ML19263E589
| ML19263E589 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 05/29/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Coughlin J PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA |
| References | |
| NUDOCS 7906200136 | |
| Download: ML19263E589 (1) | |
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GLEN ELLYN ILLINOIS 60137 MAY Z 91979 Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN:
Dr. James Coughlin Vice President, Nuclear 1000 East Main Street Plainfield, IN 46168 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of this office.
Sincerely,
.h N~uuL ames G. Keppler Director
Enclosure:
IE Information Notice No. 79-13 cc w/ encl:
Mr. R. M. Brown, Construction Project Cuperintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR 2288 192 NSIC TIC LeBoeuf, Lamb, Leiby & MacRae 7906200136
U.S. ' NUCLEAR REGULATORY COMMISSION Y
OFFICE OF INSPECTION AND ENFORCEMENT,
REGION III May 29, 1979 IE Information Notice No. 79-13 INDICATION OF LOW WATER LEVEL IN THE OYSTER CREEK REACTOR Serv A loss of feedwater transient at the Oyster Creek facility on May 2, 1979, resulted in a significant reduction in water inventory within the reactor core shroud area as measured by one set of water level instruments (triple low level), while the remaining level instruments, sensing from the reactor annulus area indicated water levels above any protective feature setpoint (Figure 1).
The water level within the core shroud area was reduced below the " triple low level" setpoint of 4-feet, 8-inches above the top of the fuel.
Subsequent analysis by the licensee has determined that the minicu= collapsed water level (solid, without steam voids) over the top of the fuel was 1 to 1-1/2 feet.
Coolant sa=ple analyses and offgas release rates do not indicate any fuel damage occurred.
General Oyster Creek is a non-jet pu=p BWR with licensed power of 1930 MWt.
The plant was first made critical May 3, 1969.
Status Before Transient Operating at near full power with the main parameters at levels as follows:
1895 MWt power level 79" Yarway (13'4" over top of fuel) reactor water level 1020 psig reactor pressure 2288 193 7.1x106 f /hr feedflow 14.8x104 gpm recirculation flow rate (4 pumps) 12 psid core op e
DUPLICATE DOCUMENT "D" recire pump 00S due to se "B" startup transformer OOS f Entire document previously entered into system under:
ANO f/
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