ML063120309
| ML063120309 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/08/2006 |
| From: | Coutu T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BW060098 | |
| Download: ML063120309 (29) | |
Text
________ _____ Exel_n.
Exelon Generation Company, LLC www~exe1oncorp.com N uc]
B aidwood Station 5 C ~t 53~ 84 November 8, 2006 BW060098 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Core Operating Limits Report, Braidwood Unit 2 Cycle 13 The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for Braidwood Unit 2 Cycle 13, in accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR). Braidwood Unit 2 Cycle 13 COLA, Revision 1 was implemented during Braidwood Unit 2 Refueling Outage 12 in support of Cycle 13 operation. Subsequently a suspect leaking fuel assembly was identified that necessitated a core redesign. In support of the Braidwood Unit 2 Cycle 13 redesign, Braidwood Unit 2 Cycle 13 COLA, Revision 2 was implemented shortly thereafter. Attached are Revision 1 and Revision 2 of the Braidwood Unit 2 Cycle 13 COLR.
If you have any questions regarding this matter, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.
Sincerely, Thomas Coutu Site Vice President Braidwood Station Attachments: Core Operating Limits Report, Braidwood Unit 2 Cycle 13, Revision 1 Core Operating Limits Report, Braidwood Unit 2 Cycle 13, Revision 2
ATTACHMENT 1 Core Operating Limits Report Braidwood Unit 2 Cycle 13 Revision 1
COLR BRAIDWOOD 2 Revision 1 Page 1 ofl3 CORE OPERATING LIMiTS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 13 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 (SL5)
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 (F0(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F~H)
LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCO 3.2.5 Departurefrom 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 ILCO 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 I and MODE 2 with keff 1.0 TRM TLCO 3.1.1 Shutdown Margin (SOM) 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 1 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 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 s~_____
2250 psia .--~
U-
~
640 ._~
2000ps1*
.~
1860 ps~
620
~\
600 ~
580 I I I I I I I I I I I I I_~ I I I I ~I 0 .2 .4 .6 .8 .2 Fraction of Nominal Power Figure2.1.1: Reactor Core Limits
COLR BRAIDWOOD 2 Revision 1 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.2 SHUTDOWN MARGIN (SOM)
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 (LCO5 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% L~k/k(LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +0.963 x 10~L~k/k/°F, 2.3.2 The EOLJARO/HFP-MTC lower limit shall be -4.6 x 10~L,~k/k/°F.
2,3.3 The EOLJARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 1O~~k/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10~~kfkf°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 0. 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 1 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Figure 2.5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 220 200 180
~160 161)
(100~/~,
~~120 C
0
~100 0
a-C to
&60 40 20 0
0 10 20 30 40 50 60 70 80 90100 Relative Power (Percent)
COLR BRAIDWOOD 2 Revision I Page 5 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.6 Heat Flux Hot Channel Factor (F~j~fl (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FRIP FQ(Z) 2-xK(Z) forP 0.5 F RIP F0(Z) 2--xK(Z) forP>0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~T~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 Table 2.6.2.a.
The normal operation W(Z) values have been determined at bumups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2.b shows the F%(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FW0(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.b.
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula Up,, = U,,
- U~
where:
Uqu = Base F0 measurement uncertainty 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE.)
U = Engineering uncertainty factor = 1.03 0
2.6.4 PDMS Alarms:
F0(Z) Warning Setpoint 2% of F0(Z) Margin F0(Z) Alarm Setpoint 0% of F0(Z) Margin
COLR BRAIDWOOD 2 Revision 1 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 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) 1
~
. 0.924) 0.9 0.8
~ 0.7 a
~0.6 gO.5 4 LOCA Limiting
~0.4 Envelope 0.3 a .. a a. ..... a 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 101112 BOTTOM Core Height (ft) TOP
COLR BRAIDWOOD 2 Revision I Page 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Table 2.6.2.a W(Z) versus Core Height (Top and Bottom 8% Excluded per WCAP-1 0216)
Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTIJ MWDIMTU MWD/MTU 000 (core bottom) 1.2513 1.3489 1,4300 13492 020 12374 13208 1.4000 1.3361 0.40 1.2309 1.3128 1.3870 1.3316 0.60 1.2274 1.3173 1.3730 1.3298 0.80 1.2165 1.2937 1.3660 1.3249 1.00 1.2079 1.2781 1.3630 1.3222 1,20 1.1959 1.2595 1.3500 1.3123 1.40 1.1844 1.2414 1.3340 1.3059 1.60 1.1741 1.2244 1.3166 1.2903 1.80 1.1662 1.2108 1.3000 1.2792 2.00 1.1543 1.1962 1.2830 1.2662 2.20 1.1420 1.1787 1.2640 1.2498 2.40 1.1316 1.1636 1.2460 1.2346 2.60 1.1220 1.1465 1.2301 1.2160 2.80 1.1179 1.1314 1.2189 1.1983 300 1.1161 1.1220 1.2067 1.1805 3.20 1,1142 1.1209 1.1924 1.1621 3.40 1.1131 1.1208 1.1792 1.1610 3.60 1.1058 1.1201 1.1679 1.1598 3.80 1.1016 1.1195 1.1620 1.1609 4.00 1.1086 1.1181 1.1560 1.161~
4.20 1.1092 1.1162 1.1471 1.1604 4.40 1.1090 1.1134 1.1409 1.1605 4.60 1,1080 1.1102 1.1318 1.1685 4.80 1.1068 1.1065 1.1237 1.1746 5.00 1.1055 1.1026 1.1154 1.1785 5.20 1.1028 1.0972 1.1168 1.181~
5.40 1,1103 1.0923 1,1179 1.1826 5.60 1.1187 1.0895 11189 1.1933 5.80 1.1286 1,0971 1.1358 1.2108 6.00 1.1463 1.1027 1.1514 1.2262 6.20 1.1620 1.1156 1.1660 1.2378 6,40 1.1758 1.1332 1.1767 1.2474 6.60 1.1884 1.1500 1.1854 1.2531 6.80 1,1993 1.1658 1.1931 1.2568 7.00 1.2091 1.1806 1.1989 1.2576 7.20 1.2198 1.1934 1 2007 1.2545 7.40 1.2247 1.2044 1.2025 1.2495 7,60 1.2257 1.2143 1.2005 1.2405 7.80 1.2268 1 2233 1.1984 1.2308 8.00 1.2303 1.2321 1.1944 1.2177 8.20 1.2302 1.2403 1.1884 1.1989 8.40 1.2296 12483 1.1825 1.1822 8.60 1.2159 1.2544 1.1736 1,1759 8.80 1.2171 1.2604 1.1648 1,1707 9.00 1.2248 12857 1.1619 1.1666 9.20 1,2398 1.2784 1,1619 1.1630 9.40 1.2527 1.2907 1.1676 1.1629 9.60 1.2840 1.3033 1.1735 1.1775 9.80 1.2708 1.3147 1.1783 1.2161 10.00 1.2710 1.3263 1.1842 1.2517 10.20 1.2820 1.3442 1.2109 1.2884 10.40 1.2930 1.3609 1.2326 1.3191 10.60 1.2910 1.3672 1.2494 1.3408 10.80 1.2980 1.3720 1.2642 1.3596 11.00 1.3062 1.3479 1.2759 1.3734 11.20 1.3201 1.3393 1.2538 1.3723 11.40 1.3280 1.3524 1.2457 1.3622 11.60 1.3281 1.3570 1.2376 1.3501 11.80 1.3310 1.3562 1.2246 1.3391 12.00 (core top) 1.3362 1.3656 1.2125 1.3299 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle bumups greater than 20000 MWD/MTU to prevent W(Z) function extrapolation
COLR BRAID WOOD 2 Revision 1 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Table 2.6.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penal~Factor (MWD/MTU) F ~(Z) 150 1.0200 323 1.0213 495 1.0286 668 1.0353 840 1.0413 1013 1.0467 1185 1.0513 1358 1.0551 1531 1.0532 1703 1.0478 1876 1.0419 2048 1.0359 2221 1.0301 2393 1.0248 2566 1.0201 2739 1.0200 Notes:
Linear interpolation is adequate for intermediate cycle burnups.
All cycle bumups 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 1 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN~(LCO 3.2.2) 2.7.1 F~H F~[1,0+ PF,~H(1.0 P)J -
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER
~RTP PFAH = 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 F~Hshall be calculated by the following formula:
UF~H= UF,~,Hm where:
UFJHm = Base F~Hmeasurement uncertainty = 1.04 2.7,3 PDMS Alarms:
F~HWarning Setpoint 2% of F~HMargin F~HAlarm Setpoint 0% of F~HMargin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFO Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9,1 DNBRAPSL 1.536 The Axial Power Shape Limiting DNBR (DNBR~51)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
COLR BRAIDWOOD 2 Revision 1 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits with PDMS Inoperable 120 100 LU 0 80 a.
-J LU I 60 I-0 Ui I-40 20 0
40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRAIDWOOD 2 Revision 1 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAID WOOD UNIT 2 CYCLE 13 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10.1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / °F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal Ta~atRTP (indicated) 1 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 t1 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 14 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant t~shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant 16 shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) positive breakpoint shall be +10% Al.
2.10.13 The f1 (Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive slope shall be +3.47% 1% Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% 1% Al.
COLR BRAIDWOOD 2 Revision 1 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.11 Reactor Trip System (RTS) lnstrumentaii~n(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 Tavg rate/lag coefficient K5 shall be equal to 0.02 / °Ffor increasing Tavg, 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 I °Ffor decreasing Tavg 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / ~Fwhen T > T.
2.11.5 The Overpower AT reactor trip setpoint Ta~ heatup coefficient K6 shall be equal to 0/ °Fwhen T 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 AT lead/lag time constant r1 shall be equal to 8 sec.
2.11.8 The measured reactor vessel AT lead/lag time constant 12 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant 13 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant 16 shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant t~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(M) positive slope shall be 0 for all Al.
2.11.15 The f2 (Al) negative slope shall be 0 for all Al.
COLR BRAIDWOOD 2 Revision I Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNiT 2 CYCLE 13 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 psi9.
2.12.2 The RCS average temperature (Ta~)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 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 IRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shaD be greater than or equal to the values given in the Table below.
COLR Conditions Boron Section Concentration (ppm) 2.13.1 Refueling 1747 2.13.2 a) prior to initial criticality 1821 2.13.2 b) all other times in core life 1989
ATFACHMENT 1 Core Operating Limits Report Braidwood Unit 2 Cycle 13 Revision 2
COLR BRAID WOOD 2 Revision 2 Page 1 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Braidwood Station Unit 2 Cycle 13 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 (F0(Z))
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F~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 (BDPS)
LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual affected by this report are listed below:
TRM TLCO 3.1 .b Boration Flow Paths Operating TRM TLCO 3.1 .d Charging Pumps Operating TRM TLCO 3.1 .f Borated Water Sources Operating TRM TLCO 3.1.g Position Indication System Shutdown TRM TLCO 3.1.h Shutdown Margin (SDM) MODE 1 and MODE 2 with keff 1.0 TRM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TRM TLCO 3.1.j Shutdown and Control Rods TRM TLCO 3.1 .k Position Indication System Shutdown (Special Test Exception)
COLR BRAIDWOOD 2 Revision 2 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 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 (SL5I (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 ,s~_____
2250 psia .--.
V ~
a, ._~
2000psia U .~
E 620 600 ._
580 I I I I I I I I I I t I I I I 0 .2 .4 .6 .8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
COLR BRAIDWOOD 2 Revision 2 Page 3 of 13 CORE OPERATING LiMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.2 SHUTDOWN MARGIN (SDM)
The SDM limit for MODES 1, 2, 3, and 4 is:
2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).
The SDM limit for MODE 5 is:
2.2.2 SDM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).
2.3 Moderator Temperature Coefficient (MTC) (LCO 3.1.3)
The Moderator Temperature Coefficient (MTC) limits are:
2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +0.963 x 10~AkIkI°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x ~ Ak/k/°F.
2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10~AkIk/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10~Ak/kI°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 2 Page 4 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Figure 2.5.1:
Control Bank Insertion Umits Versus Percent Rated Thermal Power 224 (27%, 224) (77%, 224) 220 200 180 j160 (100%, 161) 140 120 0
~100 0
a.
C 80 0 60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 RelatIve Power (Percent)
COLR BRAIDWOOD 2 Revision 2 Page 5 of 13 CORE OPERATiNG LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.6 Heat Flux Hot Channel Factor (FQ(Zfl (LCO 3.2.1) 2.6.1 Total Peaking Factor:
F RTP FQ(Z) 9---xK(Z) forP 0.5 F RTP FQ(Z) 9--xK(Z) forP>O.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F~T~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 Table 2.6.2.a.
The normal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2.b shows the FCa(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWQ(z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.b.
2.6.3 Uncertainty
The uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor F0(Z) shall be calculated by the following formula UFQ = Uq~* Ue where:
Uqu = Base F0 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:
F0(Z) Warning Setpoint 2% of F0(Z) Margin F0(Z) Alarm Setpoint 0% of F0(Z) Margin
COLR BRAIDWOOD 2 Revision 2 Page 6 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAID WOOD UNIT 2 CYCLE 13 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) 1 - --~
~ ~ 12k 0.924)
~ ~
0.9 0.8 i;:i~ 0.7 a
~0.6
~o0.5
~$~LOCA Limiting
~0.4 Envelope 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 101112 BOTTOM Core Height (ft) TOP
COLR BRAIDWOOD 2 Revision 2 Page 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Table 2.6.2.a W(Z> versus core Height (Top and Bottom 8% Excluded per WCAP-10216)
Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 000 (core bottom) 12521 13301 14450 13480 0.20 1.2373 1.3037 1.4150 1.3376 0.40 1.2309 1.2922 1.4020 1.3338 0.60 1.2252 1.2937 1.3890 1.3329 0.80 .2140 1.2757 1.3710 1.3284
.00 .2049 1.2612 1.3670 1.3228
.20 .1918 1.2417 1.3580 1.3134
.40 .1807 1.2257 ~1.3430 1.3059 1.60 .1659 1.2077 1,3240 1.2935 1.80 .1504 1.1927 1.3080 1.2821
~.00 1.1361 1.1797 1.2920 1.2696 2.20 1.1330 1.1637 1.2730 1.2545 2.40 1.1307 1.1507 1.2560 1.2401 2.60 1.1267 1.1357 1.2350 1.2220 2.80 .1229 1.1283 1.2205 1.2048 3.00 .1196 1.1248 1.2089 1.1903 3.20 .1148 1.1187 1.1949 1.1729 3.40 .1100 1.1171 1.1813 1.1683 3.60 .1117 1.1150 1.1718 1.1682 3.80 .1156 1.1144 1.1672 1.1677 4.00 .1184 1.1140 1.1642 1.1654 4.20 1.1160 1.1116 ~1.1601 1.1633 4.40 .1178 1.1092 1.1554 1.1645 4.60 .1183 1.1067 1.1493 1.1725 4.80 .1182 1.1033 1.1427 1.1774 5.00 .1170 1.1007 1.1364 1.1805 5.20 .1199 1.0953 1.1395 1.1832 5.40 .1283 1.0918 1.1407 1.1855 5.60 .1346 1.0892 1.1419 1.1992 5.80 .1399 1.0958 1.1415 1.2157 6.00 .1473 1.1014 1.1515 1.2282 6.20 .1628 1.1163 1.1651 1.2399 6.40 .1756 1.1340 1.1757 1.2476 6.60 .1874 1.1498 1.1834 1.2534 6.80 .1981 1.1655 1.1901 1.2562 7.00 .2069 1.1784 1.1949 1.2569 7.20 .2158 1.1903 1.1967 1.2509 7.40 .2239 1.1993 1.1975 1.2448 7.60 .2275 1.2063 1.1955 1.2338 7.80 .2319 1.2123 1.1924 1.2219 8.00 .2329 1.2203 1.1884 1.2081 8.20 .2304 1.2293 1,1814 1.1893 8.40 .2279 1.2382 1.1745 1.1735 8.60 .2206 1.2432 1.1646 1.1585 8.80 .2152 1.2534 1.1558 1.1584 9.00 .2241 1.2701 1.1552 1.1596 9.20 .2253 1.2853 1.1613 1 .1605 9.40 .2382 1.2996 1.1670 1 .1634 9.60 1.2449 1.3129 1,1725 I .1784 9.80 1.2505 1.3273 1,1765 1 .2170 10.00 1.2572 1.3438 1.1870 I .2536 10.20 1.2636 .3570 1.2117 1 .2893 10.40 1.2715 .3680 1.2334 I .3209 10.60 1.2733 .3717 1.2502 1 .3438 10.80 .2879 .3788 1.2650 I .3625 11.00 .3062 1.3575 1.2767 1 .3763 11.20 .3273 1.3608 1.2537 I .3762 11.40 .3393 1.3753 1.2446 I .3651 11.60 .3325 1.3818 1.2355 1 .3541 11.80 1.3303 1.3822 1.2235 I .3430 12.00 (core top) 1.3348 1.3930 1.2123 I .3329 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWDIMTU to prevent W(Z) function extrapolation
COLR BRAIDWOOD 2 Revision 2 Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Table 2.6.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup PenaI~tFactor (MWD/MTU) F Q(Z) 0 1.0244 150 1.0244 323 1.0310 495 1.0375 668 1.0435 840 1.0488 1013 1.0536 1185 1.0547 1358 1.0521 1531 1.0483 1703 1.0435 1876 1,0380 2048 1.0322 2221 1.0265 2393 1.0213 2566 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 2 Page 9 of 13 CORE OPERATING LiMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor (Ft~jj(LCO 3.2.2) 2.7.1 F~H F~[1,0 + PF~H(1.0 P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER RTP rAH 1~
PF~H= 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 F~Hshall be calculated by the following formula:
UF~H= UF~Hm where:
UF,4Hm = Base Ft~AHmeasurement uncertainty = 1.04 2.7.3 PDMS Alarms:
F~H Warning Setpoint 2% of F~HMargin FNSH Alarm Setpoint 0% of F~HMargin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.8.1 When PDMS is inoperable, the AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in Figure 2.8.1 or the latest valid PDMS Surveillance Report, whichever is more conservative.
2.8.2 When PDMS is OPERABLE, no AFD Acceptable Operation Limits are applicable.
2.9 Departure from Nucleate Boiling Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL 1.536 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER 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
COLR BRAIDWOOD 2 Revision 2 Page 10 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 Figure 2.8.1 Axial Flux Difference Limits as a Function of Rated Thermal Power Axial Flux Difference Limits w ith PDMS Inoperable 120 100 w
0 a- 80
-j 2
Ui I 60 I-Ui I-40 20 0
40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
COLR BRA1DWOOD 2 Revision 2 Page 11 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overtemperature AT Setpoint Parameter Values 2.10,1 The Overtemperature AT reactor trip setpoint K1 shall be equal to 1.325.
2.10.2 The Overtemperature AT reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 / °F.
2.10.3 The Overtemperature AT reactor trip setpoint pressure coefficient K3 shall be equal to 0.00181 / psi.
2.10.4 The nominal Tavg at RTP (indicated) T 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 r1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag time constant t2shall be equal to 3 sec.
2.10.8 The measured reactor vessel AT lag time constant r3 shall be less than or equal to 2 sec.
2.10.9 The measured reactor vessel average temperature lead/lag time constant t4shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant t5shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant z6 shall be less than or equal to 2 sec.
2.10.12 The f1 (Al) positive breakpoint shall be +10% Al.
2.10.13 The f1 (Al) negative breakpoint shall be -18% Al.
2.10.14 The f1 (Al) positive slope shall be +3.47% / % Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% 1% Al.
COLR BRAIDWOOD 2 Revision 2 Page 12 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0.02 / F for increasing Tavg, 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / F for decreasing Tavg, 2.11.4 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 / F when T > T.
2.11.5 The Overpower AT reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0/ F when T 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 AT lead/lag time constant r1 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 t3 shall be less than or equal to 2 sec.
2.11.10 The measured reactor vessel average temperature lag time constant t6shall be less than or equal to 2 sec.
2.11.11 The measured reactor vessel average temperature rate/lag time constant ~ 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.
COLR BRAIDWOOD 2 Revision 2 Page 13 of 13 CORE OPERATING LIMITS REPORT (COLR) for BRAIDWOOD UNIT 2 CYCLE 13 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 (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 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 8.2 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 Section Concentration (ppm) 2.13.1 Refueling 1737 2.13.2 a) prior to initial criticality 1811 2.13.2 b) all other times in core life 1979