ML12305A468
| ML12305A468 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/30/2012 |
| From: | Enright D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW120106 | |
| Download: ML12305A468 (17) | |
Text
October 30, 2012 BW120106 U.S. Nuclear Regulatory Commission ATIN: 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 17 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 17, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR)." Braidwood Unit 2 Cycle 17 COLR, Revision 6 was implemented during Braidwood Unit 2 Refueling Outage 16 in support of Cycle 17 operation. Note that Revision 6 is the original version of the Braidwood Unit 2 Cycle 17 COLR implemented in support of Cycle 17 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 2 COLR, I.e., Braidwood Unit 2 Cycle 16 COLR, Revision 5.
If you have any questions regarding this matter, please contact Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.
Daniel J. Enright Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 17, Revision 6 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station NRC Project Manager, NRR Illinois Emergency Management Agency - Division of Nuclear Safety
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 2 CYCLE 17 EXELON TRACKING ID:
COLR BRAIDWOOD 2 REVISION 6
COLR BRAIDWOOD 2 Revision 6 Page 1 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 17 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 (F NilH)
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 (BOPS)
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)
COLR BRAIDWOOD 2 Revision 6 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 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 .,----....---'---.,.-----,..----,,-------,------.
660 -t---...;;~I::---_+_---_+_---I----_+---_1
'G:'
~
c3
- 640 +-----+----.:::~==__---t_---+_-....;;:",._.:;::__+---__1
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e Q)
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600 +----+-----1-----t--~ood-----+--..:::::....o::::::_-1 o .2 .4 .6 .8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
COLR BRAIDWOOD 2 Revision 6 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 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% ~k1k (lCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TlCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).
The SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% ~k1k (lCO 3.1.1, lCO 3.3.9; TRM TlCOs 3.1.i and 3.1.j).
2.3 Moderator Temperature Coefficient (MTC) (lCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOLIARO/HZP-MTC upper limit shall be +1.772 x 10-5 ~k1k1°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 ~k1k1°F.
2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 ~k/k1°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 ~k1k1°F.
where: BOl stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOl stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (lCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (lCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.
2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.
2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:
Park Position (step) Overlap Limit (step) 226 111 227 112 228 113 229 114
COLR BRAIDWOOD 2 Revision 6 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%,224) (77%,224) 220
, , r
/
/ I
/
V 200 i 180 ~
hANKB I
~
V C
3 160
~
/ 1V (100%,161)
/1L I /
1(0%,162) 1
":5
~ 140
,/
til IBANKe Q.
~ 120
/~
c o
+:
.~ 100 0.
V I
/
/ IBANKO I
.:t:.
C
~
a:I 80 / i
/
"D::
o / /
60 / /
40
/
"'(0%,47) I i
I I /
V 20 V
1(30%,0)V o
o 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BRAIDWOOD 2 Revision 6 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.6 Heat Flux Hot Channel Factor (Fg(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ(Z) ~-Q-xK(Z) forP~0.5 0.5 F RTP FQ(Z) ~ -Q-xK(Z) for P > 0.5 P
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~TP = 2.60 K(Z) is provided in Figure 2.6.1.
Figure 2.6.1 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.1 (0.0 1.0) (6.0, 1.0)
(12.( ,0.924)
"""'l 0.9 0.8 N 0.7 a
,.,u.
Cl) 0.6 J:!111
...0E 0.5 z
N .....LOCA Limiting
~ 0.4 Envelope I--
0.3 0.2 0.1 o
012 3 456 7 8 9 10 11 12 BOTTOM Core Height (tt) TOP
COLR BRAIDWOOD 2 Revision 6 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 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 as:
- 1) Table 2.6.2.a are the normal operation W(Z) values for the full cycle and correspond to the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The normal operation W(Z) values have been determined at burnups of 150, 6000,14000, and 20000 MWD/MTU.
- 2) The EOL-only normal operation W(Z) values provided in Table 2.6.2.b may be used for cycle burnups :2: 18000 MWD/MTU. The EOL-only W(Z) values correspond to the REDUCED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The EOL-only normal operation W(Z) values have been determined at burnups of 18000 and 20000 MWD/MTU and the last column of W(Z) values is a duplicate of the 20000 MWD/MTU values. If invoked, the EOL-only W(Z) values are to be used for the remainder of the cycle unless superseded by a subsequent analysis.
Table 2.6.2.c shows the Feo(z) penalty factors that are greater than 2% per 31 Effective W
Full Power Days (EFPD). These values shall be used to increase the F o(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burn ups that are outside the range of Table 2.6.2.c.
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula U FQ = U qll eU e where:
Uqu =Base Fo measurement uncertainty =1.05 when PDMS is inoperable (U qu is defined by PDMS when OPERABLE.)
Us = Engineering uncertainty factor = 1.03 2.6.4 PDMS Alarms:
Fo(Z) Warning Setpoint =2% Fo(Z) Margin Fo(Z) Alarm Setpoint =0% Fo(Z) Margin
COLR BRAIDWOOD 2 Revision 6 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.a Full Cycle W(Z) versus Core Height for AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-10216)
Height 150 6000 14000 20000 (feetl MWD/MTU MWD/MTU MWD/MTU MWDIMTU 0.00 (core bottoml 1.2875 1.4463 1.4370 1.3976 0.20 1.2772 1.4175 1.4240 1.3732 0.40 1.2740 1.4005 1.4070 1.3580 0.60 1.2698 1.3866 1.3910 1.3429 0.80 1.2558 1.3654 1.3460 1.3163 1.00 1.2465 1.3486 1.3280 1.2974 1.20 1.2488 1.3320 1.3130 1.2864 1.40 1.2598 1.3231 1.3010 1.2723 1.60 1.2461 1.3017 1.2720 1.2601 1.2821 1.2616 1.
2.00 1.2207 1.2615 1.2539 1.2430 2.20 1.2059 1.2383 1.2430 1.2305 2.40 1.1926 1.2175 1.2332 1.2201 2.60 1.1768 1.1958 1.2201 1.2057 2.80 1.1694 1.1796 1.2092 1.1924 3.00 1.1618 1.1758 1.1965 1.1780 3.20 1.1531 1.1719 1.1812 1.1640 3.40 1.1475 1.1675 1.1690 1.1637 3.60 1.1426 1.1616 1.1654 1.1620 3.80 1.1375 1.1557 1.1624 1.1614 4.00 1.1332 1.1493 1.1588 1.1620 4.20 1.1339 1.1409 1.1538 1.1615 4.40 1.1345 1.1325 1.1492 1.1591 4.60 1.1341 1.1231 1.1422 1.1608 1.1328 1.1137 1.1347 1.1683 5.00 1.1304 1.1037 1.1268 1.1738 5.20 1.1270 1.0962 1.1292 1.1786 5.40 1.1227 1.0913 1.1314 1.1819 5.60 1.1231 1.0876 1.1318 1.1925 5.80 1.1300 1.0907 1.1311 1.2108 6.00 1.1366 1.0963 1.1425 1.2264 6.20 1.1414 1.1043 1.1551 1.2389 6.40 1.1451 1.1110 1.1667 1.2486 6.60 1.1479 1.1177 1.1754 1.2542 6.80 1.1487 1.1234 1.1811 1.2580 7.00 1.1495 1.1282 1.1859 1.2588 7.20 1.1474 1.1345 1.1868 1.2546 7.40 1.1565 1.1449 1.1867 1.2496 7.60 1.1655 1.1536 1.1827 1.2396 7.80 1.1738 1.1617 1.1778 1.2277 8.00 1.1812 1.1694 1.1700 1.2139 8.20 1.1870 1.1748 1.1592 1.1962 8.40 1.1924 1.1804 1.1475 1.1784 8.60 1.1957 1.1885 1.1329 1.1597 8.80 1.1995 1.2000 1.1324 1.1452 9.00 1.2019 1.2182 1.1364 1.1396 9.20 1.2110 1.2354 1.1422 1.1340 9.40 1.2222 1.2522 1.1508 1.1510 9.60 1.2325 1.2674 1.1583 1.1950 9.80 1.2427 1.2818 1.1730 1.2330 10.00 1.2523 1.2955 1.2010 1.2670 10.20 1.2597 1.3075 1.2330 1.2970 10.40 1.2577 1.3100 1.2560 1.3220 10.60 1.2327 1.3055 1.2780 1.3360 10.80 1.2356 1.3037 1.2880 1.3540 I
11t=+
11.00 11.
11.
1.2318 1.2407 1.2411 1.2445 1.3136 1.3177 1.3300 1.3359 1.2870 1.2760 1.2820 1.2664 1.3680 1.3770 1.3700 1.3562 11.80 I 1.2498 1.3426 1.2603 1.3501 12.00 (core too' I 1.2574 1.3584 1.2560 1.3518 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BRAIDWOOD 2 Revision 6 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.b EOl-only W(Z) versus Core Height for AFD Acceptable Operation Urn its in Figure 2.8.1.b (Top and Bottom 8% Excluded perWCAP-10216)
Height 18000 20000 25330 ffeet! MWD/MTU MWDIMTU MWD/MTU 0.00 (core bottom) 1.2717 1.2572 1.2572 0.20 1.2569 1.2365 1.2365 0.40 1.2428 1.2226 1.2226 0.60 1.2290 1.2083 1.2083 0.80 1.1982 1.1862 1.1862 1.00 1.1827 1.1707 1.1707 1.20 1.1733 1.1627 1.1627 1.40 1.1636 1.1513 1.1513 1.60 1.1581 1.1443 1.1443 1.80 1.1533 I 1.1388 1.1388 2.00 1.1475 1.1320 1.1320 2.20
- 1.1394 1.1227 1.1227 2.40 1.1324 1.1150 1.1150 2.60 1.1261 1.1108 1.1108 2.80 1.1223 1.1110 1.1110 3.00 1.1223 1.1132 1.1132 3.20 1.1236 1.1180 1.1180 3.40 1.1253 1.1227 1.1227 3.60 1.1261 1.1264 1.1264 3.80 1.1266 1.1298 1.1298 4.00 1.1291 1.1369 1.1369 4.20 1.1320 1.1438 1.1438 4.40 1.1364 1.1521 1.1521 4.60 1.1445 1.1608 1.1608 4.80 1.1512 1.1683 1.1683 5.00 1.1559 1.1738 1.1738 5.20 1.1601 1.1786 1.1786 5.40 1.1634 1.1819 1.1819 5.60 1.1700 1.1925 1.1925 5.80 1.1797 1.2108 1.2108 6.00 1.1940 1.2264 1.2264 6.20 1.2069 1.2389 1.2389 6.40 1.2178 1.2486 1.2486 6.60 1.2249 1.2542 1.2542 6.80 1.2294 1.2580 1.2580 7.00 1.2320 1.2588 1.2588 7.20 1.2295 1.2546 1.2546 7.40 1.2257 1.2496 1.2496 7.60 1.2173 1.2396 1.2396 7.80 1.2074 1.2277 1.2277 8.00 1.1950 1.2139 1.2139 8.20 1.1789 1.1962 1.1962 8.40 1.1624 1.1784 1.1784 8.60 1.1436 1.1597 1.1597 8.80 1.1341 1.1452 1.1452 9.00 1.1315 1.1396 1.1396 9.20 1.1298 1.1340 1.1340 9.40 1.1425 1.1510 1.1510 9.60 1.1699 1.1950 1.1950 9.80 1.1978 1.2330 1.2330 10.00 1.2303 1.2670 1.2670 10.20 1.2628 1.2970 1.2970 10.40 1.2886 1.3220 1.3220 I 10.60 1.3080 1.3360 1.3360 10.80 1.3236 1.3540 1.3540 11.00 1.3301 1.3680 1.3680 11.20 1.3292 1.3770 1.3770 11.40 1.3272 1.3700 1.3700 11.60 1.3109 1.3562 1.3562 11.80 1.3037 1.3501 1.3501 12.00 (core top) 1.3011 1.3518 1.3518 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BRAIDWOOD 2 Revision 6 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor (MWD/MTU) Fl,;Q(z) 11218 1.0200 11391 1.0217 11564 1.0241 11736 1.0264 11909 1.0287 12082 1.0311 12255 1.0329 12428 1.0345 12601 1.0360 12774 1.0332 12947 1.0297 13120 1.0260 13293 1.0219 13466 1.0200 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.
COLR BRAIDWOOD 2 Revision 6 Page 10 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 N
2.7 Nuclear Enthalpy Rise Hot Channel Factor (F DJ:J1 (LCO 3.2.2)
F ilH :s; F~~P[1.0 + PFilH(1.0 - P)]
N
2.7.1 where
P =the ratio of THERMAL POWER to RATED THERMAL POWER F~~P = 1.70 PFilH =0.3
2.7.2 Uncertainty
The uncertainty, UFilH , to be applied to the Nuclear Enthalpy Rise Hot Channel Factor N
F ilH shall be calculated by the following formula:
where:
UFdHm = Base FNilH measurement uncertainty = 1.04 when PDMS is inoperable (U FilHm is defined by PDMS when OPERABLE.)
2.7.3 PDMS Alarms:
F ilH Warning Setpoint =2% F ilH Margin N N F ilH Alarm Setpoint =0% F ilH Margin N N 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX 01 FFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below or the latest valid PDMS Surveillance Report, whichever is more conservative.
a) Figure 2.8.1.a is the full cycle AFD Acceptable Operation Limits associated with the full cycle W(Z) values in Table 2.6.2.a.
b) Figure 2.8.1.b is the Reduced AFD Acceptable Operation Limits which may be applied after 18000 MWD/MTU. The Reduced AFD Acceptable Operation Limits are associated with the EOL-only W(Z) values in Table 2.6.2.b. Prior to changing to Figure 2.8.1.b, confirm that the plant is within the specified AFD envelope.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPsL 2 1.539 The Axial Power Shape Limiting DNBR (DNBRAPsd is applicable with THERMAL POWER 2 50% RTP when PDMS is OPERABLE.
2.9.2 PDMS Alarms:
DNBR Warning Setpoint =2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin
COLR BRAIDWOOD 2 Revision 6 Page 11 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Figure 2.8.1.a:
Axial Flux Difference Limits as a Function of Rated Thermal Power (Full Cycle)
Axial Flux Difference Limits with PDMS Inoperable 120
(-15 100) (+10, 00) 100 W
0:: Unacc eptablE / \ Una ccepta lie 3:
0 80 Ope ation J 0 eratio 1
\
a.
..J
- E 0::
W 60
/ A ~cepta >Ie c peratic n
~
J:
t-o W
/ \
t-(-3 p,50' (+ 25,5( >>)
....~
0 40 0~
20 o I
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 2 Revision 6 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 Figure 2.8.1.b:
Reduced Axial Flux Difference Limits as a Function of Rated Thermal Power (Cycle burnup ~ 18000 MWD/MTU)
Axial Flux Difference Limits with PDMS Inoperable
(-10, 100) 100 +---+-----+---+---,.---10-.......--1----+----+---1 a::
w 3:
~ 80
-I
- is
~
~ 60 -t + +
l-e w
(-20,
~
-o ere 40 o
-50 -40 -30 -20 -10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 2 Revision 6 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature t.T Setpoint Parameter Values 2.10.1 The Overtemperature t.T reactor trip setpoint K 1 shall be equal to 1.325.
2.10.2 The Overtemperature t.T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297/ of.
2.10.3 The Overtemperature t.T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal T avg at RTP (indicated) T' shall be less than or equal to 588.0 of.
2.10.5 The nominal RCS operating pressure (indicated) pi shall be equal to 2235 psig.
2.10.6 The measured reactor vessel t.T lead/lag time constant '1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel t.T lead/lag time constant '2 shall be equal to 3 sec.
2.10.8 The measured reactor vessel t.T lag time constant '3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant '4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant '5 shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant '6 shall be less than or equal to 2 sec.
2.10.12 The f 1 (t.I) "positive" breakpoint shall be +10% t.1.
2.10.13 The f 1 (t.I) "negative" breakpoint shall be -18% L'.I.
2.10.14 The f 1 (t.I) "positive" slope shall be +3.47% / % t.1.
2.10.15 The f 1 (t.I) "negative" slope shall be -2.61 % / % t.1.
COLR BRAIDWOOD 2 Revision 6 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 2.11 Reactor Trip System (RTS) Instrumentation (LeO 3.3.1) - Overpower ~ T Setpoint Parameter Values 2.11.1 The Overpower ~T reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower ~ T reactor trip setpoint T avg rate/lag coefficient Ks shall be equal to 0.02/ of for increasing Tavg .
2.11.3 The Overpower ~T reactor trip setpoint Tavg rate/lag coefficient Ks shall be equal to 0/ of for decreasing Tavg .
2.11.4 The Overpower ~ T reactor trip setpoint T avg heatup coefficient K6 shall be equal to 0.00245/ of when T > Til.
2.11.5 The Overpower ~ T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0 / of when T:o; Til.
2.11.6 The nominal Tavg at RTP (indicated) Til shall be less than or equal to 588.0 of 2.11.7 The measured reactor vessel ~ T lead/lag time constant 1:"1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel ~T lead/lag time constant 1:"2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel ~T lag time constant 1:"3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant 1:"6 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant 1:"7 shall be equal to 10 sec.
2.11.12 The f2 (~I) "positive" breakpoint shall be 0 for all ~1.
2.11.13 The f2 (~I) "negative" breakpoint shall be 0 for all ~1.
2.11.14 The f2 (~I) "positive" slope shall be 0 for all ~1.
2.11.15 The f2 (~I) "negative" slope shall be 0 for all ~1.
COLR BRAIDWOOD 2 Revision 6 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 17 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 avg ) shall be less than or equal to 593.1 OF.
2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the value given in the Table below (LCO 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.
2.13.2 To maintain keff ~ 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action B.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the values given in the Table below.
COLR Conditions Boron Concentration Section (uum) 2.13.1 Refueling (prior to initial criticality) 1678 2.13.2 a) prior to initial criticality 1747 2.13.2 b) all other times in life 1992