ML19209C916

LER 79-086/03L-0:on 790916,channel D Reactor Bldg High Pressure Bistable Tripped.Caused by Buildup of Dust on Shaft of Reactor Bldg Switch BS-62-PS.Switch Was Disassembled, Cleaned,Reassembled & Returned to Svc

ML19209C916
Person / Time
Site:	Crystal River
Issue date:	10/10/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19209C913	List: ML19209C912 ML19209C916
References
LER-79-086-03L, LER-79-86-3L, NUDOCS 7910180472
Download: ML19209C916 (2)

Text

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EVENT DESCRirTICN Argo PROB A8LE CONSECuENCES h ITTTl l At 1153 in Mode 1, it was reported that the Channel "D" Reactor Building I g iHigh Pressure bistable tripped. This created an event contrarv to Technical 1 o . ISnecification 3.3.1.1. No effect upon the plant or eeneral public as redun- f a $ l dant Reactor Protection Channels were operable. This is the first occurrence f l of this tVpe reported. ' l 0 6 f

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i o l The cause of this event is attributed to a buildup sof dust on the shaft of I m i Reactor Building pressure switch BS-62-PS. The swiech was disassenbled. I w I cleaned, reassembled, and returned to service at 1455 following satisfactorv i

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SUPPLEMENTARY INFORMATION

1. Report No.: 50-302/79-086/03L-0

2. Facility: rystal River Unit #3

3. Report Date: 10 October 1979

4. Occurrence Date: 16 September 1979

5. Identification of Occurrence:

One reactor protection channel (Channel "D" Reactor Building High Pressure) inoperable contrary to Technical Specification 3.3.1.1.

6. Conditions Prior to Occurrence:

Mode 1 Power Operation (72%)

7. Description of Occurrence:

At 1153, it was reported that the Channel "D" Reactor Build-ing High Pressure bistable tripped. The affected channel was placed in the tripped mode at 1252. Further investiga-tion 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 test-ing.

8. Designation of Apparent Cause:

The cause of this event is attributed to a buildup of dust on the shaft in Reactor Building pressure switch PS~62-PS.

9. Analysis of Occurrence:

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

10. Corrective Action:

The pressure switch was disassembled, cleaned, reassembled, and returned to service at 1455 following satisfactory com-pletion of SP-112, Calibration of the Reactor Protection System. Reactor Building pressure switches associated with redundant channels "A", "B", and "C" will be inspected as soon as possible for generic implications. (

Reference:

W/R 9958)

11. Failure Data:

This is the first occurrence of this type reported.

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