ML20084G917

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Ro:On 711211,failure of 3/4 Inch Isolation Condenser Vent Line Discovered.Caused by Excessive Motion of Vent Line. Broken Nipple Repaired & New Pipe Support Installed
ML20084G917
Person / Time
Site: Oyster Creek
Issue date: 01/12/1972
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084G920 List:
References
NUDOCS 8304270126
Download: ML20084G917 (2)


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Jersey Central Powo,e r% Light Company

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M ADISoN AVENU E AT PUNCH BOWL Ro AD e MoRRISToWN, N.J. 07960 e 539-6118' January 12, 1972 N

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Dr. Peter A. Morris, Director f

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N Division of Reactor Licensing lA N JM United States Atomic Energy Commission

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D Washington D. C. 20545 Un

Dear Dr. Morris:

Subject:

Oyster Creek Station Docket No. 50-219 Failure of Isolation Condenser Vent Line The purpose of this letter is to report to you, as a matter of interest, the failure of a 3/h-inch vent line from the isolation condenser system. The vent line failed at the point where it is connected to one of the main steam lines downstream of both main steam isolation valves and also downstream of the isolation valves for each isolation condenser vent line.

The above failure was discovered on Saturday, December 11 and was followed by an orderly shutdown which permitted closing thes main steam isolation valves by 8:20 p.m. on December 11.

The repairs were completed by h:15 a.m. on Saturday, Decem'er 12 and were followed b

by a normal startup to power.

g We believe the cause of the failure was due to excessive 1 motion of the vent line since the first pipe hanger upstream of the fai]ure was found to be disconnected thereby permitting the line to raove freely. The failure was repaired by removing a broken nipple at the main steam line connection and revelding it.

In addition, a new pipe support was installed in the immediate area and the existing hanger that was found disconnected was reconnected. All other hangers associated with this vent line were inspected'and found to be in~

satisfactory c_ondition.

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NS 8304270126 720112 M

PDR ADOCK 05000219

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U Dr. Peter A. Morris Page II January 12, 1972 We believe there 10 no safety significance associated with this incident since the failure occurred downstream of automatically actuated, or remotely operated, isolation valves.

In addition, all gases released from the steam leak were monitored and exhausted via the main stack.

All liquids were collected through the radwaste floor drain collection system.

We are enclosing twenty-five copies of this report.

Very truly yours,

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Ivan R. Finf 'ck,

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Manager, Nuclear Generating Stations IRF/pk Enclosures cc:

Mr. J. P. O'Reilly, Director Division of Compliance, Region I 5

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