05000287/LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Encl

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Forwards LER 82-014/01T-0.Detailed Event Analysis Encl
ML20064J206
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 01/05/1983
From: Tucker H
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20064J209 List:
References
NUDOCS 8301170524
Download: ML20064J206 (2)
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LER-1982-014, Forwards LER 82-014/01T-0.Detailed Event Analysis Encl
Event date:
Report date:
2871982014R00 - NRC Website
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text

i er DUKE POWER GOMPANY P.O. ISOX 33180 CitAMI,OTrE, N.C. 28242 bl vu e en rr (7 8 17 January 5, 1983 m... r-= ~"

Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Subject: Oconce Nuclear Station Docket No. 50-287

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Dear Mr. O'Reilly-

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Please find attached Reportable Occurrence Report R0-287/82-14. Thisieport is submitted pursuant to Oconee Nuclear Station Technical Specificatiod

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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 December 31, 1982 addressed the delay in the preparation of this report, r<

Very truly yours, W

f W

Ital B. Tucker I

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Attachment i

i cc:

Document Control Desk U. S. Nuclear Regulatory Commission i

Washington, D. C. 20555 1

Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 O {\\$

Mr. E. L. Conner, Jr.

odgiN'C Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission np Washington, D. C. 20555

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{/ N 8301170524 830105 PDR ADOCK 05000287 g

PDR

Duke Power Company Oconee Nuclear Station Report Number: R0-287/82-14 Report Date: January 5,1983 Occurrence Date: December 11, 1982 Facility: Oconee Unit 3, Seneca, South Carolina Identification of occurrence:

3B steam generator tube leaks Condition Prior to Occurrence:

100% FP Description of Occurrence:

On December 11, 1982, a steam generator tube Icak developed in the 3B steam generator, as indicated by an increase in the 3RIA-40 count rate. The tube leak was calculated at.208 gpm. The unit was shut down that day for leakage identification and repair. The nitrogen bubble test was performed on December 14, 1982; the eddy current differential test was run on December 15, 1982; and the eddy current 8 x 1 probe test was run on December 16, 1982.

There were 417 tubes tested by the differential test and 165 tubes were tested by the 8 x 1 probe test. The results of these tests were that tube 77-9 was cracked (leaker) and tube 78-2 had a 62 percent through wall indication at the 15th Tube Support Plate. A fiber optic inspection was performed on tube 77-9 on December 15, 1982 and revealed a tight circumferential crack of about 45 degrees located near the bottom edge of the upper tube sheet.

Apparent Cause of Occurrence:

The apparent cause of the tube Icak was a circumferential crack propagated by low stress high cycle fatigue which is typical of the type associated with the inspection lane degradation mechanism. Tube 77-9 is on the open lane (row 76) and is the outermost tube of a line that had been previously plugged (77-10 through 77-21).

Analysis of Occurrence:

The leakage of this tube during operation was.208 gpm which is well below the technical specification allowed limit of 1 gpm. Personnel and systems adequately controlled this event and the releases were well within technical specification limits. 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. Nitrogen bubble, eddy current, and visual inspections were performed on the 3B steam generator to define the problem. Tubes 77-9 and 78-2 were both stabilized from the top and explosively plugged from the bottom.

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