ML19352B206

LER 80-067/01X-1:on 801107,tritium Concentration Exceeded Limits in Unrestricted Area Following Radioactive Liquid Waste Release.Caused by Inadequate Procedure Failing to Avoid Problems of Reactor Bldg Sump Discharge Sys

ML19352B206
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1981
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19352B184	List: ML19352B183 ML19352B206
References
LER-80-067-01X, LER-80-67-1X, NUDOCS 8106030341
Download: ML19352B206 (1)

Text

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[TTT] l On Friday, November 7,1980, at 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> , it was determined that the concentration l rypq l cf tritium in an unrestricted area following a radioactive liquid wasta release that l I o 14 I [ was made on October 23, 1980, exceeded the limit specified in LCO 4.8.2(a). Re . l

o ; 3, j portable per Fort St. Vrain Technical Specification AC 7.5.2(a)2. No accompanying l o o l occurrence. Reportable Occurrence R0 80-52 deals with a related subject area. l IoTTII I 10181I 80 l

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g l avoid problems arising from the design of the reactor building sumo discharge system. I g l Sypass installed around the oil separator in the reactor building sumo discharge sys-l ii64i l tem on February 8,1981. System operating procedure and surveillance requirement l 7 e 9 amended to provide for use of bypgs during liquid waate releases, flush of remainingo

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