ML19312C724

Responds to NRC .Lists Util Actions Taken to Assure That Monitoring & Procedural Controls Maintain Radioactive Releases Alap

ML19312C724
Person / Time
Site:	Oconee
Issue date:	09/27/1977
From:	Parker W DUKE POWER CO.
To:	Case E, Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 7912190934
Download: ML19312C724 (3)

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September 27, 1977 Vict PSE$aOEgt TELEP=CNE: A#EA 704 373-4083 SYEAu PROOuCT:OP

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Mr. Edson G. Case, Acting Director n 4 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission

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a Attention:

Mr. A. Schwencer, Chief C

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Reference:

Oconee Nuclear Station II: 6 0\\

Docket Nos. 50-269, -270, -287

Dear Sir:

Your letter of August 4, 1977 concerned items discussed at a June 1, 1977 meeting at the Oconee Nuclear Station with regard to additional monitoring and procedural controls which might be employed to assure that radioactive releases are maintained as low as reasonably achieva-ble.

In this regard, the following actions have been or will be taken:

1.

Radiation monitors have been installed in the two turbine building sumps. These monitors provide alarms in the control room of inad-vertent radioactive release entering the turbine building sump or upon malfunction of the monitor.

In order to ensure that inadver-tent radioactive releases from the sump do not occur either the radiation monitors will be operable or the sumps will be sampled prior to batch release.

Either measure in itself is considered reasonable and effective to prevent inadvertent releases of radio-active liquids from the turbine building sumps to the environment.

During periods of known secondary system contamination, the turbine building sumps will be batch released with prior sampling.

In instances when batch releases are made, no dependence will be made l

on the radiation monitors, 2.

A composite, flow proportional water sampler will be installed at the outfall of the oil collection basin by March 1, 1978. Weekly, a gamma isotopic analysis will be performed on the composite samples.

In the event of an inadvertent radioactive liquid release to the basin, an additional composite sample will be drawn.

This sample will be analyzed for Sr89 and Sr90 along with the samples taken on a monthly basis from the other low level activity radio-active waste tanks.

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Procedures will be instituted by November 1, 1977 which will require two independent valve alignment checks prior to discharging radio-active spent secondary system demineralizer resins to the receiving tanks. This procedure will be followed whenever the activity in the secondary system indicates that there has been primary to secondary leaks, and continue until all activity from the secondary system has been removed.

Although your letter requested that the above proposals be incorporated into the Oconee Technical Specifications, we do not feel that this action is required. The equipment and procedures listed above are extensions of the defense in depth concept to prevent inadvertent liquid effluent releases. They support the objectives and specifications written in Oconee Technical Specification 3.9, Release of Liquid Radioactive Waste, and as such assist in the effective control of the release of radioactive liquid wastes from the station. Any revision to the Technical Specifica-tion incorporating the above items would duplicate objectives and speci-fications presently contained in Oconee Technical Specification 3.9.

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William O. Parker, Jr.

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