ML19318B999

Supplemental LER 79-086/03L-1:on 790916,channel D Reactor Bldg High Pressure Bistable Tripped.Caused by Corrosion Buildup on Reactor Bldg Pressure Switch.Switch Was Cleaned & Returned to Svc

ML19318B999
Person / Time
Site:	Crystal River
Issue date:	06/17/1980
From:	Lancaster K FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19318B997	List: ML19318B996 ML19318B999
References
CS-80-166, LER-79-086-03L, LER-79-86-3L, NUDOCS 8006300401
Download: ML19318B999 (2)

Text

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cALSE CESCA18TICN ANC c0 AREOOVE AO* IONS i;a;I The cause of this event is attributed to corrosion buildup on Reactor Building ,

, pressure switch BS-62-PS. The switch was disassembled, cleaned, dried, re-assembled, and returned to service at 1455. The associated pressure switch

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s, SUPPLEMENTARY INFORMATION Report No.: 50-302/79-086/03L-1

'Fccility: Crystal River Unit #3 Ripsrt Date: 17 June 1980 Occurrence Date: 16 September 1979 Idtntification of Occurrence:

One reactor protection channel (channel "D" Reactor Building hig pressure) inoperable contrary to Technical Specification 3.3.1.1 Conditionr,P*ior to Occurrencer Mode 1 power operation (72%)

D:scription of Occurrence:

At 1153, it was reported that the channel "D" Reactor Building high pressure bistable tripped. The affected channel was placed in the tripped mode at 1252. Further investigation revealed that Reactor Building pressure switch BS-62-PS had failed.

Maintenance restored operability. BS-62-PS was returned to service at 1455 following post-maintenance testing.

Drsignation of Apparent Cause:

The cause of this event is attritot-d to corrosion buildup on Reactor Building pressure switch BS-62-PS, due to moisture accumulation in the associated pressure switch cabinet (3A4) rather than the dust as originally reported.

Analysis of Occurrence:

No effect upon the plant or general public as redundant reactor protection channels were operable.

Corrective Action:

The pressure switch was disassembled, cleaned, dried, reassemble and returnedEto service at 1455 following satisfactory com-pletion of SP-ll2, Calibration of the Reactor Protection System. Channels A, B, and C switches exhibited no corrosion buildup when inspected per Work Request 9958 and on subsequent checks during current outage.

Failure Data:

This is the first occurrence of this type. reported.

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