ML20090D675

AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked

ML20090D675
Person / Time
Site:	Oyster Creek
Issue date:	04/18/1975
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Anthony Giambusso Office of Nuclear Reactor Regulation
References
AO-50-219-75-11, NUDOCS 8303020273
Download: ML20090D675 (3)

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MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6111 asnun er ras ge}e { Public Utilities Corporation General amu

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Mr. A. Giambusso Director, Division of Reactor Licensing Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission i

Washington, D. C. 20555

Subject:

Oyster C' reek Station Docket No. 50-219 Abnormal Occurrence Report No. 50-219/75-11 The purpose of this letter is to forward to you the attached abnormal occurrence report in compliance with paragraph 6.6.2.a of the l

l Technical Specifications.

Enclosed are forty copies of this submittal.

V.cr{trulyyours, 5L4'b

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l DonaldA.Ross, Manager (

Generating Stations-Nuclear cs j

Enclosures l

cc: Mr. J. P. O'Reilly, Director Office of Inspection and Enforcement, Region 1 SD ;'

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4.u, n, 8303020273 750418 PDR ADOCK 05000219 S

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d MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J.07960

• 201-539-6111 g'{~, Public Uhhhes Corporahon seneral SrsTE u OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/75-11 Report Date April 18, 1975 Occurrence Date April 10, 1975 ss Identification of occurrence Violation of the Technical Specifications, paragraph 4.5.F.1.d, leakage of the main line drain and bypass line in excess of the SS. L allowable for any one to penetration or isolation valve. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15.E.

Conditions Prior to Occurrence The reactor was. shut down for refueling.

The reactor coolant temperature was i

less than 212 F and the reactor mode switch in refuel.

I Description of Occurrence On April 10,1975, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, a local leak rate test was conducted on the

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main steam line drain and bypass line (V-1-106, 107, 110, and 111), and the Icakage rate was calculated to be 38.3 scfh when corrected to 20 psig pressure.

While pressurizing the line, leakage was detected past the packing of V-1-110.

Apparent Cause of Occurrence Failure of the packing on valve V-1-110 is the cause of this occurrence.

Analysis of Occurrence This event cannot be fully analyzed until repairs are made to V-1-110.

At that time, the line will be tested again to determine.the leakage.

If required, further testing will be conducted to determine the leakage of the inside valves

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• Abnormal Occurrence Report No. 50-219/75-11 Page 2 (V-1-106 and 107) and the outside valves (V-1-110 and 111), separately, to detennine if a failure of redundant components had occurred.

Corrective Action 4

Valve V-1-110 will be repacked and then retested to assure its leak rate is less than allowable. The Plant Operations Review Committee concluded that re-packing the valve is sufficient repair action for this type of failure.

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