ML20137U703

Fire Protection Special Rept 85-03:on 851216,insp of 14 Fire Dampers Identified Design or Installation Deficiencies Resulting in Dampers Being Determined Inoperable.Caused by Nonconforming as-found Fire Damper Configuration

ML20137U703
Person / Time
Site:	Oyster Creek
Issue date:	01/20/1986
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
85-03, 85-3, NUDOCS 8602190295
Download: ML20137U703 (3)

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GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River, New Jersey 08 /31-0388 609 971-4000 Writer's Ditoct Dial Numter:

January 20, 1986 Dr. Thomas E. Murley Regional Adninistrator US Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50. 219 Fire Protection Special Report Enclosed is Fire Protection Special Report No. 85-03 which is submitted in accordance with Technical Specifications 3.12.E.

If any any questions or comments should arise, please contact Mr.

Drew Holland, Oyster Creek Licensing Manager at (609)971-4643.

Te'ter S. Fiedler Vice President & Director Oyster Creek P8F:JJR: dam Enclosure (0140A) cc: NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 0602190295 060120 QDR ADOCK 05000219 PUlt

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- o OYSTER CREEK NOCLEAR GENERATING STATION Forked River, NJ 08731 Special Report 85-03 Date of Discovery l

December 16, 1985 Date of Report January 20, 1986 Identification of Occurrence An inspection of 14 fire dampers identified design or installation deficiencies which resulted in these dampers being determined to be inoperable.

Plant Condition Prior to Discovery The reactor was fueled with the mode switch in the REFUEL position. The reactor coolant temperature was greater than 2120F.

Description of Discovery On December 10, 1985, a field walkdown of the fire dampers installed in ventilation ducts penetrating fire barriers to safety related areas was '

performed. The fire areas evaluated were:

The New Cable Spreading Room

! The Electrical Tray Room i The 4163 Volt "C" and "D" Vaults The "C" Battery Room l As a result of the walkdown and the evaluation of the findings,14 fire dampers were found to have similar deficiencies to those identified in IE Information Notice No. 83-69 and were dolcared inoperable on December 16, 1985.

Cause of Inoperability The cause of inoperability was the as-found fire damper configuration which did not conform to applicable codes / standards and vendor's installation requirements. A review of the actual installation of these dampers was unable to assure the operability of the fire dampers due to the following deficiencies:

1. Three fire dampers were found to be installed in non-fire rated duct work. The remaining eleven fire dampers were installed at the rated fire barriers.

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Dr. Thomas E. Murley Page 2

2. No UL label could be identified on five of the fourteen fire dampers.

These are located in the floor of the New Cable Spreading Room.

3. All fourteen dampers were not installed per manufacturers installation instructions, involving one or more of the following specifics:.

a. No clearance was provided around the fire damper to allow for thermal expansion,

b. On center spacing of damper attachment fasteners exceeded maximum limits.

c. Closure angles were not provided around the entire perimeter of the duct.

d. Closure angles were not provided on both sides of a fire barrier.

e. On center spacing of the fasteners holding the angle iron to the duct exceeded the maximum limits.

A preliminary evaluation indicated that 5 of the 14 fire dampers found inoperable may not require any modifications or repairs. These are located in the floor of the new cable spreading room. The results of this evaluation when finalized will either be incorporated in a revision to Oyster Creek's 10CFR50 Appendix R submittal or a separate submittal addressing this specific concern.

Action Taken An hourly fire watch patrol was established within one hour of the determination of the dampers' inoperability as required by Oyster Creek Nuclear Generating Station Technical Specification 3.12.E for the fire areas identified above. The hourly fire watch patrol will continue until a final disposition for the dampers is accomplished.

P_1_ans and Schedule A definition of work scope and a schedule for implementation will be provided by February 28, 1986.