BYRON 2005-0119, Cycle 13 Core Operating Limits Report
| ML052840067 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/07/2005 |
| From: | Kuczynski S Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BYRON 2005-0119 | |
| Download: ML052840067 (15) | |
Text
Fx ci Cci cC r Bc p lily, L wvvWcxclc cc rp crc ExelN ucl earflM
~yrc t it
~14ONi CC ciii B B Boil By i BulB B794 October 7, 2005 LTR: BYRON 2005-0119 File: 1.10.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455
Subject:
Byron Station Unit 2 Cycle 13 Core Operating Limits Report In accordance with Technical Specification 5.6.5, Core Operating Limits Report (COLR),
we are submitting the Unit 2 Cycle 13 COLR revision 0.
Should you have any questions concerning these reports, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.
Respectfully, Stephen E Kuczynski Site Vice President Byron Nuclear Generating Station
Attachment:
- 1) Byron Station Unit 2 Cycle 13 COLR, revision 0 SEK/JL/rah
ATTACHMENT I Byron Station Unit 2 Cycle 13 Core Operating Limits Report Revision 0
Revision 0 Page I of 13 CoRE OPERAflNG LIMITS REPORT (COLR) tor BYRON UNIT 2 CYCLE 3 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLA) for Byron 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)
LCD 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
LCD 3.2,5 Departure from Nucleate Boiling Ratio (ON BR)
LCO 3.3.1 Reactor Trip System (RTS) instrumentation LCO 3.3.9 Boron Dilution Protection System (BDPS)
LCD 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 TAM TLCO 3.1 .d Charging Pumps Operating TAM TLCO 3.1 .i Borated Water Sources Operating TAM TLCO 3.1.g Position Indication System Shutdown TAM TLCO 3.1 .h Shutdown Margin (SDM) MODE 1 and MODE 2 with keff 1.0 TAM TLCO 3.1.i Shutdown Margin (SDM) MODE 5 TAM TLCO 3.1.j Shutdown and Control Rods TAM TLCO 3.1.k Position Indication System Shutdown (Special Test Exception)
Revision 0 Page 2 of 13 CORE OPERATING LIMITS REPORT (COLR) lhr BYRON 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 (ACS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.1.1.
680 660 2250 psia L~
c71
~1) ~
2000 sia ~
~
~I640 1860 psia 620
~
600 ~__
580 ..~___J._.~_.i_...__L__ I ~i I I I I I Ii .2 .4 .6 .8 .2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits
Revision 0 Page 3 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON 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; TAM 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; TAM 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/AAO/HZP-MTC upper limit shall be +1.68 x 1 0~Ak/k/°F.
2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 1 ~*4 Ak/k/°F.
2.3.3 The EOL/AAO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10~Ak/k/CF.
2.3.4 The EOLAAOIHFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 1 0~Ak/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:
~
Revision 0 Page 4 of l3 CORE OPERATiNG LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 13 Figure 2~5.1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power 224 220 200 180 160 (100%, 161)
~14O 120
- ~ioo (0
0 0~
C
~60 40 20 0
0 10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)
Revision 0 Page 5 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE l3 2.6 Heat Flux Hot Channel Factor (F0~fl.(LCD 3.2.1) 2.6.1 Total Peaking Factor:
FRIP F0(Z) ~xK(Z) for P0.5 FRrP F0(Z) 2xK(Z) forP>0.5 where: P the ratio of THERMAL POWER to RATED THERMAL POWER F~TP= 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 FC0(z) penalty factors that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase the FWo(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, U~0,to be applied to the Heat Flux Hot Channel Factor FQ(Z) shall be calculated by the following formula U = U, . (I, 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
Re~isionI) Page fi of I 3 C()RIP OPERATING LIMITS REPORT (COLR) for BYRON UNI~I2 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 12 ,0.924) 0.9 0.8 i~:I0.7 0
4~ LOCA Limiting
~0.4 Envelope 0.3 0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 1011 12 BOTTOM Core Height (ft) TOP
Revision 0 Page 7 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 13 Table 2.6.2.a W(Z) versus Core Height (Top and Bottom 15% Excluded per WCAP-10216)
Height 150 6000 14000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0,00 (core bottom) 1.0000 1.0000 1.0000 1.0000 0.20 1.0000 1,0000 1.0000 1.0000 0.40 1.0000 1.0000 1.0000 1.0000 0.60 1.0000 1.0000 1.0000 1.0000 0.80 1.0000 1.0000 1.0000 1.0000 100 1.0000 1.0000 1.0000 i.oooo 1.20 1.0000 1.0000 1,0000 1.0000 1.40 1.0000 1.0000 1.0000 1.0000 1.60 1.0000 1,0000 1.0000 1.0000 1.80 1.2061 1.2169 1.2897 1.2720 2.00 1.2002 1.1986 1.2759 1.2600 2.20 1.1807 1.1779 1.2591 1.2434 2.40 1.1784 1.1804 1.2443 1.2277 2.60 1.1646 1.1431 1.2266 1.2091 2.80 1.1600 1.1399 1.2108 1.1915 3.00 1.1561 1.1370 1.2011 1.1780 3.20 l.l502 1.1323 1.1906 1,1770 3.40 1.1443 1.1285 1.1836 1.1750 3.60 1.1374 1,1218 1.1796 .1720 3.80 1.1315 1.1170 1.1758 1.1680 4.00 1.1269 1.1144 1.1716 1.1654 4.20 1.1243 1,1115 1.1650 1.1780 4.40 1.1221 1.1096 1.1596 1.1887 4.60 1.1186 1.1055 1.1509 1.1990 4.80 1.1152 1.1025 1.1427 1,2064 5.00 1.1116 1.0993 1.1444 1.2117 5.20 1.1062 1.0954 1.1450 1.2139 5.40 1,1016 1.0925 1.1455 1.2148 5.60 1.1043 1.0981 1.1441 1.2123 5,80 1.1129 1.1037 1.1528 1.2228 6.00 1.1228 1.1082 1.1644 1.2364 6.20 1.1405 1.1119 1.1740 1.2460 6.40 1,1562 1.1214 1,1807 1.2538 6.60 1,1700 1,1352 1.1864 1.2576 6.80 1.1827 1.1481 1.1901 1.2594 7.00 1.1935 1.1590 1.1909 1.2583 7.20 1.2024 1.1681 1.1899 1.2523 7.40 1.2093 1.1801 1.1878 1.2453 7.60 1,2123 1.1921 1.1827 1.2333 7.80 1.2153 1.2060 1.1778 1.2214 8.00 1.2154 1.2190 1.1699 1.2095 8.20 1,2106 1.2305 1.1609 1.1931 8.40 1.2115 1.2438 1.1530 1.1812 8,60 1.2148 1.2528 1.1502 1.1702 8,80 1.2162 1.2639 1.1485 1.1642 9.00 1.2200 1.2720 1.1507 1.1578 9.20 1.2230 1.2771 1.1509 1.1485 9.40 1.2270 1.2888 1.1520 1.1460 9,60 1.2320 1.3018 1.1523 1.1920 9,80 1.2450 1.3140 1,1660 1.2310 10.00 1.2610 1.3262 1.1940 1,2670 10.20 1.2860 1.3364 1,2190 1.3000 10.40 1.0000 1.0000 1.0000 1.0000 10.60 1.0000 1.0000 1.0000 1.0000 10,80 1 0000 1.0000 1.0000 1,0000 11.00 1.0000 1.0000 1.0000 1.0000 11.20 1.0000 1.0000 1.0000 1.0000 11.40 1.0000 1.0000 1.0000 1.0000 11.60 1.0000 1.0000 1,0000 1,0000 11.80 1.0000 1.0000 1,0000 1.0000 12.00 (core tOp) 1.0000 1,0000 1,0(100 1.0000 Note: W(Z) values at 20000 MWD/MTU may be applied to cycle burnups greater than 20000 MWD/MTU to prevent W(Z) tunction extrapolation
Revision I) Page 8 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 13 Table 2.6.2.b Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penal~yFactor (MWD/MTU) F o(z) 840 1.0200 1012 1.0220 1185 1.0248 1357 1.0266 1530 1.0280 _____
1702 1.0292 1875 1.0309 2047 1.0332 2220 1.0338 2392 1.0340 2565 1.0342 2737 1.0344 2910 1.0342 3082 1.0335 3255 1.0320 3427 1.0300 3600 1.0271 3772 1.0233 3945 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.
Revision 0 Page 9 of 13 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 13 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FN~H).(LCD 3.2.2) 2.7.1 F~0 F~[{1.0+ PF~H(1.0- P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FR7P 90 PF H = 0.3 4
2.7.2 Uncertainty when PDMS is inoperable The uncertainty, U~40,to be applied to the Nuclear Enthalpy Rise Hot Channel Factor F1~0shall be calculated by the following formula:
UF4H = UF8Hm where:
UFzIHm = Base F1~~ measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
F1~0Warning Setpoint 2% of Ft~HMargin FN H Alarm Setpoint 0% of FN~,HMargin 4
2.8 AXIAL FLUX DIFFERENCE (AFD) (LCD 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) (LCD 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
Revision 0 Page 10 of IS CORE OPERATING LiMITS REPORT (COLR) (or BYRON 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 -___ ___
(-1& 100) ~+10, 100) 100 1 ___ .
Unacceptat~le / Unacceptable
~ 80 Operation / . . Operation Acceptable
~ 60 OperatIon 40 (-35, 5.0) (+25, 50) 20 0.~ , ** __ __
40 20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (%)
Revision() Page II oIlS CORE OIERATING LIMITS REPORT (COLR) for BYR~NUNIT 2 CYCLE 13 2.10 Reactor Trip System (RTS) Instrumentation (LCD 3.3.1) Overtemperature AT Setpoirtt 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 T8~9coefficient K2 shall be equal to 0.0297 I °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) T shall be less than or equal to 588.0 0F.
2.10.5 The nominal RCS operating pressure (indicated) F shall be equal to 2235 psig.
2.10.6 The measured reactor vessel AT lead/lag time constant t shall be equal to 8 sec.
1 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 r4shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant r5shall be equal to 4 sec.
2.10.11 The measured reactor vessel average temperature lag time constant t6shall be less than or equal to 2 sec.
2.10.12 The f~(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%I% Al.
2.10.15 The f1 (Al) negative slope shall be -2.61% 1% Al.
Revision 0 Page 12 of 13 CORE OPERATING LIMITS REPORI (COLR) for BYRON UNiT 2 CYCLE IS 2.11 Reactor Trip System fATS) Instrumentabon (LCD 3.3.1) Overpower AT Setpoint Parameter Values 2.11.1 The Overpower AT reactor trip setpoint K4 shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint T~~rate/lag coefficient K5 shall be equal to 9
0.02 / F for increasing T5~9 2.11.3 The Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 shall be equal to 0 / F for decreasing Tav9 2.11 .4 The Overpower AT reactor trip setpoint T heatup coefficient K6 shall be equal to 4~9 0.00245 / F when T > 1.
2.11.5 The Overpower AT reactor trip setpoint T4~9heatup coefficient K6 shall be equal to 0 / F when T T.
2.11.6 The nominal Taug 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 ~2 shall be equal to 3 sec.
2.11.9 The measured reactor vessel AT lag time constant r3shall 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 t7shall be equal to 10 sec.
2.11.12 The f2(AI) positive breakpoint shall be 0 for all Al, 2.11 .13 The I2 (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 Ofor all Al.
ReViSiOfl 0 Page 13 oF 13 CORE OPERATING LIMITS REPORT (COLR) for BYRCN UNIT 2 CYCLE IS 2.12 Reactor Coolant System (ACS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCD 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.
2.12.2 The ADS average temperature (T~~shall 9) 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 (LCD 3.9.1). The reported value also bounds the end-of-cycle requirements for the previous cycle.
2.13.2 To maintain keff 5 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.
COLA Conditions Boron Concentration Section (ppm) 2.13.1 Refueling 1728 2.13.2 a) prior to initial criticality 1790 2.13.2 b) all other times in core life 1995