ML19340A121

Proposed Tech Spec 3.9.7 Re Measures to Assure Conformance W/Liquid Waste Effluent Release Limits

ML19340A121
Person / Time
Site:	Oconee
Issue date:	07/30/1976
From:	DUKE POWER CO.
To:
Shared Package
ML19340A111	List: ML19340A110 ML19340A121
References
NUDOCS 7911250041
Download: ML19340A121 (2)

Text

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3.9.3. The rate of release-of radioactive materials in liquid waste from the station shall be controlled such that the instantaneous concentrations of radioactivity in liquid waste upon release from the Restricted Area, does not exceed the values' listed in 10CFR20, Appendix B, Table II, Column 2.

3.9.4 The equipment installed in the liquid radioactive waste system shall be maintained and operated for the_ purposes _of keeping releases with-4 in the objectives of these specifications and shall process all liquids prior to their discharge in order to limit the activity, excluding tritium and disso?ved noble gases, released during any calendar quarter to 1.25 curies or less per unit.

3.9.5 As far as practicable,-the releases of liquid waste shall be co-ordinated with the operation _of the Keowee Hydro unit.

3.9.6 Liquid waste. discharged from the liquid waste disposal system shall be continuously monitored during release. The liquid effluent monitor reading shall be compared with the expected reading of each' discharge batch. The monitor shall be tested daily or prior to releases and calibrated at refueling intervals. The calibration procedure shall consist of exposing the detector to a referenced -

calibration source _ in a controlled, reproductible geometry. The sources and geometry shall be referenced to the original monitor calibration which provides the applicable calibration curves.

3.9.7 The effluent control monitor shall be set to alarm and automatically close the waste discharge valve such that the appropriate require-ments of the specification are met.

In the event that the effluent control monitor is inoperable or cannot be calibrated to perform this function, the following will be performed to assure that prescribed release limits are not exceeded: A redundant valve lineup check of the effluent pathway and redundant sample analyses will be performed prior to each liquid effluent release.

These additional actions will be applicable until December 1, 1976.

3.9.8 In addition to the continuous monitoring requirements, liquid radio-active waste sampling and activity analysis shall be performed in

-accordance with Table 4.1.3. Records shall be maintained and reports of the sampling- and ~ analysis shall be submitted in accordance with Section 6.6 of these Technical Specifications.

Bases It is expected that the releases of radioactive materials and liquid wastes will be kept within the design objective levels and will not exceed the con--

centration: limits.specified in 10CFR20. These levels provide the reasonable assurance that the -resulting annual exposure to the whole body or any in-dividual body organ will not' exceed 5 millirem per year. At the same time, the 1icensee is~ permitted the flexibility of operation compatible with

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considerations of health and safety to assure that the public is provided a dependable source of power ~under unusual' operating conditions which may temporarily result.in-releases higher than design objective levels but still within the concentration limits specified in 10CFR20. - -It is expected that when using this operational flexibility under unusual operating conditions, the licensee shall exert every effort to keep the levels of-radioactive materials and liquid wastes as low as practicable and that annual releases will not exceed a'small fraction of the annual average concentration limits specified in 10CFR20.

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