ML20042A508

Forwards LER 82-003/01T-0.Detailed Event Analysis Encl

ML20042A508
Person / Time
Site:	Oconee
Issue date:	03/09/1982
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20042A509	List: ML20042A508 ML20042A516
References
NUDOCS 8203230507
Download: ML20042A508 (2)

Text

r-O Duxn POWER COMPANY Powen Uu Loswo 4ec Sourn Cucacu Sruzer, Crunwire. N. C. ana4a WILLIAM O. PA R M E R, J R.

v.c r e.e..or~' March 9, 1982 T r ' < *** " <: ^" *

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$ T EA M P.CouCTION 373-4083 c) ~~

Mr. James P. O'Reilly, Regional Administrator fj U. S. Nuclear Regulatory Commission Region II RECEWED 101 Marietta Street, Suite 3100 01

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3 rb Atlanta, Georgia 30303

} MAR 2 219826 -

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• 6-Re: Oconee Nuclear Station '**

82Gtumtr tp 7 2 3 Docket No. 50-269 p

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Dear Mr. O'Reilly:

N 01 Please find attached Reportable Occurrence Re,) ort R0-269/82-03. Thisr$rt is submitted pursuant to Oconee Nuclear Station Technical Specification 6.6.2.1.a(3), which concerns an abnormal degradation of the reactor coolant pressure boundary. This report describes an incident which is considered to be of no significance with respect to its effect on the health and safety of the public. My letter of February 28, 1982 addressed the delay in the preparation of this report.

Verv truly yours, p

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i wa (d . &

William O. Parker, Jr.

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 l

Mr. W. T. Orders Mr. Philip C. Wagner NRC Resident Inspector Office of Nuclear Reactor Regulation Oconee Nuclear Station U. S. Nuclear Regulatory Commission Washington, D. C. 20555

,OFFICIAE.copyy O 000 h hM

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DUKE POWER COMPANY OCONEE NUCLEAR STATION UNIT 1 Report Number: R0-269/82-03 Report Date: . March 9, 1982 Occurrence Date: February 9, 1982 Facility: Oconee Unit'1, Seneca, South Carolina Identification of Occcurrence: lA steam generator tube leak Conditions Prior to Occurrence: 100% FP Description of Occurrence: On February 9, 1982, a steam generator tube leak developed on the 1A steam generator, as indicated by an increase in the 1RIA-40 count level. Based on the radiation count level increase the calculated leak rate was 0.11 gal / min.

Apparent Cause of Occurrence: The apparent cause of the tube leak was a high cycle fatigue failure. This is based on experience with similar tube failures in the Lane Region at the fifteenth tube support plate on the upper tube sheet.

Analysis of Occurrence: The last eddy current test of Tube 74-2 was performed during an outage in July 1981. No indications of tube degrada-tion were found during that inspection.

Personnel and. systems adequately controlled this event and the releases were well within regulatory requirements. Thus, it is considered that the health and safety of the public were not affected by this event.

Corrective Action: The reactor was shut down, and the leaking tube was identified as Tube 74-2, which was stabilized from the top and explosively plugged from the bottom. Eddy Current Testing was conducted on all tubes in the Lane Region and no other defective tubes were found.

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