ML19317E765

Discusses Util Actions to Assure Min Radioactive Releases Noted in .Addl Precautions Include Batch Releases Following Sampling or Use of Sump Monitors to Control Releases

ML19317E765
Person / Time
Site:	Oconee
Issue date:	10/14/1977
From:	Parker W DUKE POWER CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 7912180951
Download: ML19317E765 (3)

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373-4083 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation

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Oconee Nuclear Station Docket Nos. 50-269, -270, -287 g/

Dear Sir:

In my letter of September 27, 1977 actions were described that would assure that radioactive releases are maintained as low as reasonably achievable at Oconee. These actions were in response to your letter of August 4, 1977.

The first action of this letter concerned the turbine buildings sumps and installed radiation monitors.

It was stated, in part, that during periods of known secondary system contamination, the turbine building sumps would only be batch released with prior sampling.

In this regard, it is our current intent to use either batch release with prior sampling or the sump radiation monitor to control the release of liquids from turbine building sumps. The following incorporate the action above and reiterate the other actions presented in my letter of September 27, 1977:

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-cent 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.

In instances when batch releases are made, no dependence will be made 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-ficati,ons presently contained in Oconee Technical Specification 3.9.

Very truly yours,

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L-William O. Parker, Jr WOP /mir t