ML19269D829
| ML19269D829 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 05/29/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 7906200128 | |
| Download: ML19269D829 (1) | |
Text
k'h gaa asore UNITED STATES
?g NUCLEAR REGULATORY COMMISSION
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REGloN 111 Is
g ctEn Ettvn. itusois sour NAY 2 91979 Docket No. 50-367 Northern Indiana Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 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, p. % jf;y e b
vJames G. Keppler Director
Enclosure:
IE Information Notice No. 79-13 cc w/ enc 1:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR 2253 003 NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 7 9 0 6 20 012F
s.
U.S.' NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT REGION III May 29, 1979 IE Information Notice No. 79-13 1NDICATION OF LOW WATER LEVEL IN THE OYSTER CREEK REACTOR Sum =ary 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 lov 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 minimu= collapsed water It: vel (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 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 gpm recirculation flow rate (4 pumps) 2253 004 14.8x104 12 paid core Ap Equiement Out of Service (OOSI
D" recire pump 00S due to se DUPLICATE DOCUMENT
,B startup transformer 00S f Entire document previously entered into system under:
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