ML20147F516
| ML20147F516 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 03/04/1988 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| LIC-88-129, NUDOCS 8803070367 | |
| Download: ML20147F516 (1) | |
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WI Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 March 4, 1988 LIC 88-129 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
Special Report on Inoperability of Fire Damper #61 The Omaha Public Power District, Holder of Operating License DPR-40 submits this special report in accordance with the requirements of Technical Speci-fication 2.19(7) regarding the inoperability of fire barrier Fire Damper #61 which was found inoperable on January 28, 1988.
Fort Calhoun Station Unit No.
1 Technical Specification 2.19(7) requires that all penetration fire barriers protecting safety related areas shall be functional (intact). With a pene-tration fire barrier non-functional, within one hour, either establish a continuous firewatch on at least one side of the affected penetration, or verify the operability of fire detectors on at least one side of the penetra-tion and establish an hourly firewatch patrol.
The non functional barrier shall be restored to functional status within seven days, or a report shall be prepared and submitted to the NRC within another 30 days.
On January 28, 1988, Fire Damper #61 was found to be inoperable due to holes inadvertently made in the damper sleeve to allow conduit to pass through. This necessitated replacement of the damper sleeve and rerouting of the conduit.
This work was accomplished in conjunction with station modification MR-FC-86-059 and was completed on March 4,1988. A firewatch was posted within one hour of the time of discovery and was released when the fire damper was re-stored to operable status.
The fire damper was inoperable in excess of seven days. This special report is being issued within the 30 day time limit of Technical Specification 2.19(7).
No further action is required.
Sincerely, kW R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior ResMent Inspector
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