ML17160A482
| ML17160A482 | |
| Person / Time | |
|---|---|
| Issue date: | 10/30/1993 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | England L GULF STATES UTILITIES CO. |
| References | |
| IEIN-93-083, IEIN-93-83, NUDOCS 9311150094 | |
| Download: ML17160A482 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206654001 October 30'993 ENCLOSURE 4
Les England, Chairman BWR Owners Group c/o Gulf States Utilities River Bend Station, North Access Road St. Francisville, Louisiana 70775
Dear Mr. England:
As we discussed the week of October 4, 1993, this letter is to inform you about an issue that the NRC is evaluating concerning the potential loss of spent fuel pool (SFP) cooling following a loss of coolant accident (LOCA).
This issue was first brought to the NRC's attention in a 10 CFR Part 21 notification, dated November 27,
Subsequently, additional submittals related to this issue were submitted to the NRC on December 14, 1992 and January 2, March 31, August 13, and October 1,
1993.
The concerns, discussed in these submittals are identified in NRC Information Notice (IN) 93-83, "Potential Loss of Spent Fuel Cooling Following a Loss of Coolant Accident (LOCA)," which is enclosed.
In response to these
- concerns, Pennsylvania Power and Light Company, the licensee for SSES, has made submittals to the NRC dated May 24, July 6, and August 16, 1993.
Additionally, the licensee has met with the NRC in public meetings on March 18 and July 8, 1993, to discuss their position on the issue.
The NRC is establishing a task action plan to address this issue at SSES as well as its'eneric implications for other nuclear power plants.
We would be interested in knowing what plans the Boiling Water Reactors Owners Group (BWROG) has to address this issue.
If you have any questions regarding this letter or need further information, contact me at (301) 504-2884 or George Hubbard at (301) 504-2870.
Sincerely,
Enclosure:
As stated Ash k C. Thadani, Director Div sion of Systems Safety and Analysis Office of Nuclear Reactor Regulation
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