ML20006E622
| ML20006E622 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/14/1990 |
| From: | Wilson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Winslow T GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9002260144 | |
| Download: ML20006E622 (3) | |
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FEB 141990 ~
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' Docket No. 70 1113
' License No. SNM.1097 i
General Electric Company ATTN: 'Mr. T. Preston Winslow Manager Licensing and Nuclear Materials Management, M/C J88 P.O. Box 780 Wilmington, North Carolina-28402 l
1" Gentlemen:
. We have reviewed your application dated November 9,1989, and will require additional information in support of the amendment application to use the Uranium Recovery from Lagoon Sludge (URLS) facility. The additional information, identified in the enclosure, was discussed with you on February 8,1990.
In your amendment request you submitted a new Section 1.8.13 " Exemption &
e Special Authorizations" which requested special authorization for the URLS project facility. Section 1.7.3 of the current license should be expanded to authorize nitrate sludge processing and Section 1.8.5 should be revised, as appropriate, to acconnodate the disposal of process residues. Accordingly, the proposed new Section 1.8.13 should be deleted from this amendment request. -
We will continue our review upon receipt of the requested information.
If you have any questions. please call me on (301-492-0126).
Sincerely, t
Mk Robert E. Wilson Uranium Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS i
Enclosure:
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i LETTER T. P. WINSLOW TO L. C. ROUSE DATED NOVEMBER 9, 1989 SAFETY-RELATED QUESTIONS ON CHAPTER 5 Please provide information in response to the following questions. Proposed license conditions, as appropriate, should be provided in Part I.
L 5.1.1 Sludoe queue L
5.1.1.1 What is the history of additions to the sludge basins? (What quantities ha e been added and at what enrichments?)
What were the referenced measurements? How many samples were ta ken? How were they analyzed? What is the range of results and what is the standard deviation?
What is the minimum critical concentration taken to be (on what basis)? How is the expected range of concentrations and enrichment determined, and how does this relate to minimum critical concentration (M.C.C)? Is there a confidence criteria for the M.C.C? Was the sampling program adequate to support confidence criteria?
5.1.1.2 What is the program for queue tank sampling? How will tanks be representative 1y sampled? What is the confidence criteria for sampling? What will be the criteria for enrichment determination?
Is double batching considered credible? If not, on what basis?
5.3.2 Leach and filtration 5.1.2.1 Uranium concentration in leachate may increase. What are the controls to limit concentration to 4.2.1.3 criteria?
5.1.2.2 Have the referenced plumbing controls had a rigorous safety analysis? If so, provide summary of results.
5.1.3 Solvent extraction How do " batch" controls interface with continuous process controls?
5.1.3.1 What is the initial assumption on enrichment to set equipment geometries, or what is the limit on enrichment if the geometry is controlling?
5.1.3.2 How will the referenced chemical controls be administrated?
What are the controls to assure that they will not be defeated?
5.1.3.3 Does the sampling control have common mode failure possibilities?
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b 5.1.4 Precipitation 5.1.4.1 What is the assumstion of enrichment for sizing, or what' is the-limit on permissi>1e enrichment?
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5.1.4.2 What assumptions are used for the safe mass conclusion? Provide t
I information on constraints which will enforce the concentrations
. assumption.
p 5.3.2 Chemical Safety l
Provide more information 'on safety controls for storage and handling of significant quantities of concentrated acid.
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From the detailed safety (What is the set of criticality scenarios?) a each criticality risk.
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What are the barriers to prevent each scenario?
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What are the criteria for the quality of these barriers?
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