ML19221A698
| ML19221A698 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 05/29/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mary Johnson SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 7907030101 | |
| Download: ML19221A698 (1) | |
Text
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- jaa ung'c UNITED ST ATES NUCLEAR REGULATORY COMMISSION
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South Carolina Electric and Gas Con:pany Atto:
H. C. Johnson, Vice President Special Services and Purchasing Post Office Box 764 Colu=bia, South Carolina 29218 Gentlemen:
This Information Notice is provided as an early notification of a possibly It is expected that recipients will review the significant matter.
No specific information for possible applicability to their facilities.
If further NRC evaluations action or response is requested at this time.
so indicate, an IE Circular or Bulletin vill be issued to recoecend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, C~
gJamesP.O'Reilly Director
Enclosure:
Information Notice No. 79-13 w/ Enclosures 273 120 5665530101 Q
UNITED STATES NUCLEAR REGULATORY COMMISSION OyFICE OF INSPECTION AND Eh70RCEMENT HASHINGTON, D.C.
20555 May 29, 1979 IE Infor,mation Notice No. 79-13 INDICATION OF IDW WATER LEVEL IN THE OYSTER CREEK REACTOR Suasaary 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 instrument.s (triple lov level), while the re=af ning level instruments, sensing free the reactor ammlus area indicated water levels above any protective feature setpoint (Figure 1).
The water level within the core shroud area was reduced below the " triple lov 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 indicate no fuel damage occurred.
General Oyster Creek is a non-jet pump BVR with licensed power of 1930 w t.
The plant was first made critical May 3, 1969.
Status Before Transient Operating at naar full power with the main parameters at levels as follows:
1895 Wt power level 79" Yarvsy (13'4" over top of fuel) reactor water level 1020 psig reactor pressure 7.1x106 f/hr feedlov 14.8x104 gpr recirculation flow rate (4 pus:ps) 12 paid core p Equipment Out of service (005) l DUPLICATE DOCUMENT (()
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