 8.00 3.2048 8.20 1.2074 8.40 8.60 8.80 9.00 9.20 12108 12103 1.21 17 1.213 1.2110 I1 t! 23 ] 2 - 2 01 9.40 1.2101 1.10 .%
9.60 1.207D 9.80 10.00 10.20 1.2072 1.2199 1.2340 10.40 3.000 10.60 3.0000 10.80 l.DOO 11.00 1.0000 1.05 11.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.o0 11.40 1.000 11.60 1.0000 CORE HEIGHT (FEET) 11.80 1.0000 12.o l.00O
CAD-03-89, Rev. 1 Page 9 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE I I Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Height MAX W(Z)
Feet Broidwood Urit 1Cycle 11 0.00 I.00W 020 1.0000 Figure Z6.2.b 0.40 1.0000 0.60 1.0000 Summnay of W(Z) Furction ot 6000 MWDIMTU 0.80 .0000 (rop and Bottorn 15% Exckided per WCAP-10216) 1.00 1.0000 1.20 1.0000 1.40 1.0000 1.60 .0000 1.S5 1.80 l.2676 ; IIIIIIIIIIIIIIIIII111111 2.00 1.2454 TlTrT Tfl Tgrl rl § l m gt t Ll r Er l TI r TI I I rr¢ l T1 Tn l 2.20 1.2221 2A0 1.2009 2.60 1.173 2.B0 1.1695 1 111 xrr 3.W 3.20 1.1652 1.1582 1.30 __ ____ ___ I m 1'11 3J0 t XM 1.1529 3.60 1.1468 3.B0 1.1397 4.00 1.1318 420 1.1220 4.40 4.60 4.80 1.1130 1.1067 1.1038 125 . ___ _X _ X_ f X I IT 0: __
5.00 5.20 1.097 1.0947 , __ _X._ +___ ___ *1 _
_ __ ___ _. +_ ___ __ __ _ _
5A0 5.60 5.80 1.0948 1.094 1.1019 z
0 6.00 620 1.1064 1.1110 E
z 1.20 6A0 1.1205 660 6.80 7.00 1.1342 1.1469 1.1577 g.,
1.1 I - . -
720 :1683
_ _ _ _ , _ _ _ _ _ _ _ _ F _ . _ _ _ _ .
7A0 1.3805 7.60 1.1921 _ _ _ _ _ v _ _ _ _ _ _ . __ _ _ _ _ _ _ _
7.80 1.2027 t15.
8.00 820 1.2117 1.216S 8.40 1.2265 L..
8.60 1.2336 8.80 1.239S 9.00 1.2470 9.20 1.26S0 9A0 9.60 1.2790 1.2930 1.10 - - - - -- - - - "t H - -- - - - X 9.80 1.2990 10m 1.3020 10.20.
10.40 1.3070 1.0000
- - - - -- - -- - - X Z 10.60 1.OO 10.80 1.0000
.o 1.0000 1.05 111.20 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 1lA0 1.0000 CORE HEIGHT (FEET) 11.60 3.0000 11.80 l.00W 12.O l.OWO
CAD-03-89, Rev. I Page IO of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Height MAX W(Z)
Feet Brokiwood Unit I Cycle I O.o0 1.0000 0.20 3.0o00 FIge 2.6.2.c 0A 1.0000 0.60 J.000 Sumny of W(Z) Funclion ot 14000 MWDJM1U 0.80 2.0000 (rop and Bottom 15% Exchded per WCAP-10216) 1.00 1.0000 1.20 1.0000 lAO l.OWO 1.60 I oooo 5 I I I I I I I T I I I I I I I I 11 1.80 1.2831 2.0 1.2731 2.20 2.40 260 1.2567 1244S 1.2310 TI I I rrr t l m r TI r 1111111 111111
, l lll l ll ; §§§rr 2J0 1.2132 3.0 1.2070 3.20 1.1949 1.30 3.40 1.1903 3.60 1.13s6 3.80 1.1323 400 1.1758 420 4AD 4.60 4.80 50 1.16S7 1.1612 1.1527 1.1442 1.1396 125 ,lMr :-- i if 0.f 00 1 1H 1 1 ^
5.20 SAO 1.140S 1.1401 1 11 t . . .
5.60 1.1408 T X 5.80 1.1452 O
- , X iiii 6.0 1.1538 0 6.20 1.1704
, 1.20 6.40 1.2300 IL 6.60 1.165 6.80 1.1913 7.D 1.1940 .15 7.20 1.193S 7.40 7.60 7.80 1.1927 1.1395 L.1355 1.t5
... . FKF 8.00 1.1796 820 1.1697 .
80 1.1627 '..
0.60 1.1577 8.80 1.1546 9.00 1.1537 0 i ; ; iii i 920 1.1522 9A0 1.149 1.10 9.60 1.1519 9.80 1.1780 10.00 1.2070 10.20 1.2350 .
10.40 .0000 IQ60 1.0000 X X XXXX XX X 10.80 I.OWO 11.00 I.OD00 1.05 1 120 1.0000 0.00 2.00 4.00 6.00 8.00 10.00 12.00 1AO 1.0000 CORE HEIGHT (FEET) 11.60 1.0000 11.80 1.0000 IZOO 1.0000
CAD-03-89, Rev. I Page I I ofi17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Height MAX W(Z)
Feel Brdidwood Unit 1 Cycle 11
.OODO 020 1.0000 Figue 2.6.2.d 0.40 1.0000 0.60 .0000 Summwry of W(Z) Functbn of 2W000 MWDmTU 0.80 I.OOOD (Top and Bottom 15% Excluded per WCAP-10216) 1.00 1.0000 1.20 1.0000 1AO 1.0000 1.60 1.0000 1.80 32906 2.00 32771 2.20 1.2607 240 1.2452 260 1.225S 2.80 1.20S4 3.00 1.1900 3.20 1.1777 3AO 1.17S0 3.60 1.174 3.80 1.1770 I:
1.1754 I
4.00 4.20 1.1770 II 4.40 1.3873 4.60 4.80 1.1954 12028 f 5.20
~~~SAO 1.20S9 1.2109 I
- 1.2125 I I I
I.
5.60 1.2110 5.80 1.2207 1.2334 II I
6.O0 620 1.2431 640O 1.2508 6.60 1.254S 6.80 1.2563 III I
7.00 1.2552
.1 I
7.20 1;2491 7.40 1.2430 7.6D 1.2311 7.50 1.2192 8.00 8.2D 8.40 1.2063 1.1914 1.1775 I.
8.60 1.6i3 8.80 1.1664 9.0 1.166S 9.20 1.1642 9.0 1.1735 9.60 1.2151 9.80 1.2516 10.00 1.2861 10.20 13207 10.40 1.0000 10.60 1.0000 10.80 1.0000 11.00 1.00O 1120 l.00O 11.40 l.0000 11.60 1.0000 11.80 1.0 12.00 1.0000
- CAD-03-89, Rev. 1 Page 12 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP Applicable for PDMS Inoperable AFD Limits from -1 6% to +1 0% at 100% RTP Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor - F"o(z)
(MWD/MTU) (%)
839 2.00 1012 3.13 1184 4.21 1356 5.15 1529 5.92 1701 6.47 1874 6.67 2046 6.00 2218 5.28 2563 3.97 2735 3.53 2908 3.28 3080 3.19 3425 3.28 3597 3.31
. 3769 3.23 3942 3.00 4114 2.61 4286 2.13 4459 . .2.00 Notes:
Linear interpolation is adequate for intermediate cycle bumups.
All cycle bumups outsidethe range of the table shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
CAD-03-89, Rev. I Page 13 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% lo + 10% at 100% RTP 2.7 Nuclear Enthalpy Rise Hot Channel Factor FN) (LCO 3.2.2) 2.7.1 FH < FH [1.0 + PF,,(1.0- P)J where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FZ= 1.70 PFH = 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:
UFAH = UFAH.e where:
UFj,, = Base FNAH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNmJ Warning Setpoint 2 2% of FNm Margin FNAH Alarm Setpoint 2 0% of FNH 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 Whbn 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 21.536 The Axial Power Shape Limiting DNBR (DNBRpst) is applicable with THERMAL POWER Ž 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint 2 2% of DNBR Margin DNBR Alarm Setpoint 2 0% of DNBR Margin
CAD-03-89, Rev. I Page 14 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE II Applicable for PDMS Inoperable AFD Limits from -16% 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 Limits from -16% to +10% at 100% RTP
CAD.03 -89, Rev. Page 15 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP 2.10 Reactor Tri 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 setpointTR. coefficient K2 shall be equal to 0.0297 F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient 13 shall be equal to 0.00181 I 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 lead/lag time constant r shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant T2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant 13 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 s5 shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant Tr 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) -negativer breakpoint shall be -18% Al.
2.10.14 The f (Al) positive slope shall be +3.47% % Al.
2.10.15 The f (Al) negative" slope shall be -2.61%% Al.
CAD-03-89, Rev. I Page 16 of 17 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP 2.11 Reactor Trio System (TS) 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 Tvg rate/lag coefficient K5 shall be equal to 0.02/ F for Increasing T,,v 2.11.3 The Overpower AT reactor trip setpoint Tg ratellag coefficient Ks shall be equal to 0 / OF for decreasing Tng, 2.11.4 The Overpower AT reactor trip setpoint T., heatup coefficient Kr, shall be equal to 0.002451F when T > T".
2.11.5 The Overpower AT reactor trip setpoint T., heatup coefficient Kr, shall be equal to 0 OF when T
- T".
2.11.6 The nominal Tag at RTP (indicated) To shall be less than or equal to 588.0 F 2.11.7 The measured reactor vessel AT lead/lag time constant r shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT leadAag time constant 2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT 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 r6 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 (Al) 'positive" slope shall be 0 for all Al.
2.11.15 The f2 (Al) negative' slope shall be 0 for all Al.
CAD-03-89, Rev. I Page 17 of 17 CORE OPERATING LMTS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 11 Applicable for PDMS Inoperable AFD Limits from -16% to +10% at 100% RTP 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (NB) 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 (Tvg) 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).
2.13.2 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) 1733 ppm prior to initial criticality.
b) 1979 ppm at all other times in core life.