05000269/LER-1981-025, Forwards LER 81-025/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-025/03L-0.Detailed Event Analysis Encl
ML20071H938
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 02/11/1982
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20071H941 List:
References
NUDOCS 8203080585
Download: ML20071H938 (2)


LER-2081-025, Forwards LER 81-025/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2692081025R00 - NRC Website

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" (b Mr. James P. O'Reilly, Regional Administrator S U. S. Nuclear Regulatory Commission 9 p O EC *gkg Region II 101 Marietta Street, Suite 3100 2 _g Atlanta, Georgia 30303 -

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Re: Oconce Nuclear Station 8 g ://

Docket No. 50-269 g N

Dear Mr. O'Reilly:

Please find attached Reportabic Occurrence Report R0-269/81-25. This report is submitted tursuant to Oconce 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 con-sidered to be of no significance with respect to its effect on the health and safety of the public. My letter of January 28, 1982 addressed the delay in the preparation of this report.

Ver truly yours, 4

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William O. Parker, J . \

JFK/php Attachment cc: Director Records Center Office of Management & Program Analysis Institute of Nuclear Power Operations U. S. Nuclear Regulatory Commission 1820 Water Place Washington, D. C. 20555 Atlanta, Georgia 30339 Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station 8203080585 820211 o' E.

PDR ADOCK 05000269 l'2(y'Il cg7 S PDR b OL g l

DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 1 Report Number: R0-269/81-25 P.eport Date: February 11, 1982 Occurrence Date: December 29, 1981 Facility: Oconec Unit 1, Seneca, South Carolina Identification of Occurrence: Reactor Building Cooling Unit Inoperable Conditions Prior to Occurrence: llot Standby, performing Zero Power Physics i Tests l Description of Occurrence: On December 29, 1981, Valve ILPSW-24 was cycled and shut to stop leakage through the valve, and could not be reopened. Valve I ILPSW-24 is the discharge valve for the 'C' Reactor Building Cooling Unit. i The inability to open this valve rendered the cooling unit inoperable.

Ayparent Cause of Occurrence: The apparent cause of this incident was exces-sive valve vibration causing the operator torque limit switches to vibrate loose, thus allowing the valve to shut with excessive torque.

Analysis of Occurrence: The two redundant Reactor Building Cooling Units were operable during this incident as required by the Technical Specifications.

Additionally, the Reactor Building Spray Pumps were operable; thus, the health and safety of the public were not affected by this incident.

Corrective Action: The valve operator was loosened and the valve cycled manually. The limit switches were tightened and reset, and the valve was satisfactorily cycled electrically; the Reactor Building Cooling Unit was declared operable. This valve application will be analyzed to determine if the use of the valve as a throttle valve is a correct application of this valve design.