ML13266A106
| ML13266A106 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/20/2013 |
| From: | Kanavos M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW130083 | |
| Download: ML13266A106 (17) | |
Text
September 20, 2013 BW130083 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 18 The purpose of this letter is to transmit the Core Operating Limits Report (COLA) for Braidwood Unit 1 Cycle 18, in accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLA)." Braidwood Unit 1 Cycle 18 COLA, Revision 10 was implemented during Braidwood Unit 1 Refueling Outage 17 in support of Cycle 18 operation. Note that Revision 10 is the original version of the Braidwood Unit 1 Cycle 18 COLA implemented in support of Cycle 18 operation. The revision number is based on a numbering convention that continues from the previous revision of the Unit 1 COLA, i.e., Braidwood Unit 1 Cycle 17 COLA, Revision 9.
If you have any questions regarding this matter, please contact Chris VanDenburgh, Regulatory Assurance Manager, at (815} 417-2800.
Mark E. Kanavos Site Vice President Braidwood Station
Attachment:
Core Operating Limits Report (COLA) for Braidwood Unit 1 Cycle 18, Revision 10 cc: NRC Regional Administrator, Region Ill
CORE OPERATING LIMITS REPORT (COLR)
FOR BRAIDWOOD UNIT 1 CYCLE 18 EXELON TRACKING ID:
COLR BRAIDWOOD 1 REVISION 10
vVLf\. UJ:'\nll..J VV VVLJ I Revision 10 Page I of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 1 Cycle 18 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).
The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) 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 (Fa(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN t.H)
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 (TRM) 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)
Revision 10 Page 2 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 18 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.-------r---~~-------r------.------,,-----~
.2 .4 .6 .8 1* 2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
LVLK OKAIUWUUU I Revision 10 Page 3 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 18 2.2 SHUTDOWN MARGIN (SDMl 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% Llklk (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% Llklk (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:
5 2.3.1 The BOUARO/HZP-MTC upper limit shall be +1. 735 x 10* .1k/k/0 F.
4 2.3.2 The EOUARO/HFP-MTC lower limit shall be -4.6 x 10' .1k/k/°F.
2.3.3 The EOUARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 Llklk/°F.
4 2.3.4 The EOUARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10" .1k/k/°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power 2.4 Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.
2.5 Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with 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) 227 112 228 113 229 114
LULK tlKAIUWUUU I Revision 10 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 (27%. 224) (77%, 224) 220 200 y I' I
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180 c~
160 I<O%, 162)
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~ 140 I IBANKC I i/
s
~ 120 c
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v 60
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20 I 1(30%.0)VI 0 I 0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
COLR BRAIDWOOD I Revision 10 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 2.6 Heat Flux Hot Channel Factor (F~ (LCO 3.2.1) 2.6.1 Total Peaking Factor:
pRTP FQ (Z) ~ _Q_xK(Z) for P ~ 0.5 0.5 pRTP FQ(Z) ~-Q-xK(Z) forP>0.5 p
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FtTP = 2.60 K(Z) is provided in Figure 2.6.1.
Figure 2.6.1 K(Z) - Normalized F0 (Z) as a Function of Core Height 1.1 (O.C 1.0) (6.0 1.0) 1 (12.( 0.924) 0.9 """"'
0.8 N' 0.7 a
u.
-g 0.6
.~
c; e o.s z0 .....,._LOCA Limiting I
~ 0.4 Envelope j 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Core Height (ft) TOP
CULR BRAIDWOOD I Revision 10 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 18 2.6.2 W(Z} Values:
a) When the Power Distribution Monitoring System (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 ;?: 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 Fc 0 (z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). 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 burnups that are outside the range of Table 2.6.2.c.
2.6.3 Uncertainty
The uncertainty, UFa. to be applied to the Heat Flux Hot Channel Factor Fa(Z) shall be calculated by the following formula where:
Uqu =Base Fa measurement uncertainty= 1.05 when PDMS is inoperable
{Uqu is defined by PDMS when OPERABLE.)
Ue = Engineering uncertainty factor= 1.03 2.6.4 PDMS Alarms:
Fa(Z) Warning Setpoint = 2% F0 (Z) Margin Fa(Z) Alarm Setpoint = 0% Fa(Z) Margin
\..-VLI'- 01.'-AIUVVVVU Revision 10 Page 7 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT l CYCLE 18 Table 2.6.2.a Full Cycle W(Zl versus Core Height for AFD Acceptable Operation Llmts In Figure 2.8.1.a (Top and Bottom 8% Excluded per WCAP-10216)
Height 150 6000 14000 20000 (feet) MWDIMTU MWDIMTU MWDIMTU MWDIMTU 0.00 (core bottom) 1.2721 1.4091 1.4469 13790 0.20 1.2523 13757 1.4158 1.3841 0.40 12420 1 3822 1.4080 1.3518 080 12321 13497 1 3915 1.3411 080 1.2235 13208 1.3882 1.3257 1.00 12146 1.2879 1 3527 1.3190 120 1.2040 1.2701 13288 1.3090 140 1 2011 1 2566 13116 13010 160 12058 1.2388 1.2927 12890 1.80 1 2136 12233 12777 1.2790 2.00 1.2008 1 2061 12630 1.2870 220 1.1884 1 1931 12517 12500 2.40 11733 11862 1.2372 12360 2.60 11617 1.1774 1.2257 1.2180 2.60 1.1558 11695 1.2153 12010 3.00 1.1489 1.1647 12043 11848 320 1.1410 11609 1.1913 11838 3.40 11399 11571 1.1846 11818 3.60 11417 1.1516 11812 1.1800 3.80 1.1434 1.1458 1' 1780 11796 4.00 1.1440 1.1403 11736 1.1780 4.20 1.1437 1.1323 1.1678 1'1742 4.40 1.1433 1.1245 1.16113 1.1706 4.60 11417 1.1155 1.1538 1.1709 480 1.1392 U074 1.1450 1.1765 5.00 1.1357 1.0979 1.1361 11802 5.20 11317 1.1049 1.1365 1.1834 540 1.1273 1.1109 1.1387 1.1849 MO 1.1299 1.1152 1.1393 11997 5.80 11436 1.1205 1.1389 1.2163 6.00 1.1612 11250 1 '1478 1.2300 6.20 1.1768 1.1276 1.1594 1.2406 6.40 11915 1.1311 1,1690 12493 6.60 1.2043 1.1349 1.1759 12541 6.80 1.2162 1.1456 1.1818 1.2569 7.00 1.2264 1.1560 11852 12558 7.20 12336 11655 1.1857 1.2517 740 1.2409 1.1727 1.1845 12447 760 12456 1.1773 1.1805 12347 7.80 1.2493 1.1793 1.1748 12229 8.00 1.2515 1.1780 1.1702 12091 8.20 1.2505 1.1764 11633 11913 840 12438 11832 1.1586 11736 8.60 12363 1.1891 1.1556 11569 8.80 12276 11981 1.1547 1.1457 9.00 1.2182 12068 1.1538 1.1409 9 20 1.2146 12267 1.1520 1.1331 9.40 1.2124 12434 1.1492 1.1680 960 12138 1 2591 1.1590 12130 9.80 1 2167 12740 1.1920 1.2510 1000 12190 1.2879 12220 1.2850 10.20 12240 1.2997 12540 1.3170 10.40 12300 1.3014 1.2760 1.3420 10.60 12460 13050 1.2880 1.3630 10.80 12460 1 3072 1.3060 13828 11.00 1.2420 1.3009 13060 1.3966 11.20 12460 13162 1.2840 13870 11.40 1.2480 1.3392 12890 1.3790 1160 12500 13471 12720 1.3634 1180 1.2540 13561 12604 1.3563 12.00 (core top) 1.2600 1.3776 1.2511 13551 Note: W(lJ values at 20000 MIIVDIMTU may be applied to cycle bumups greater than 20000 MIIVDIMTU to prevent W(Z) functiOn extrapolation
COLR BRAIDWOOD I Revision 10 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 Table 2.6.2.b EOL.only W(Z) venue Core Height for AFO Acceptable Operation llmlla In Figure 2.8.1.b (Top and Bottom 8% Excluded per WCAP-10216)
Height 18000 20000 25486 (feet) MWOIMTU MWOIMTU MWOIMTU 0.00 (core bottom) 1.2817 1.2349 1.234g 0.20 1.2650 12259 1.2259 OAO 1.2599 1.2207 12207 0.60 1.2519 1.2181 1.2181 0.80 1.2423 1.2151 1.2151 1.00 12363 1.2115 1.2115 1.20 1.2227 1.2041 1.2041 1.40 1.2126 1.1978 1.1978 1.60 1.2032 1.1884 1.1884 1.80 1.1969 1.1804 1.1804 2.00 1.1890 1.1706 1.1706 2.20 1.1780 1.1570 1.1570 2.40 1.1672 1.1453 1.1453 2.60 1.1537 1.1307 1.1307 2.80 1.1464 1.1265 1.1265 3.00 1.1422 1.1279 1.1279 3.20 1.1368 1.1294 1.1294 3.40 1.1365 1.1299 1.1299 3.60 1.1387 1.1360 1.1350 3.80 1.1426 1.1424 1.1424 4.00 1.1448 1.1485 1.1485 4.20 Lt474 1.1553 1.1553 4.40 1.1502 1.1634 1.1634 4.60 1.1548 1.1709 1.1709 4.80 1.1599 1.1765 1.1765 5.00 1.1635 1.1802 1.1802 5.20 1.1657 1.1834 1.1834 5.40 1.1672 1.1849 1.1849 5.80 1.1755 1.1997 1.1997 5.80 1.1843 1.2163 1.2163 6.00 1.1964 1.2300 1.2300 6.20 1.2062 1.2406 1.2406 6.40 1.2179 1.2493 1.2493 6.60 1.2239 1.2541 12541 6.80 122n 1.2569 12569 700 12280 12558 1.2558 720 1.2251 1.2517 1.2517 7.40 1.2200 1.2447 1.2447 7.60 1.2119 1.2347 1.2347 7.80 1.2021 12229 1.2229 8.00 1.1921 1.2091 1.2091 8.20 1.1786 1.1913 1.1913 8.40 1.1655 1.1736 1.1736 8.60 1.1540 1.1569 1.1569 8.80 1.1483 1.1457 1.1457 9.00 1.1423 1.1409 1.1409 9.20 1.1352 1.1331 1.1331 9.40 1.1520 1.1880 1.1680 9.60 1.1811 1.2130 1.2130 9.80 1.2183 12510 1.2510 10.00 1.2518 . 1.2850 1.2850 10.20 1.2854 1.3170 1.3170 10.40 1.3107 1.3420 1.3420 10.60 1.3327 1.3630 13630 10.60 1.3459 1.3628 1.3628 1100 13572 1.3986 13986 11 20 1.3391 1.3670 13870 11.40 1.3352 1.3790 1.3790 1160 1.3169 1.3634 1 3634 11.80 13061 1.3563 1.3563 12.00 {core top) 1.2986 1.3551 1.3551 Note: W(Z) values at 20000 IVIINDIMfU may be applied to cycle bumups greater than 20000 IVIINDIMfU to preverrt W(Z) function extrapolation
CULR BRAIDWOOD I Revision 10 Page 9 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 Table 2.6.2.c Penalty Factors in Excess of 2% per 31 EFPD Cycle Bumup Penalty Factor (MWO/MTU) Fca(z) 0 1.0200 150 1.0200 323 1.0259 496 1.0382 669 1.0463 843 1.0524 1016 1.0566 1189 1.0588 1362 1.0575 1535 1.0507 1708 1.0435 2228 1.0265 2574 1.0215 2921 1.0209 3267 1.0228 3440 1.0231 3613 1.0232 3786 1.0224 4133 1.0200 25486 1.0200 Notes:
Linear interpolation is adequate for intermediate cycle burnups.
All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.
COLR BRAIDWOOD I Revision 10 Page 10 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18
- 2. 7 Nuclear Enthalpy Rise Hot Channel Factor (FN~ (LCO 3.2.2) 2.7.1 FN~ .S F~;r[1.0 + PF~H(1.0- P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)
=
~J;P 1.70 PF~ = 0.3
- 2. 7.2 Uncertainty:
The uncertainty, UF~H. to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN,~H shall be calculated by the following formula:
where:
UFJHm = =
Base FN~H measurement uncertainty 1.04 when PDMS is inoperable (UFt.Hm is defined by PDMS when OPERABLE.)
- 2. 7.3 PDMS Alarms:
FN,lH Warning Setpoint = 2% FN6 H Margin
=
FN~H Alarm Setpoint 0% FN6 H 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 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;?: 1.539 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER
2.9.2 PDMS Alarms:
=
DNBR Warning Setpoint 2% DNBR Margin
=
DNBR Alarm Setpoint 0% DNBR Margin
COLR BRAIDWOOD I Revision 10 Page II of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 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 I
(-15 100) (+10, ~00) 100
~
a::
w Unacc ~ptabli Ope ation L
I
\ Una ccepta ole 01 eratio ~
v 0 80
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- a. A ~cepta )18
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w 60 I J.
- r:
1-Q w
/I \
...~
(-3 5, 50' (+ 25, 5( ))
40 0
0~
I I
20 0 ' '
-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD I Revision 10 Page 12 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 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 120 i
i I,_ (-10, 1100) (+10 100) 100 I I
I a:; iI I, I w I .
~ UnadceptabiJ UnacceptableI
~ 80 I
- I I Operation-
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0 40
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20 0
-50 -40 -30 -20 -1 0 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (o/~
COLR BRAIDWOOD I Revision 10 Page 13 ofl5 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1)- Overtemperature ~ T Setpoint Parameter Values 2.1 0.1 The Overtemperature ~ T reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature ~ T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.
2.1 0. 3 The Overtemperature ~ T reactor trip set point pressure coefficient K3 shall be equal to 0.00181 I psi.
2.10.4 The nominal Tav0 at RTP (indicated) T' shall be less than or equal to 588.0 °F.
2.1 0.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.
2.10.6 The measured reactor vessel ~T lead/lag time constant
- 1 shall be equal to 8 sec.
- 2. 10. 7 The measured reactor vessel ~T lead/lag time constant
- 2 shall be equal to 3 sec.
2.1 0.8 The measured reactor vessel ~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.
2.1 0.10 The measured reactor vessel average temperature lead/lag time constant *s shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant *a shall be less than or equal to 2 sec.
2.10.12 The f 1 (~I) "positive" breakpoint shall be +1 0% ~1.
2.10.13 The f 1 (~I) "negative" breakpoint shall be -18% ~I.
2.10.14 The f 1 (~I) "positive" slope shall be +3.47% I% ~1.
2.10.15 The f 1 (~I) "negative" slope shall be -2.61% I% ~1.
COLR BRAIDWOOD I Revision 10 Page 14 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1)- Overpower 11T Setpoint Parameter Values 2.11.1 The Overpower LiT reactor trip setpoint ~shall be equal to 1.072.
2.11.2 The Overpower 11T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 I oF for increasing Tavg*
2.11.3 The Overpower 11T reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I oF for decreasing Tavg*
2.11.4 The Overpower LiT reactor trip setpoint Tavg heatup coefficient Ka shall be equal to 0.00245 I oF when T > T".
2.11.5 The Overpower 11T reactor trip setpoint Tavg heatup coefficient Ka shall be equal to 0 I oF when T :s;T".
2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 °F.
2.11. 7 The measured reactor vessel 11T lead/lag time constant t1 shall be equal to 8 sec.
2.11. 8 The measured reactor vessel 11T lead/lag time constant t 2 shall be equal to 3 sec.
2.11. 9 The measured reactor vessel 11T 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 (111) "positive" breakpoint shall be 0 for all 111.
2.11.13 The f2 (111) "negative" breakpoint shall be 0 for all Lll.
2.11.14 The f2 (111) "positive" slope shall be 0 for all 111.
2.11. 15 The f2 {.11) "negative" slope shall be 0 for all 111.
COLR BRAIDWOOD I Revision 10 Page 15 of 15 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT I CYCLE 18 2.12 Reactor Coolant System (RCS) Pressure, Temperature. and Flow Departure from Nucleate Boiling <DNBl Limits (LCO 3.4. 1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.
2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 °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 the applicable value given in the Table below (LCO 3.9.1). The reported "prior to initial criticality" value also bounds the end-of-cycle requirements for the previous cycle.
2.13.2 To maintain keff s 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action 8.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the applicable value given in the Table below.
COLR Conditions Boron Concentration Section (ppm) 2.13.1 a) prior to initial criticality 1715 b) for cycle burnups ~ 0 MWD/MTU 1839 and < 16000 MWD/MTU c) for cycle burnups ~ 16000 1520 MWD/MTU 2.13.2 a) prior to initial criticality 1772 b) all other times in life 2028