ML20215E270
| ML20215E270 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/31/1987 |
| From: | Dilworth S, Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| SL-2615, NUDOCS 8706190313 | |
| Download: ML20215E270 (7) | |
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.f ATTAC MENT A - Cause/B - Corrective Action to Prevent Reoccurrence April - #7 and #1 A.
The root cause of both of these reactor trips was a. faulty bistable circuit board on the process protection rack (7300 panel ).
The faulty board caused OPAT and OTAT Bistables trips.
l B.
The' faulty bistable circuit board was replaced and the entire channel of the process control system was retested to confirm operability.
- 2 A.
The. root cause of this trip was procedural inadequacy in that a l
test procedure did not provide adequate direction concerning operation of the turbine generator controller during the test.
Because of an over shoot to 82 percent in reactor power the main feedwater pump-operating in automatic could not maintain steam generator-water level and resulted in a Reactor Trip on low low level.
8.
Startup Test Procedure 1-6SC-02 " Load Swing Test" was clarified to contain specific guidance on how the turbine generator load q
limit set potentiometer was to be adjusted.
J
- 3 A.
Root cause of the trip was an inadequacy in work instructions for' performing maintenance on MSIV's while operating at power.
The loop 1 MSIV was improperly blocked open and slammed shut causing steam generator #1 to reach the low low level setpoint.
1 B.
Guidelines describing proper methods to maintain valve position while performing maintenance on main steam isolation valves (MSIVs), (FWIVs) and (ARVs) have been established and provided to Work Planning and Maintenance Engineering for reference.
- 4 A.
The cause of this trip was operator error.
A non-safety related manual isolation valve in the #3 bypass feedwater regulating i
1 valve piping was left closed.
B.
The unit Operating Procedure was changed to include an 4
independent verification of important feedwater valves.
E-3a
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~.p AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-424 UNIT NO.
Vogtle 1 DATE 6-12-87 COMPLETED'BY S. C. Dilworth TELEPHONE.
(404) 724-8114 MONTH May 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
.(MWe-Net)
(MWe-Net) g 541 17 2 775 18 3 778 19 6 373 20 '5 21
-o-6 149 22
-o-j 7
788 23
_n_
8 790-24
_n_
9 66 25 750 10 265 26 inst 11 770 27 11n7
. 12 791-28 1116
- 13 79 29 1136 30 1120 14 15 31 1124 16 E-4
ay
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' Georgia Power Company J 333 Piedmont Avenue l Atlanta, Georgia 30308 1
Telephone 404 5266526 Mading Address:
Fbst Office Box 4545.
Atlanta, Georgia 30302 L'
Georgia Poiver C T. Gucwa tre southern electic system
' Manager Nuclear Safety
- and Licensing SL-2615 0080m X7GJ17-V510 1
i June 15, 1987
']
.q Director, Office 'of Resource Management E
U.. S. Nuclear Regulatory Commission l
?.
Washington, D.C. -20555' PLANT V0GTLE - UNIT 1 I
NRC DOCKET 50-424 OPERATING LICENSE NPF-68 MONTHLY OPERATING REPORT l
~Gentiemen:
i Enclosed is the Monthly Operating. Report for Plant Vogtle Unit 1 for
]
.May, 1987.
This report is submitted ' pursuant to the requirements of j
Technical Specification Section 6.8.1.5.-
Sincerely, j
p t. T. Gucwa JAE/im
Enclosure:
l.
Operating Data Report 2.
Unit Shutdowns and Power Reductions 3.
Average Daily Unit Power Level c:
(see next page)
+d
)\\
f GeorgiaPower d U. S. Nuclear Regulatory Commission June 15, 1987 Page Two c: Georgia Power ComDany i
Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico Mr. C. H. Hayes G0-NORMS Southern Comoany Services Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridae Mr. B. H. Churchill, Attorney-at-Law Troutman. Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law U. S. Nuclear Regulatory Commission l
Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle NRC Document Control Desk Georaians Aaainst Nuclear Eneray Mr. D. Feig Ms. C. Stangler i
i I
0080m i
l 700776
.