ML19317D938

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Forwards Supplemental Info Re Designation of Apparent Cause of Occurrence in Abnormal Occurrence AO-269/75-19 Filed 751017.Incident Caused by Procedural Inadequacy in Coolant Storage Sys Preoperational Test Procedure
ML19317D938
Person / Time
Site: Oconee 
Issue date: 12/29/1975
From: Parker W
DUKE POWER CO.
To: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7912100618
Download: ML19317D938 (3)


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Mr. Norman C. Moseley

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Atlanta, Georgia 30303 Re: Oconee Unit 2 Docket No. 50-269 A0-270/75-19

Dear Mr. Moseley:

My letter of October 17, 1975 transmitted Abnormal Occurrence Report A0-270/75-19 concerning an unplanned release of radioactive liquids through the Turbine Building sump. This letter provides supplemental information relative to the " Designation of Apparent Cause of Occurrence" section of that report.

The line which allowed the discharge to the Turbine Building sump was originally intended to connect the secondary side of the steam generator to the condensate storage tank via the component drain pump, thereby allowing for quick drainage of the steam generator during initial testing by pumping with the component drain pump.

An investigation into construction records shows that the component drain system was turned over from the Construction Department to the Steam Production Department in February 1972 with a note that the line from the component drain pump to the condensate storage tank was cut to allow for a system flush.

This was not formally identified, however, as an exception in the turnover documentation.

Steam Production Department Preoperational Test Procedure TP/2/B/230/12,

" Coolant Storage System Flush", required that the line be cut downstream of the isolation valve in the vicinity of the Turbine Building sump. This was verified on March 21, 1973, and the flush was completed on March 22, 1973.

There was no requirement in the procedure to assure that the line was restored to its original intended configuration. Had this been accomplished, two isolation valves would have sepsrated the contaminated quench tank drain system from the condensate storage system and one leaking valve would not have resulted in release of radioactive liquid.

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~ i-Mr. Norman C. Moseley December 29, 1975 Page 2 Therefore, it is considered that this incident was primarily caused by a procedural inadequacy in the Coolant Storage System preoperational test proceddre.

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William O. Parker, Jr.

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