ML19263E568
| ML19263E568 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/29/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 7906200101 | |
| Download: ML19263E568 (1) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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MAY 2 91979 Docket No. 50-440 Docket No. 50-441 The Cleveland Electric Illuminating Company ATTN:
Mr. Dalwyn R. Davidson Vice President - Engineering P. O. Box 5000 Cleveland, OH 44101 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, A
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James G. Ke er Director
Enclosure:
IE Information Notice No. 79-13 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR Ef 2288 267 Harold W. Kohn, Power Siting Commission Mr. Daniel D. Wilt, Attorney 790620010)
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U.S." NUCLEAR REGULATORY COMMISSION
--e 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 feedvater 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 b: the licensee has determined that the minimu= collapsed water level (solid, viu out 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 da= age 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 7.1x106 f /hr feedflow 14.8x104 gpm recirculation flow rate (4 pumps) 2288 268 12 psid core op Equiement Out of Service (00s)
"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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