ML19317H387
| ML19317H387 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/23/1980 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | |
| References | |
| TLL-248, NUDOCS 8006030459 | |
| Download: ML19317H387 (3) | |
Text
/
Metropolitan Edison Company
- h,"
f-ff (')
Post Office Box 480 "2
Middletown, Pennsylvania 17057 717 9444041 Writer's Direct Dial Number May 23, 1980 TLL 248 4
Office of Inspection and Enforcement Attn:
Boyce H. Grier, Director Region I U. S. Nuclear Regulatory Cc mission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit II (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Licensee Event Report No. 80-20/IP This letter is to confirm the conversation between Mr. G. A. Kunder, Unit II Supervisor Technical Specification Compliance, and Mr. R. Conte, Region I, NRC at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on May 23, 1980.
A condition considered reportable under Technical Specification 6.9.1.8 was declared at 1500 on May 22, 1980. During the attempted Reactor Building entry on May 20, 1980, it was discovered that a small purge valve ("E")
on the outer hatch bulkhead was open by procedure when entry into the inner door was attempted. When the inner door equalizing valve opened this created a path which technically violated containment integrity.
Although the alignment of the valve ("E") and attempted door opening were in accordance with Tech Spec 3.6.1.1, and 3.6.1.3 individually, and was performed in accordance with an approved procedure, the unique combination of valve ("E") being open following the purging operation simultaneous with the inner door opening operation constitutes a violation of containment integrity.
Technicians recognized the problem immediately and closed the valve and the procedures are being revised to preclude further occurrences.
Y D
8.006030 Metrecomn Ed. son Company is a Memter of the Genera' Nene U:st es Sys:ern L
- Mty 23, 1980 TLL 248 Also, in relation to reportability per 10 CFR 50.72, at 11:20 May 23, 1980, Mr. R. Conte informed Mr. G. Kunder that it was the Site NRC's opinion that the event was also reportable under 10 CFR 50.72.
As a result of that interpretation a call was placed to the NRC Operations Center in Bethesda to make the notification at 11:40 hours.
It should be noted that the event was not considered reportable per 10 CFR 50.72 when it occurred and thus the call was made af ter the fact to assure the record was conservatively 2
completed.
The condition created no threat to safety because the added precautions of maintaining a negative reactor building pressure assured that any equalizing air flow was into rather than out of the reactor building.
Further details will be included in the follow-up report.
Sincerely,
/s/ G. K. Hovey G. K. Hovey Director, TMI-2 GKH/GAK/In ec:
J. T. Collins
.