ML19321A035
| ML19321A035 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 07/02/1980 |
| From: | Walker F TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19321A033 | List: |
| References | |
| NUDOCS 8007220360 | |
| Download: ML19321A035 (9) | |
Text
_. _ -
i O
TENNESSEE VALI2Y AUTHORITY DIVISION OF NUCLEAR P0kIR SEQUOYAH NUCLEAR PLANT f
MONTHLY OPERATING REPORT JUNE 1, 1980 - JUNE 30, 1980 4
m.
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 4
d Submitted By.' thd/
0h ILLit Plant}uperintendent I
a
.8007220360
TABLE OF CONTENTS Operations Summary.
.1 Significant Operational Events.....................
2 Average Daily Unit Power Level.....................
3 Operating Data Report
.4 Unit Shutdown and Power Reduction
.5 i
Plant Maintenance Summary
.6 Outage Maintenance Summary..........
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Operations Summary June 1980 The following sumary describes the significant operational activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.
There were twenty-five Licensee Event Reports submitted to the NRC during the month of June.
During the month, heatup to normal operating pressure and temperature i
was completed. The reactor coolant system was at 547*F and 2235 psig at the end of June.
An inadvertant SI signal occurred on 6-17-80, however, no water was injected into the core. A second inadvertant SI signal on 6-23-80 did
- inject water into the core. This SI happened when the operator opened the main steam isolation valves. A high steam flow-lo-lo Tavg signal caused the SI.
A break of an air line to a steam dump resulted in dropping reactor coolant system pressure and temperature to 2090 psig and 520*F.
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Significant Operational Events Date Event 6/17/80 An inadvertant SI signal was actuated.
No water was injected into the reactor Core.
6/21/80 RCS in Mode 4 6/22/80 RCS in Mode 3 6/23/80 An inadvertant SI signal was actuated with full safety injection.
6/24/80 RCS pressure and temperature was 2235 psig and 547 F.
6/24/80 RCS pressure and temperature dropped to 2090 psig and 520 F due to air line being broken to steam dump valve and one or more valves failing open, i
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-327 UNIT 1
DATE 7/2/80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295 MONTH June 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1MWe Net) 1 0
17 0
2 0
Is 0
3,.
0 19 0
4 0
20 0
5 0
1 0
6 0
22 0
7 0
23 0
8 0
4 0
9 0
25 0
i 10 0
26 0
.i i1 0
27 0-12' 0
0 28 13 0
29 0
14 0
30 0
15 0
0 3i 16 0
i INSTRUCTIONS
~~
On this format.!ist the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
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DOCKET NO.
50-327 DATE 7-2-80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295 OPERATING STATUS
- 1. Unit Name:
Sequoyah 1 Notes
- 2. Reporting Period:
3""* 1980
- 3. Licensed Thermal Power (MWt):
170a 4.. Nameplate Rating (Gross MWe):
1220.5
-5. Design Electrical Rating (Net MWe):
1148
- 6. Maximum Dependable Capacity (Gross MWe):
1185
- 7. Maximum Dependable Capacity (Net MWe):
1148
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
4
- 9. Power Level To Which Restricted.If Any (Net MWe):
- 10. Reasons For Restrictions. If Any.
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i This Month Yr..to.Date Cumulative
- 11.~ Hours in Reporting Period 720 2928 2928
- 12. Number Of Hours Reactor Was Critical 0
0 0
- 13. Reactor Reserve Shutdown Hours 0
0
-0.
I'4. Hours Generator On.Line 0
0 0
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- 15. Unit Reserve Shutdown flours -
0 0
0 f
- 16. Gross Thermal Energy Generated (MWH) 0 0
0 17.' Gross Electrical Energy Generated (MWH) 0 0
0
- 18. Net Electrical Energy Generated (MWH) 0 0
0 4
- 19. Unit Service Factor N/A N/A N/A
- 20. Unit Availability Factor N/A N/A N/A j
- 21. Unit Capacity Factor (Using MDC Net).
N/A -
N/A N/A.
- 22. Unit Capacity Factor (Using DER Net)-
N/A N/A N/A l
- 23. Unit Forced Outage Rate N/A N/A N/A
' 24.' Shutdowns Scheduled Over Next 6 Months (T)pc. Date, and burstion of Each):
~
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- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
' Forecast
- Achieved INITIAL CRITICALITY 7-4-80 i-clNITIA L ELECTRICITY 8-21-80 COMMERCIAL OPERATION 10-3-30
- 5% Low Power Testing License'.
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Plant Maintenance Summary 4
Staking of the component cooling heat exchanger "A" tubes was com-pleted during June. This modification was made to reduce the tube vibration.
Removable vent piping hangers were installed on safety injection pumps IA-A and IB-B per work plan number 8664.
i The oil lift system of reactor coolant pump motor #2 was repaired.
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Outage Maintenance Summary i
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l Inspected pipe hangers on safety relsted systems inside and outside I
containment in.accordance with a conformation of action letter from NRC and IE bulletin 79-14.
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