05000287/LER-1981-004, Forwards LER 81-004/03L-0.Detailed Event Analysis Encl

Forwards LER 81-004/03L-0.Detailed Event Analysis Encl

ML20030B967
Person / Time
Site:	Oconee
Issue date:	04/10/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20030B968	List: 05000287/LER-1981-004, Forwards LER 81-004/03L-0.Detailed Event Analysis Encl 05000287/LER-1981-004-03, /03L-0:on 810312,valve 3FDW-105 Failed to Close Electrically After Chemical Sampling of Steam Generator B. No Apparent Cause Found.Valve Manually Closed & Circuit Breaker Opened,Disabling Valve
References
NUDOCS 8108250261
Download: ML20030B967 (2)

LER-1981-004, Forwards LER 81-004/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2871981004R00 - NRC Website

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Dear Mr. O'Reilly:

Please find attached Reportable Occurrence Report R0-287/81-04. This report is 4

submitted pursuant to Oconee Nuclear Station Technical Specification 6.6.2.1.b(2),

which concerns operation in a degraded mode permitted by a limiting condition for operation, and describes an incident which is considered to be of no signi-ficance with respect to its effect on the health and safety of the public.

Very truly yours,

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01 4 itS William O. Parker, Jr.

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Director Mr. Bill I.avallee Office of Management & Program Analysis Nuclear Safety Analysis Center U. S. Nuclear Regulatory Conunission P. O. Box 10412 Washington, D.C.

20555 Palo Alto. California 94303 0100250261 010410

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DUKE POWER COMPANY OCONEE UNIT 3 Report Number:

R0-287/81-04 Repore Date: April 10, 1981 Occurrence Date: March 12, 1981 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence: Failure of Value 3FDW-105 To Close Electrically Conditions Prior to Occurrence: Hot shutdown Description of Occurrencet At 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br /> on March 12, 1981 valve 3FDW-105 failed to close electrically af ter the chemical sampling of Steam Generator "B" was com-This constitutes operation in a degraded mode per Technical Specification plete.

3.6.3.b(2) and is thus reportable pursuant to Technical Specification 6.6.2.1.b(2).

Apparent Cause of Occurrence: Investigation found no apparent problems with the valve operation. However, initially there was no open indication light in the control room when the valve was cycled. Af ter one complete cycle and each subsequent cycleing of the valve, all indications of valve position worked pro-perly.

Analysis of Occurrence: The unit was in hot shutdown, and manual isolation was j

obtained within the time permitted by the Technical Specifications. Also, the redundant automatic isolation valve was operable. Thus, the health and safety of the public werenot endangered by this incident.

Corrective Action

Insiediate corrective action consisted of manually closing 3FDW-105 and operning the circuit breaker disabling the valve per Technical Specification 3.6.3.

The existing troubleshooting procedure is not entirely adequate regarding troubleshooting motor operated valves, therefore, a procedure will be written to cover troubleshooting motor operated valves. The current procedure is a generic troubleshooting procedure and does not specifically address items necessary to diagnose EMO problems.

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