ML19341C707
| ML19341C707 | |
| Person / Time | |
|---|---|
| Site: | 07000687 |
| Issue date: | 12/15/1980 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8103031108 | |
| Download: ML19341C707 (2) | |
Text
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tv K MORANDUM FOR:
W. T. Crow, Section Leader
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Uranium Process Licensing Section 5
FEB 091981 = si Uranium Fuel Licensing Branch g.- Mu ymm j 4
FROM:
N. Ketzlach Uranium Process Licensing Section kt
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Uranium Fuel Licensing Branch b q;g \\
SUBJECT:
UNION CARBIDE FACILITY SITE VISIT TO REVIEW FUEL HANDLING OPERATIONS RELATED TO LICENSE N0. SNM-639 (DECEMBER 10, 1980)
Purpose To review the fuel handling operations of the Union Carbide facilities related to their SNM license which is now subject to renewal.
Place and Date Union Carbide facilities at Tuxedo, New York, December 10, 1980.
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Discussion As project manager of the Union Carbide (UC) facility in Tuxedo, New York, A. T. Clark made a site visit in preparation for the review of the UC license renewal application (separate report to be prepared by Clark).
I accompanied him on December 10, 1980, to become more familiar with the fuel handling activ-ities and particulary with the nuclear criticality safety of the operations.
The principal UC attendees during my visit were the following:
1.
M. H. Voth, Manager Nuclear Operations 2.
D. D. Grogan, Hot Laboratory Supervisor 3.
F. J. Morse, Process Engineer I reviewed the operations from receipt of the target U 0 powder, preparation I
of the targets, uranium dissolution after irradiation,3 ptne uranium waste form l
processing and the w.< aging of the uranium wastes. The processing is a batch operation involving single targets (615 g2350/ target) and multiple groupings of' target materials as solids or in solution. A good understanding of the operations and their locations within the facility was obtained.
1 UC has submitted an amendment application dated D'ecember 5,1980 (which had i
not been received by the date of the site visit) requesting an exemption from i
the 70.24 (a) criticality alarm requirements. The application was discussed and the operation of the current criticality monitoring program reviewed.
It appears that justification for the exemption has not been provided.
A more 4
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detailed review of the application will be made after its formal receipt by the NRC.
The site visit should provide good background informaticn for our
'eview.
Conclusion The site visit was very useful in providing a better understanding of the UC operations and should help in the review of the renewal application and requests for license amendments.
f) jf is L we Norman Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch 5