ML19318C113
| ML19318C113 | |
| Person / Time | |
|---|---|
| Site: | 07000687 |
| Issue date: | 05/22/1980 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Voth M UNION CARBIDE CORP. |
| References | |
| NUDOCS 8006300682 | |
| Download: ML19318C113 (2) | |
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NUCLEAR REGULATORY COMMISSION
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MAY 2 21980 FCAF: LR Docket No.70-687 9
Union Carbide Corporation ATTN: Mr. Marcus H. Voth, Manager Nuclear Operations P. O. Box 324 Tuxedo, New York 10987 Gentlemen:
This refers to your application of April 2,1980 requesting amendment of Special Nuclear Material License No. SNM-639 to authorize modifications to the existing waste, handling process. On May 15,1980 Messrs. J. J. McGovern, F. J. Norse and M. H. Voth of Union Carbide met with Dr. A. T. Clark, Mr. R. L. Fonner and myself of the NRC to discuss this application.
Prior to the meeting we questioned whether the additional processing steps would place your hot cell irradiated fuel activities outside the scope of the exception defined by Section 50.2(a)(3)(iii) of 10 CFR Part 50.
The description and clarification provided by your representatives at the meeting on the proposed processing steps for conversion of the present sulfate waste stream to an oxide form resolved this question, and we have concluded that your operations will continue to meet the provisions of Section 50.2(a)(3)(111).
l As further discussed during the meeting, our review has revealed the need for additional information to support your application. Accordingly, please provide responses to the following items as a supplement to your application:
1.
Provide a more detailed description of the waste form conversion process and process equipment.
Include a description of any off-gas treatment from the drying and calcining steps and a description of the ventilation-exhaust system which serves the process cells and their operating areas.
Describe the radiological monitoring and the control instrumentation for the system l
including alarms and their locations.
2.
provide an evaluation of the airborne effluents that may be released as a result of the additional processing steps including projected concentrations
.and quantities of individual radionuclides and the basis for your determina-tion that these releases are as low as reasonably achievable (ALARA). This evaluation'should provide a sufficient description of the effluents resulting from present operations to establish any incremental increases attributable to the proposed additional processing steps. The evaluation should provide particular focus on volatile and semi-yolatile fission products present in the waste stream, e.g., iodine, ruthenium and cesium.'
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provide an evaluation of potential offsite radiation exposures including the dose to the nearest (critical) resident. Again the evaluation should provide a sufficient description of the present situation to permit assess-ment of the incremental impact of adding the proposed processing steps.
Include a description of the dose assessment methodologies used in your 3
evaluation in sufficient detail to permit confirmation of your calculations.
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Provide your analysis of the credible accidents which could occur with the waste form conversion process, discussing mitigating factors, such as engineered safety equipment, which may alleviate the consequences. The analysis should present estimates for both onsite and offsite radiological exposures which may result from the event (s).
5.
Assess the incremental occupational exposure that may accrue from the added processing steps, if any, and the basis for your dete'rmination that such exposures are ALARA.
6.
Describe a detailed start-up plan that provides a basis for assessing the performance of the process and equipment and to verify the safety of the operation.
If you have any questions regarding this matter, please let me know (301-427-4205).
Sincerely, W
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Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety 4
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