ML20215F043
| ML20215F043 | |
| Person / Time | |
|---|---|
| Site: | Byron |
| Issue date: | 05/31/1987 |
| From: | Querio R, Spitzer D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYRON-87-0652, BYRON-87-652, NUDOCS 8706220216 | |
| Download: ML20215F043 (14) | |
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BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT l
COMMONWEALTH EDISON COMPANY
'A NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 s
LICENSE NO. NPF-66 s
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8706220216$Oh54 PDR ADOCK PDR R
-(0625M/0062M) (2)
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Monthly Report for Byron Unit 1 A.
Summary of Operating Experience for Unit 1
-The Unit began this reporting period in Mode 5 (Cold Shutdown). On 5/6/87 the Unit entered Mode 4 (Hot Shutdown). On 5/11/87 the Unit entered Mode 3 (Hot Standby).. The Unit re-entered Mode 4 on 5/15/87 at 0804 hours0.00931 days <br />0.223 hours <br />0.00133 weeks <br />3.05922e-4 months <br />, to repair a seal in the 1A reactor coolant pump. Mode 5 was entered at 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br />.on 5/15/87. On 5/23/87 the Unit entered Mode 4.
Mode 3 was entered on 5/24/87. The reactor was taken critical at 0104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> on 5/28/87'and remained in Mode 2 (Startup) for the rest of the reporting period.
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-t-Bi -' OPERATING DATA REPORT DOCKET NO.:
050-454-UNIT: -Byron One
,DATE: 06/10/87 COMPILED BY:
D. J. Spitzer TELEPHONE:
(815)234-5441' x2023 OPERATING STATUS 1.; Reporting Period: May 1987. Gross Hours:
744 2..-
Currently. Authorized Power Level (MWt): 3411 Design Electrical' Rating: 1175 (MWe-gross)
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net):'NOT DETERMINED 3.
Power Level to Which Restricted (If Any):
4.-
Reasons for Restriction (If Any):
THIS MONTH YR TO DATE CUMULATIVE *
' 5.
.-Report Period Hrs.
744 3623 15696 6.- Rx Critical Hours 95 1152.8 10866.2.
7.
Rx Reserve Shutdown Hours 0
0
'37.8 8.
Hours Generator on Line 0
1056.8
. 10010.5 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 0 2210980 28756814
' 11. Gross Elec. Energy (MWH).
0 722844' 9647076
- 12. Net Elec. Energy (MWH)
- 15967 623993 9032894 13.-Reactor Service Factor 12.8 31.8 69.2
- 14. Reactor Availability Factor 12.8 31.8.
69.5
- 15. Unit Service Factor 0
x 29.2 63.8
- 16. Unit Availability Factor 0
29.2 63.8
- 17. Unit Capacity Factor (MDC net)
N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 0 15.4 51.4
- 19. Unit Forced Outage Hrs.
0 0
777
'20.: Unit Forced Outage Rate 0
0 7.2
- 21. Shutdowns Scheduled Over Next 6 Months:
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
06/02/87
- 23. Units in Test Status (Prior to Commercial Operation): See Unit 2 (II.B.23)
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- Note - The cumulative numbers do not reflect power generated prior to commercial service.
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(0625M/0062M) (4)
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:
050-454 UNIT: Byron One DATE:
06/10/87 COMPILED BY:
D. J. Spitzer TELEPHONE:
(815)234-5441 x2023
. MONTH: May, 1987 f
DAY AVERAGE DAILY POWER LEVEL (MWe-Net).
1
-1. -
0 MW 15.
O MW I
l 2.
O MW 16.
O MW 3.
O MW-17.
O MW 4.
O MW 18.
O MW 5.
0 MW 19.
30 MW 6.
O MW 20.
O MW i
7.
-0 MW-21.
O MW 8.
O MW
- 22. -
0 MW 9.
O MW 23.
O MW 4~
10.
O MW 24.
O MW 11.
O MW 25.
O MW 12.
O MW 26.
' 0 MW s
,y
- 13.
O MW 27.
s0 MW 14.
O MW 28.
O MW 29.
O MW 30.
O MW 31.
O MW INSTRUCTIONS On this form. list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.) In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
(0625M/0062M) (5)
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UNIQUE REFORTING REQUIRDENTS (UNIT 1) 1.
Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None 2.
Licensee generated changes to ODCM.
(Y/N)
No 3.
Indications of failed fuel.
(Y/N) 1 4
No.
(Fuel reconstituted and core reloaded) 9 i
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F.
LICENSEE EVENT REPORTS (UNIT 1)
The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, May 1 through May 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Occurrence l
Licensee Event Report Number Date Title of Occurrence 87-009-00 4-8-87 Inadvertent ESF actuation -
Cnmt Vent Isolation during testing.
87-010-00 4/19/87 Failure of both VC trains.
87-011-00 4/15/87 Valve on CO2 Storage Tank found closed.
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.II. Monthly Report for Byron Unit 3 A.
Summary of Operating Experience for Unit 2 The Unit began this reporting period in Mode 1 (power Operation) at 88% power (1050 MWe). At 2047 hours0.0237 days <br />0.569 hours <br />0.00338 weeks <br />7.788835e-4 months <br /> on 5/2/87 a rampdown to 60 MWe l
was commenced because of wide range RTD problems.
The Main Generator was tripped at 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br /> on 5/2/87.
Mode 3 (Hot Shutdown) was entered at 0133 hours0.00154 days <br />0.0369 hours <br />2.199074e-4 weeks <br />5.06065e-5 months <br /> on 5/3/87. The reactor was taken critical at 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br /> on 5/3/87. At 1433 on 5/3/87 the unit was syncronized to the grid and power was ramped to 500 MWe.
At 0055 on 5/4/87 a power.
i ramp up to 1050 MWe was commenced.
On 5/4/87 at 0645 a reactor trip occurred due to lost of the 211 instrument inverter. The reactor was taken critical at 0755 on 5/5/87 and returned to Mode 1 at 0458 on 5/5/87.
On 5/6/87 power was increased to 86%. The Unit remained in Mode 1 for the rest of the reporting period.
Nw A.
1 (0625M/0062M) (9)
B.
OPERATING DATA REPORT-DdCKETMO.:
050-455 UNIT: Byron Two DATE:
06/10/87 COMPILED BY:
D. J. Spitzer TELEPHONE:
(815)234-5441 x2023 OPERATING STATUS 1.
Reporting Period: May 1987. Gross Hours:
744 2.
Currently Authorized Power Level (MWt): 3411 Design Electrical Rating: 1175 (MWe-gross)
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net): NOT DEIERMINED 3.
Power Level to Which Restricted (If Any):
4.
Reasons for Restriction (If Any): The Unit is in Startup and Power Ascension Test Phase.
THIS MONTH YR TO DATE CUMULATIVE
- 5.
Report Period Hrs.
744 3424.4 3424.4 6.
Rx Critical Hours 710.6 2'943.5 2943.5 7.
Rx Reserve Shutdown Hours 0
0 0
8.
Hours Generator on Line 705.4 2257.2 2257.2 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 1899415 4925167 4925167
- 11. Gross Elec. Energy (MWH) 644896 1588651 1588651
- 12. Net Elec. Energy (MWH) 602359 1471654 1471654
- 13. Reactor Service Factor N/A N/A N/A
- 14. Reactor Availability Factor N/A
_N/A N/A
- 15. Unit Service Factor N/A
'N/A N/A
- 16. Unit Availability Factor N/A
'N/A N/A
- 17. Unit Capacity Factor (MDC net)
N/A N'/A N/A
- 18. Unit Capacity Factor (DER net)
N/A N/A N/A
- 19. Unit Forced Outage Hrs.
N/A N/A N/A
- 20. Unit Forced Outage Rate N/A N/A N/A
- 21. Shutdowns Scheduled Over Next 6 Months:
6/06/87
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
- 23. Units in Test Status (Prior to Commercial Operation):
(UNIT 2)
Forecast Achieved Initial Criticality 01/07/87 01/09/87 Initial Electricity 02/05/87 02/06/87 Commercial Operation 05/31/87
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
l (0625M/0062M) (1_0 )
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d Ci AVERAGE DAILY UNIT POWER LEVEL :
DOCKET NO.:
050-455.
t:
4 UNIT:. Byron Two DATE:
06/10/87 COMPILED BY:
D. J. Spitzer:
,q TELEPHONE:
(815)234-5441
]
x2023 i
MONTH: /May,.1987.
. DAY- ' AVERAGE DAILY POWER LEVEL j
(MWe-Net)'
l 1.
354 MW 16.
982 MW
.3.
74 MW' 17.
976 MW 4..
1
-5.
288 MW 19.
979 MW-1 I
6.
935 MW 20.
978 MW l
l 7.
989 MW 21.
930 MW 11 8.
774 MW 22.
382 MW 9.
403 MW 23.
735 MW 10.
951 MW
'n.
24, 964 MW 11.
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,12.
975 MW 27.
959 MW h.
g 14.
968 MW 28.
965 MW
]
i 29.
966 BG7' 30.
969 MW 31.
869 MW INSTRUCTIONS On this form list the average daily-unit power level in MWe-Net for each day.
in the reporting. month. Compute to the nearest whole megawatt. These figures will be'used'to. plot a graph for each reporting month.
Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.) In such cases the average daily unit power
. output sheet should be footnoted to explain the apparent anomaly.
(0625M/0062M) (11)
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UNZOUE REPORTING REjUIREMENTS (UNIT 2) 1.
Safety /Rolief valve operations for Unit Two.
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT NONE 2.
Licensee generated changes to ODCM.
(Y/N)
No 3.
Indications of failed fuel.
(Y/N)
No l
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(0625M/0062M) (13)
./.-
F.
LICD!SEE EVENT REPORTS (UNIT 2)
The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, submitted during the reporting period, May 1 through May 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Occurrence Licensee Event Report Number Date Title of Occurrence 87-006-00 04/27/87 Reactor Trip on Low Pressurizer Pressure.
1.
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(0625M/0062M) (14)
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June 10, 1987 LTR:
- File:
2.7.200 Director,' Office of Management Information and~ Program Control.
United States Nuclear Regulatory Commission Washington, D.C.
20555 ATTN:
Document Control Desk Gentlemen:
l Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power. Station for the period May 1 through May 31, 1987.
Very truly yours,
'y.
,jacs&d42 R. E. Querio Station Manager-Byron Nuclear Power Station
-s, s.
REQ /PHD/bb cc:
A.B.. Davis, NRO, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle 1.
T. J. Maiman i
D.L. Farrar Nuclear Fuel Services, PWR Plant Support' L. Anastasia, Station Nuclear Engineering INPO Records Center Thermal Group, Tech Staff Byron Station
- Nuclear. Group, Tech Staff Byron Station L. 01shan - USNRC D. J. Spitzer
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-(0625M/0062M) (1)
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