ML19290B688
| ML19290B688 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 10/23/1979 |
| From: | Crow W, Stevenson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19290B671 | List: |
| References | |
| NUDOCS 7912130527 | |
| Download: ML19290B688 (2) | |
Text
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[*g UNITED STATES g
NUCLEAR REGULATORY COMMISSION 3
j WASHINGTeN. D. C. 20555
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OCT 2 31973 DOCKET NO.:
70-1151 LICENSEE:
Westinghouse Electric Corporation (UEC)
FACILITY:
Uranium Fuel Fabrication Plant Columbia, South Carolina
SUBJECT:
REVIEW 0F LICENSE AMENDMENT APPLICATION DATED SEPTEF.BER 3,1979, FOR AUTHORIZATION TO CONSTRUCT AND USE A WASTE STORAGE BUILDING, PC NO. 79109A, MC
Background
By application dated September 3,1979, Westinghouse Electric Corporation (WEC) requested an amendment to SNM-1107 to authorize construction and use of a Waste Storage Building. The approximately 44 ft wide by 120 ft.
long building will provide some shelter for storage of low level wastes and equipment contaminated with uranium. The building is to be located in the area of the site where the packaged, contaminated wastes are now stored in the open. No uranium in dispersible form will be permitted in the building; contaminated items will be protected or containerized to prevent dispersion.
In addition to the storage use, about one half of the building will be used for activities associated with waste disposal, such as container loading, vehicle loading and unloading.
The application for authorization to construct and use the Waste Treatment Building and authorizing license amendment were discussed with Mr. G. P. Coryell, Region II principal inspector for the WEC plant, in a telecon on October 15, 1979.
Discussion Radiological Safety Since the items to be stored in the building will usually come from the main plant, they will have been surveyed for radioactivity prior to release in accordance with the license requirements.
Furthermore, the WEC radiation protection function will conduct surveys to assess the effectiveness of the contamination controls. As noted in Background, no uranium in dispersible form will be handled in the building.
1553 212 529 912130 4
2 C C I 2 3 n j'j Nuclear Criticality Safety Containerized materials will be limited to a maximum of 350 grams U-235 per container and a maximum concentration of 5 grams U-235 per cubic foot. These requirements, except for one detail, meet the exemption for fissile material given in 10 CFR 71, paragraph 71.9(e). The reference exemption requires that there not be more than 5 grams fissile material in any cubic foot.
Contaminated items will be visually inspected to be certain that no signifi-cant accumulation of radioactive material is present.
Environmental Imoact Based on the facts sumarized below, the installation of the Waste Storage Building should leave the total comitted land area well below that con-sidered (approximately 57 acres comitted to the plant areas) in the Westinghouse Environmental Evaluation.
The building installation will involve excavation and pouring of a concrete slab of approximately 6,000 square feet and relocation of a dirt access road approximately 20 feet east from its present location.
The proposed Waste Storage Building will provide improved control in the disposition of the low level wastes and further minimize the potential for release of radioactivity into the environment.
The area will be subject to routine surveillance by the WEC radiation protection function, including taking and analyzing smear samples to detect possible contamination in the area. Any water accumulated on the slab will be collected in sumps which drain to the adjacent storage lagoon.
Conclusion and Recomendations Based on the safety and environmental impact information summarized in the foregoing " Discussion," it is concluded that the proposed Waste Storage Building can be constructed and used as described without undue risk to the health and safety of the operating staff or the public, and without significant environmental impact, subject to the following condition:
Notwithstanding the wording concerning nuclear criticality safety in the enclosure to the letter dated September 3,1979, containerized materials shall be limited to a maximum of 350 grams U-235 per container and there shall not be more than 5 grams of U-235 in any cubic foot within a, container.
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CPW R. L. Stevenson Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety
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Approved by:
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W. T. Crow, Section Leader