ML19269D828
| ML19269D828 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/29/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 7906200125 | |
| Download: ML19269D828 (1) | |
Text
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NAY 2 91979 Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:
Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 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,
. Ke 1er Director
Enclosure:
IE Information Notice No. 79-13 cc w/ enc 1:
Central Files Director, NRR/DPM Director, NRR/ DOR 2252 "159 PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 79062,001 6
N-U.S. TUCLEAR REGUi.ATORY COMMISSION 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 Su:::=a ry 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 minimum collapsed water level (solid, without steam voids) over the top of the fuel was 1 to 1-1/2 feet.
Coolant sample analyses and offgas release rates do not indicate any fuel damage occurred.
General Oyster Creek is a non-jet pump 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 7.1x106 f/hr feedflow 14.8x104 gpm recirculation flow rate (4 pumps) 2252 360 12 psid core op Equiement Out of Servie "D" recire pump 00S due to se DUPLICATE DOCUMENT "B" startup transformer 00S f Entire docunient previously entered into system under:
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