ML19263D295

LER 79-018/03L-0 on 790301:inner Airlock Door Found Unlatched.Caused by Inadequate Latching Design.Corrective Action Will Be Determined Upon Results of Engineering Info Request

ML19263D295
Person / Time
Site:	Crystal River
Issue date:	03/14/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19263D290	List: ML19263D289 ML19263D295
References
LER-79-018-03L, LER-79-18-3L, NUDOCS 7903270349
Download: ML19263D295 (2)

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SUPPLEMENTARY INFORMATION Report No.: 50-302/79-018/03L-0 Facility: Crystal River Unit #3 Report Date: 14 March 1979 Occurrence Date: 1 March 1979 Identification of Occurrence:

Containment airlock inoperable contrary to Technical Specification , 3.6.1.3. a and primary containment integrity not maintained contrary to Technical Specification 3.6.1.1.

Conditions Prior to Occurrence:

Mode 3 (hot standby)

Description of Occurrence:

At 0900, while entering the Reactor Building for maintenance and inspection, it was discovered that the inner airlock door was unlatched. The inner door was closed immediately to re-establish containment integcity. Investigation has revealed that if the inner personnel doo? is closed too fast, the interlocks can be satisfied without the latching mechanism engaging. This allows the door to bounce off the latch and reopen slightly. The interlocks still being satisfied allows the outer personnel door to be opened.

It is felt that perr.onnel exiting the Reactor Building just prior to the identification of this event, closed the inner door as described in the investigation. SP-181, Containment Airlock Test, was performed to verify the operability of the airlock interlack and latching. This was accomplished with satisfactory results.

Designation of Apparent Cause:

The cause of this event can be attributed to an inadequate design of the containment airlock latching mechanism.

Analysis of Occurrence:

No effect upon public health and safety, as the reactor was in a safe shutdown condition. Containment integrity was restored immedi-ately.

Corrective Action:

As a result of this event, a Request for Engineering Information (REI) was generated for an engineering evaluation of the airlock latching mechanism. Corrective action will be determined based upon the results of the engineering evaluation.

Failure Data:

First occurrence of the Reactor Building airlock failure reported under these Technical Specifications.

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