ML19290E843

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Discusses Response to Questions Per 800102 & 03 Telcons Re Waste Disposal Activities.Steam Distillate Discharged Directly Into Atmosphere W/Steam Samples Showing Little Radioactivity.Solids Drying Equipment Will Be Installed
ML19290E843
Person / Time
Site: Wood River Junction
Issue date: 01/10/1980
From: Stevenson R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Crow W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8003170127
Download: ML19290E843 (2)


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UNITED STATES

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JAN 101990 Doc':et No.70-820 MEMORANDUM FOR:

W. T. Crow, Section Leader Uranium Process Licensing Section Uranium Fuel Licensing Branch FROM:

Robert L. Stevenson Uranium Process Licensing Section Uranium Fuel Licensing Branch

SUBJECT:

TELECONS ON JN4UARY 2 NiD 3,1980 WITH MESSRS. GREGG N1D HELGESON, UNITED NUCLEAR COMPANY (UNC), WOOD RIVER JUNCTION, R.I., CONCERNING WASTE DISPOSAL ACTIVITIES UNC's letter dated December 21, 1979 provided additional details of their plans for disposing of the process wastes currently stored in lagoons at the plant site. UNC intends to evaporate the liquids and to dry the solids for shipment to a licensed burial site. The telephone calls were made to find out some additional details of the operation:

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What UNC plans to do with the overheads from the evaporator.

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What is being done with the process wastes currently being generated?

In response to Question 1, fir. Gregg stated that the steam distillate is being discharged directly to the atmosphere, but samples of the steam show very little radioactivity. (Section 407.1 of SNM-777 requires cont 'nuous monitoring of all gaseous ef fluents.)

In response to Question 2, Mr. Gregg explained that the evaporator cannot handle solids, and hence most of the currently generated process wastes must go to the lagoon system for solids removal.

Following installation of the solids drying equipment (which the December 1979 letter indicates should be accom-plished by April 1,1980), it will be possible to route all newly generated process wastes directly to the waste handling system without using lagoons.

Mr. Gregg stated that approximately 22,000 gallons of lagoon supernate had been evaporated and the 4 GPM evaporation rate attained.

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Dr. Shum and I called Mr. Helgeson on January 3 to inquire about the method being used to monitor radioactivity in the evaporator off-gas. Mr. Helgeson said that the evaporator tube sheet had failed and that the evaporator off-gas would be continuously monitored when evaporation was resumed, following repair of the tube sheet.

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h vv Robert L. Stevenson Uranium Process Licensing Section Uranium Fuel Licensing Branch

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