ML19323A160
| ML19323A160 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 02/12/1980 |
| From: | Stevenson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8004170321 | |
| Download: ML19323A160 (2) | |
Text
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.. t@h UNITED STATES o
-g NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20555 ij k.
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FEB 12-1980 DOCKET NO.:
70-820 APPLICANT:
United Nuclear Corporation (UNC)
(UNC Recovery Systems Division)
FACI LITY:
Fuel Recovery Operation Wood River Junction, Rhode Island
SUBJECT:
JANUARY 29, 1980 MEETING WITH UNC REPRESENTATIVES Purpose To discuss a proposed amendment to UNC's license (SNM-777) to authorize modifications in UNC's procedures for proce: sing of process wastes including wastes now stored in lagoons at the site.
Place and Date NRC office in Silver Spring, Maryland, Ja'nuary 29, 1980.
l Attendees NRC - W. T. Crow, E. Y. Shum, R. L. Stevenson j
UNC - J. Dunning, R. Gregg, C. Helgeson Dis cussion The currently authorized procedures for treatment of process wastes include 6
evaporation of liquids and drying of solids.
The UNC representatives showed a proposed administrative amendment to authorize on-site storage of dried solids in drums awaiting shipment for burial at an authorized licensed burial site. The accumulated inventory of U-235 in the drums would~ exceed the amount authorized in the waste treatment area under Amendment No. 4.
However, since the criticality safety basis (limited surface density) to be used would be the same as now authorized under the license, UNC expected the amendment to be adminit.trative. Mr. Crow explained that an administrative amendment cannot cover significant safety questions and hence UNC will have to submit the application as a minor safety amendment with a check for $1,400.
Calculations and measurements to be included in the. application indicate that the waste treatment process will have only a minor environmental impact so that UNC will continue to meet the current total release limit for airborne radioactivity (25 pCi/wk) with an adequate margin.
8 004.170 3R/
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D-b FEB 121980 2
It was suggested to the UNC representatives that the application include information supporting their conclusions on the maximum U-235 content and distribution in the solidified waste.
t"Md Robert L. Stevenson Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety i
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