ML20214T441

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Special Rept:On 870501,util Informed by Ruskin Mfg That at Least Two Fire Dampers Installed in HVAC Duct Penetrations of Fire Barriers Improperly Installed & Therefore Ul Rating Was Void.Firewatch Established.Mod Request Issued
ML20214T441
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/05/1987
From: Andrews R
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-398, NUDOCS 8706100269
Download: ML20214T441 (2)


Text

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l Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 June 5, 1987 LIC-87-398 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Special Report on Inoperability of Fire Barriers Gentlemen:

The Omaha Public Power District, holder of Operating License DPR-40, submits this special report pursuant to the requirements of Fort Calhoun Station Unit No.1 Technical Specification 2.19, " Fire Protection System".

Fort Calhoun Station Unit No. 1 Technical Specification Section 2.19(7) requires that all penetration fire barriers protecting safety-related areas shall be functional (intact). With a penetration fire barrier nonfunctional, 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 penetration and establish an hourly firewatch patrol.

Restore the nonfunctional penetration to functional status within seven days, or prepare and submit within an additional 30 days a report to the Nuclear Regulatory Commission. This report is being submitted pursuant to Technical Specification 5.9.3.

On May 1,1987, OPPD was informed by Ruskin Manufacturing that at least two of the fire dampers installed in HVAC duct penetrations of fire barriers were improperly installed and therefore their U.L. rating was void. Fire detectors on one side of each penetration were verified to be operable and an hourly firewatch patrol was initiated within one hour.

Subsequent to this, a field investigation was conducted by on-site and off-site engineering personnel to determine if other improperly installed fire dampers existed. An additional eight fire dampers were also found to be installed such that their U.L. rating was void. Hourly firewatch patrols were then initiated for the other affected areas within one hour of discovery, after verifying fire detector operability.

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y N U. S. Nuclear Regulatory Commission LIC-87-398 Page Two Further discussions with damper manufacturers indicate that 38 other dampers

' installed during original plant construction were housed in an unrated sleeve design because U.L. Standard 555 for fire damper testing did not exist at the time of original plant construction. It-is believed that their continued use can be justified pending further investigation. However, the areas affected by these dampers have also been placed on the hourly firewatch patrol until the investigation is comploted.

Modification Request MR-FC-86-84, " Additional Fire Dampers", is being expanded in scope to include the corrective action required by these deficiencies. As a minimum, eight fire dampers will be remounted or replaced under this modifica-tion. Any additional resolution or alteration needed by the remaining 38 will be accomplished under this modification also.

These fire barrier fire dampers have been inoperable in excess of seven days and an hourly firewatch patrol is being maintained in the affected areas. A follow-up report will be issued within 30 days of completion of all work detailing the corrective actions taken. This special report is being issued within the 30-day limit specified in Technical Specification 2.19(7).

Sincerely,

& M R. L. Andrews Division Manager Nuclear Production RLA:rge c: R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector T. J. McIvor R. J. Mueller J. E. Lechner i

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.

Washington, DC 20036 i

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