BYRON 2002-0100, Cycle 11 Core Operating Limits Report
| ML022800028 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/27/2002 |
| From: | Lopriore R Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.01.0700, BYRON 2002-0100 | |
| Download: ML022800028 (18) | |
Text
Exelknm.
Exelon Generation Company, LLC wwwexeloncorpcom Nuclear Byron Station 4450 North German Church Road Byron, I L 61010-9794 September 27, 2002 LTR:
BYRON 2002-0100 File:
2.01.0700 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 11 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"
we are submitting the Unit 2 Cycle 11 COLR.
Should you have any questions concerning these reports, please contact William Grundmann, Regulatory Assurance Manager, at (815) 234-5441, extension 2800.
- ctfully, d
Loprior Site Vice President Byron Nuclear Generating Station
Attachment:
- 1) Byron Station Unit 2 Cycle 11 COLR RPUJL/rah cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector-Byron Station NRC Project Manager-NRR - Byron Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
ATTACHMENT Byron Station Unit 2 Cycle 11 Core Operating Limits Report
"BY2CI I COLR, Rev. 0 Page 1 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 2 Cycle 11 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 3.1.61 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 (FN6H)
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)
_J_
"BY2C] I COLR, Rev. 0 Page 2 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 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 Safeiy Limits (SLs) (SL 2.1.1) 2.1.1 In Modes 1 and 2, the combination of Thermal Power, Reactor Coolant Systerp (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 2.11.
680 2471 psia 660 "640 E=
20
- 1.
0,*A Fraction of Nominol Power Figure 2.1.1: Reactor Core Limits I
d,
"BY2CI I COLR, Rev. 0 Page 3 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 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 SbM shall be greater than or equal to 1.3% Ak/k (LCO 3.1.1, LCO 3.3.9; TRM I
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 +2.72 x 10.5 Ak/k/°F.
2.3.2 The EOL/AROIHFP-MTC lower limit shall be -4.6 x 10-4 Ak/k/°F.
2.3.3 The EOLIARO/HFP-MTC Surveillance limit at 300 ppm shall be
-3.7 x 10.4 Ak/k/°F.
2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 Ak/k/0F.'
where: BOL stands for Beginning of Cycle Life of 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 Shutdovwn 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 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 a 113 Step overlap limit.
BY2C] I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1 I Figure 25.1 Control Bank Insertion Units Versus Percent Rated Therrrd Power (27D/,; 224)
(77r/ 224)
(100%P/q 161) 20 30 40 50 60 70 80 90 100 Relative PIw (Percent) 224 220 200 180 S160
~140 CL S120 0
- 0.
80 C
60 40 40 20 0
0 10 Page 4 of 16
CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 2.6 Heat Flux Hot Channel Factor (FfZ)} (LCO 3.2.1) 2.6.1 Total Peaking Factor:
FQ(Z) *-.5xK(Z) forP_50.5 0.5 1
FP where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F RTP= 2.60 KjZ) 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 norrhal operation W(Z) values have been determined at burnups of 150, 6000, 14000, and 20000 MWD/MTU.
Table 2.6.2 shows the FCo(z) penalty factors that are greater than 2%,per 31 Effective Full Power Days. 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.
2.6.3 Uncertainty
The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula:
UFQ = Uq,,
- U, where:
- Uqu = Base FQ 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:
FQ(Z) Warning Setpoint 2 2% of Fo(Z) Margin FQ(Z) Alarm Setpoint > 0% of Fo(Z) Margin Page 5 of 16 BY2C I I COLR, Rev. 0
BY2CI I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1I Figure 2.6.1 K(Z) - Normalized Fo(Z) as a Function of Core Height 1.1 0.9 0.8 N
0.7 a
U 0.6 E
o 0.5 Z
N S0.4 0.3 0.2 0.1 0
0 1
2 3
4 5
6 7
8 9
10 11 12 Core Height (ft)
(0.0
.1.0))
LOCA Limiting!
-L_
Envelope I
Page 6 of 16
,0.924)
BY2CI I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Byrn WUit 2 Cyde 11 Flgure2 62 o S
rncri y d
W(Z) F urncbn d 150 MVVDmI" U (UcpcndI8cBia.
15% ExducLbdper WCAP-10216)
Height F eet 000 020 040 060 0 80 100 1.20 140 16o 180 200 2.20 2A0 260 280 3aol 320 340 360 380 400 420 440 460 4 80 500 520 540 5.60 580 600 620 640 660 680 7.00 7.20 7.40 7.60 7.80 8W0 820 840 860 880 9W0 9.20 940 960 980 lOW0 1020 1040 1060 1080 1100 1120 11.40 11.60 11 80 1200 KAW W(z) 10000 10000 10000 1 0000 1 0000 1.0000 10000 1.0000
, 10¢000 1.2123
'1 1939 1.1773 11617 1.1456 1.1389 1.1378 1.1357 1.1328 1.1296 1 1322 1.1337 1.1362 1.1366 11371 1.1357 1.1344 1.1310 1.1266 1.1305 1.1361 1.1417 1.1521 1.1619 1.1707 1.1785 1 1846 1.1896 1.1942 1.1987 1.2070 1.2137 1.2174 1.2221 1.2273 1.2353 1.2455 12564 12677 1.2783 1.2816 1.2777 1.2736 10000 1 0000 1 0000 1 0000 1.0000 1.0000 1 0000 1 OO0 10000 1.05 000 2.00 4 00 6 00 8.00 CORE HEIGHT (FEET) 1000 12.00 1.35 1.30 1.25 z
C,.)
n 1.20 L.
1.15 1.10 Page 7 of 16
BY2CI I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE I I Byrcn Ur-t2 Cyde 11 Figure262 b S uTrray of W(Z) F utrdn cl 6000 MWDVMv'U (FcpcndBcttln 15% Excudedupc WCAP-10216)
Hegt Feel 000 020 040 060 080 100 120 140 1.60 180 200 220 240 2.60 280 300 3.20 3 40 360 380 400 420 440 460 480 500 5.20 540 560 580 600 620 640 660 680 7.00 7.20 7.40 7.60 7.80 800 820 840 860 880 900 920 940 960 9.80 1000 1020 1040 1060 1080 1100 11.20 11.40 1160 1180 1200 Ax W(Z) 1 0000 10000 1 0000 1 0000 1 0000 1 0000 1 0000 1 0000 1 0000 1.1998 1.1853 1.1698 1.1552 1.1400 1.1303 1.1267 1.1214 1.1161 1.1089 1.1069 1.1065 1.1041 1.1026 1.1018 1.0993 1.0965 1.0916 1 0870 1.0818 1 0855 1 0984 1.1181 1.1357 1.1516 2.1664 1.1802 1.1928 1.2058 1.2158 1.2258 1.2339 1 2409 1.2479 1 2509 1 2593 1.2676 11751 1.2833 12937 1.3056 1.3173 1.3267 1 0000 1.0000 1.0000 1 0000 1 0000 1 0000 1 0000 I 0000 I 0000 1.35 1.30 1.25 z 0 z
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BY2CI I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1I Byrcn Unit 2 Cyde 11 Figre262 c S wurnmy c W(Z) Functon ti 14000 MDMT U (rcpcndBcftrT 15% ExducldP WCAP-10210)
Heght Feet 000 020 040 0160 080 100 1.20 1 An 1.80 2W0 2.20 240 260 280 300 320 340 360 380 400 420 440 460 480 5W0 520 540 560 580 600 6.20 6.4O 6.60 680 7.00 7.20 7AO 760 780 800 820 840 860 8 80 900 920 940 960 9.80 1000 1020 1040 1060 1080 1100 11.20 1140 11.60 11.80 1200 MAX W(7) 1 0000 1.0000 1.0000 1 0000 10000 10000 10000 1.9000 1 60000 1.2610 1.2520 1.2400 1.2298 12204 1.2133 1.2047 1.1943 1 1845 1.1722 11668 1 1639 1 1583 1.1534 1.1470 1.1396 1.1319 1.1225 1.1248 1.1274 1.1290 1.1296 1.1272 1.1248 1.1197 1.1145 1.1176 1 1236 1 1305 1 1346 11386 1.1417 1.1429
.1.1430 1.1443 1.1464 1.1475 1.1515 11566 1.1643 1.1700 1.1755 12002 10000 1.0000 10000 I.OO0 1.0000 1.0000 1.0000 1.0000 1.0000 1.35 1.30 1.25 0
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z : 1.20 LL 1.15 1.10 0.00 2.00 4.00 600 800 10.00 12.00 CORE HEIGHT (FEET) 1144---
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Page 10 of 16 "BY2CI I COLR, Rev. 0 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 ByrcnUnt2 Cyde 11 Fig.ie 2 6 2.d Surrnay c W(Z) F unrti ct 20000 MWDiMI" U (I cp*-)dBcttcm 15% Exducbdper WCAP-10216)
He~gN Feet 000 0 20
",040 060 080 100 120 1.40 160 180 200 2.20 2.40 2.60 280 300 320
'340 360 380 400 420 440 460 480 500 520 540 560 580 600 620 6.40 660 680 7.00 720 7.40 760 7.80 800 820 840 860 880 9.00 9.20 9.40 960 9.80 1000 1020 1040 1060 1080 1100 11 20 1140 11.60 1180 1200 MAX WZ) 10000 1.0000 10000 10000 10000 10000 1.0000 10000 1.0000 1.*735 12630 1*487 1.23352 1.2171 1.2027 11874 1.1715 1.1703 1.1686 1.1669 1.1637 1.1611 1.1651 1.1742 1.18 14 1.1857 1.1898 1 1933 1.1939 1.1925 1 1890 1 1826 1.1787 1 1875 1.1938 1.1991 11019 1.2027 1.2007 1.1981 1 1936 1.1848 1.1 777 1.1674 1.1570 1.1494 1.1467 1.1478 1.1690 1.2070 1.2410 1.2710 10000 1.0000 10000 1.0000 1 0000 1 0000 1 0000 1 0000 1 0000
.2
- 1 0.00 2.00 4 00 6.00 8.00 1000 12.00 CORE HEIGHT (FEET) 1.35 1.30 1.25 C,.)
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BY2CI I COLR, Rev. 0 Page 11 of16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 1 Table 2.6.2 Penalty Factors in Excess of 2% per 31 EFPD Cycle Burnup Penalty Factor -F e(z)
(MWDIMTU)
(%)
322 2.00 493 2.55 665 2.74 837 2.76 1008 2.74 1866 2.58 2210 2.58 2896 2.74 3068 2.75 3239 2.72 3411 2.65 3754 2.30 4097 2.00 11821 2.00 11992 2.11 12335 2.84 12507 2.89 12679 2.87 12850 2.71 13537 2.00 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 Surveillinice Requirements.
BY2CI I COLR, Rev. 0 Page 12 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNA* (LCO 3.2.2) 2.7.1 FNMH < FRTP H [1.0 + PFH(t.0 - P)]
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FRTPAH = 1.70 PFNH = 0.3 2.7.2 Uncertainty when PDMS is inoperable The uncertainty, UFaH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNH shall be calculated by the following formula:
UFH -- UFAHm where:
UF,,Hm = Base FNH measurement uncertainty = 1.04 2.7.3 PDMS Alarms:
FNAH Warning Setpoint Ž_ 2% of FNmH Margin FNH Alarm Setpoint 2 0% of FN,,H Margin
.3 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 Boiin i Ratio (DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL -I 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 Ž- 0% of DNBR Margin
BY2CI I COLR, Rev. 0 Page 13 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II Figure 2.8.! Axial Flux Difference Limits as a Function of Rated Thermal Power Axal Fux Difference Units with PI',S Inoperable 120.
0 6,
V 40 "0 20 40 20 -10 0 10 20 30 40 50 AIIAL MM
.(UX OFFJ E
(0/4
BY2CI 1 COLR, Rev. 0 Page 14 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 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 Ta,,g coefficient K2 shall be equal to 0.0297 / OF.
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 OF.
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 "c 1 shall be equal to 8 sec.
2.10.7 The measured reactor vessel AT lead/lag lime constant'"2 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 "r4 shall be equal to 33 sec.
2.10.10 The measured reactor vessel average temperature lead/lag time constant 'r 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 f1 (Al) "positive" breakpoint shall be +10% Al.
2.10.13 The f, (Al) "negative" breakpoint shall be -18% Al.
2.10.14 The fI (Al) "positive" slope shall be +3.47% /% Al.
2.10.15 The f, (Al) "negative" slope shall be -2.61% 1% Al.
"BY2CI I COLR, Rev. 0
.Page 15 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE 11 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower AT Setpoirt Paramejer. Values 2.11.1 The Overpower AT reactor trip selpoint K, shall be equal to 1.072.
2.11.2 The Overpower AT reactor trip setpoint Ta.g rate/lag coefficient K5 shall be equal to 0.02 / OF for increasing T.v,.
2.11.3 The Overpower AT reactor trip setpoint Taro rate/lag coefficient K5 shall be equal 0 /P.F for decreasing Ta,g.
2.11.4 Tile' Overpower AT reactor trip setpoint T.,, heatup coefficient K6 shall be equal
.to 0.00245 1 "F when T > T1".
2.11.5 The Overpower AT reactor trip setpoint Ta,, heatup coefficient K6 shall be equal to.0 / OF when T <TP".
2.11.6 The nominal Ta,, at RTP (indicated) To shall be less than or equal to 588.0 OF.
2.11.7 The measured reactor vessel AT lead/lag time constant -E, 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 ' 3 shall be less than or equal S3to 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 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.
"BY2C I I COLR, Rev. 0 Page 16 of 16 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 2 CYCLE II 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boilinq (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 (T2,) 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 380,900 gpm.
2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to 1753 ppm (LCO 3.9.1).
2.13.2 The Reactor Coolant System boron concentration, with all shutdown and control rods fully withdrawn, shall be greater than or equal to 1803 ppm prior to initial criticality of Cycle 11, or greater than or equal to 2048 ppm at all other times in core life, to maintain adequate shutdown margin for MODES 3, 4, and 5 during performance of rod drop time measurements and during the surveillance of Digital Rod Position Indication (DRPI) for OPERABILITY (TRM TLCOs 3.1.g and 3.1.k).
in