ML20024C095

LER 83-023/01T-0:on 830613,fire Damper FD-86,in Duct Work Between Auxiliary Bldg & Control Complex,Discovered Missing. Cause Unknown.Continuous Fire Watch Established.Evaluation underway.W/830627 Ltr

ML20024C095
Person / Time
Site:	Crystal River
Issue date:	06/27/1983
From:	Bufe J, Hughes P, Moore G FLORIDA POWER CORP.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
3F-0683-15, 3F-683-15, LER-83-023-01T, LER-83-23-1T, NUDOCS 8307120249
Download: ML20024C095 (3)

Text

NRC PORM 354 U. S. NUCLE AR REGULA7ORY COMMISSION LICENSEE EVENT REPORT EXHIBIT A (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI CONTROL SLOCK: I I ! I I I .Ih i .

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REPORT DATE 80 EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h o lon June 13, 1983, Personnel discovered a missinc fire Anmrer. Additinnn1 l o linvestigations revealed that' additional danners (arrroximntelv 55) were I

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CAUSE DESCRIPTION ANDCORRECftVE ACTIONS h l i o 1 The cause of this occurrence is unknown at this time. A continuous fire I

, , ivatch has been established in each affected area. An evaluation is under-1 i I vay to determine which damners must be replena ana /n* mnaf fiaa - a enp_ l

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SUPPLEMENTARY INFORMATION REPORT No.: 50-302/83-023/01T-0 FACILITY: Crystal River Unit 3 REPORT DATE: June 27,1983 OCCURRENCE DATE: June 13,1983 IDENTIFICATION OF OCCURRENCE:

Several fire dampers, protecting safety related areas were determined to be degraded and are considered to be nonfunctional per NRC interpretation. These fire barriers (approximately 55) are required to be functional by Technical Specification 3.7.12.

CONDITIONS PRIOR TO OCCURRENCE:

Defueled DESCRIPTION OF OCCURRENCE:

On June 13, 1983, while moving duct work to accommodate a plant modification, personnel discovered a missing fire damper (FD-86) in the duct work between the Auxiliary Building and the control complex. While processing an order for damper FD-86, it was found that the original damper procurement specifications specified fire dampers which are 1% hour rated instead of 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated as stated in the 1977 Fire Hazards Analysis.

Further investigation also revealed that approximately 24, of the 55 identified dampers, are installed in the duct work within the room rather than in the fire wall. This location is not consistent with standard design practice.

DESIGNATION OF APPARENT CAUSE:

The cause of these inadequacies is unknown at this time. Inconsistencies exist between various records (Procurement, Design, Licensing, etc.) which have not been traced to a single source at this time. A clarification of the cause will be included in the supplement referenced below.

ANALYSIS OF OCCURRENCE:

It is important to note that a lh hour fire barrier does allow a significant amount of time to prevent the spread of a fire.

Furthermore, the 1977 Fire Hazards Analysis concluded that only two (2) areas were likely to produce a fire in excess of in hours. Thus, during initial installation, the dampers did meet most of the protection requirements including those recommended by the National Fire Protection Association. These initial requirements, however, did not encompass all later requirements imposed by 10CFR50 Appendix R or license commitments.

CORRECTIVE ACTION:

A Continuous fire watch has been established in or adjacent to the fourteen (14) affected areas.

An evaluation is underway to determine which dampers must be replaced and/or modified. A supplement describing anticipated action (s), and a schedule, will be submitted by July 20,1983.

FAILURE DATA:

This is the third event reported under Technical Specification 3.7.12.

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Power COnPOnaTeoh June 27,1983 3F-0683-15 Mr. James P. O'Reilly Regional Administrator, Region II Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30303

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Licensee Event Report No.83-023

Dear Mr. O'Reilly:

Enclosed is Licensee Event Report No.83-023 and the attached supplementary information sheet, which are submitted in accordance with Technical Specification 6.9.1.8.i. This report supplies supplementary information to our initial report dated June 15,1983.

Should there be any questions, please contact this office.

Sin r ly, G. C. Moore Vice President Engineering Services AEF:mm Enclosure cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 pERCIAL COPW w.

A 8d1 General Office 3201 Thirty-fourm street soum. P O Box 14042 st. Petersburg. Florida 33733 813-866-5151