ML20134M328
| ML20134M328 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/29/1985 |
| From: | Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 85-05, 85-5, NUDOCS 8509040083 | |
| Download: ML20134M328 (2) | |
Text
i TENNESSEE VALLEY AUTHORITY
.c Sequoyah Nuclear Plant Post Office Box 2000
^
Soddy Daisy, Tennessee' 37379 4
August 29, 1985 i
U.S. - Nuclear Regulatory Commission Document Control Desk-Washington, DC 20555 Gentlemen:
l TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 2 - DOCKET NO.
50-328 - FACILITY OPERATING LICENSE DPR SPECIAL REPORT 85-05 The enclosed special report provides details concerning an inoperable fire door. This event is reported in accordance with the special report require-l ments of Technical Specification 3.7.12.
I l
Very truly yours, l
TENNESSEE VALLEY AUTHORITY
}
P. R. Wallace Plant Manager Enclosure cc (Enclosure):
J. Nelson Grace, Regional Administrator i
U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW l
Atlanta, Georgia 30323 Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 NRC Inspector, NUC PR, Sequoyah i
i 1
8509040003 850829 ADOCK 0 % y8 PDR S
Qh 1983-TVA 5OTH ANNIVERSARY j
j An Equal Opportunity Employer
I s..
m SPECIAL REPORT 85-05 SEQUOYAH NUCLEAR PLANT UNIT 2 On July 23,1985, at 0705 CST, it was discovered that fire door A-9 to residual heat removal pump room 2B at Auxiliary Building elevation 653 would not close properly. At that time, units 1 and 2 were operating in mode 1 at 100 percent power (2235 psig and 578 degrees F).
An hourly fire watch was already being conducted for the subject area due to Appendix R considerations and was continued.
An investigation showed that due to high usage the door hinge support plate inside the door was broken. The door will be temporarily repaired by September 6, 1985, and is scheduled for permanent replacement by December 18, 1985.
This report is required per the special report requirements of Technical Specification 3.7.12.
There was no ef fect on public health or safety.
i J