05000302/LER-1979-086-03, /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

/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: 05000302/LER-1979-086, Forwards LER 79-086/03L-0 05000302/LER-1979-086-03, /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
References
LER-79-086-03L, LER-79-86-3L, NUDOCS 7910180472
Download: ML19209C916 (2)

LER-1979-086, /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

Event date:
Report date:
3021979086R03 - NRC Website

text

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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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