ML20127D485
| ML20127D485 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 06/12/1985 |
| From: | Crow W, Ketzlich N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20127D445 | List: |
| References | |
| NUDOCS 8506240241 | |
| Download: ML20127D485 (3) | |
Text
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JUN 121985, DOCKET N0: 70-1100 LICENSEE: Combustion Engineering ,
FACILITY: Windsor, Connecticut
SUBJECT:
REVIEW 0F LICENSE APPLICATION DATED NOVEMBER 30, 1984 AND ITS SUPPLEMENT DATED APRIL 12, 1985
Background
Combustion Engineering, Inc., (CE), by application dated November 30, 1984, requested authorization to add-1,000 g of contained U-235 in " residue" enriched to 220 weight percent U-235. Currently CE's license is limited to <20 weight percent U-235.
CE recently discovered a small quantity of uranium enriched to approximately 80 percent U-235 which was left as a residue in their Building #3 industrial waste line. This line was part of the original building when the building was used in the late 1950's for the fabrication of highly enriched fuel assemblies
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for the naval reactor program. In addition, some high-enriched uranium material was found in the radwaste line which connected Building #6 to Building #3 (when Building #3 was used to fabricate the highly enriched fuel assemblies).
To dispose of the known quantity of highly enriched material found in the tanks and pipe, CE plans to collect, dry, package, and ship it to Barnwell, South Carolina for burial. All collecting, handling, packaging, and disposal of the material will be in accordance with existing licensing and regulatory requirements.
In order to eliminate the possibility of being out of compliance in the future if additional similar residues are found, CE requests authorization to possess residues enriched to 320 weight percent U-235. In addition, CE states the residues "from prior operations" will not exceed 350 g contained U-235 in any one location with additional locations separated from each other by a minimum of 12 feet.
In a supplement dated April 12, 1985, to the Fuel Facility SG Licensing Branch, Division of Safeguards, Office of Nuclear Material Safety and Safeguards, CE submitted the procedures to be followed covering the collection, accountability, security, and disposal of 320 weight percent U-235.
Discussion 62go g % o A. Nuclear Criticality Safety C l
i As far as nuclear criticality safety is concerned, there is neither a l criticality problem with a maximum of 350 g contained U-235 at one location
! or with a minimum separation of 12 feet between 350 g quantities. The 350 g l " batch" is no more than 45*.' of the minimum critical mass independent of I
2 JUN 121985 container size, the degree of water moderation, or reflection. The minimum distance of 12 feet between adjacent 350 g batches is sufficient to isolate them from each other. However, CE's request goes beyond its intent to handle and dispose of residues they may find on their property that contain
>20 percent U-235. The request is for a blanket authorization to possess 350 g quantities of U-235 at 3 separate locations (separated by at least 12 feet). If the request is to cover the " unknown", there can be no guarantee that future " discoveries" will be found that are at least 12 feet apart.
To strengthen administrative controls, cover future discoveries such as the above, and ensure timely management action to remove the material from CE property, Conditions 23 and 24 are recommended:
Condition 23. Upon discovery of residues at the licensed facility containing uranium enriched to 320 wt percent U-235, action shall be initiated within 30 days to remove the material from the premises in a timely manner.
Condition 24. Notwithstanding the statement made in Section 1.6 of the application dated November 30, 1984, the licensee shall separate the residues in batches no larger than 350 g contained U-235 and shall maintain a minimum separation of 12 feet between batches.
With the addition of Conditions 23 and 24, the staff recommends to authorize CE to add 1000 g contained U-235 in the form of residues found whose enrichment is 320 w/o U-235.
B. Radiation Safety The cellecting, handling, packaging, and disposal of the material will be in accordance with existing licensing and regulatory requirements. Therefore, radiation protection of personnel and facilities are assured.
C. Environmental Protection There is no requested change to the environmental protection requirements of the facilities. None are required since neither the materials handled nor the minimal quantity of additional effluents produced will add to the types and quantities previously authorized. In accordance with 10 CFR 51.22(c)(11), neither an Environmental Assessment nor an Environmental Impact Statement is not necessary for this proposed action.
Physical Security and Accountability The Fuel Facility Safeguards Licensing Branch reviewed the procedures submitted by CE letter dated April 12, 1985, that covered the collection, accountability, security, and disposal of material enriched to 320 weight percent U-235.
Safeguards approved the procedures by letter dated May 24, 1985.
3 JUN 121985 General The amendment application dated November 30, 1984, was discussed on May_31, 1985 with Mr. Jerome Roth, Region I Inspector of the facility. He foresaw no safety or environmental problem with the requested authorization, subj ;t to the proposed licensed condition.
Conclusion .
Issuance of the amendment allowing the possession and disposal of residual quantities of U-235 enriched to 320 percent U-235 is recommended subject to the following conditions:
Condition 6 G. Uranium enriched 320 w/o U-235 Condition 7.G. Residue Condition 8.G. 1000 grams of contained U-235 Condition 23. Upon discovery of residues at the licensed facility containing uranium enriched to 320 wt percent U-235, action shall be initiated within 30 days to remove the material from the premises in a timely manner.
Condition 24. Notwithstanding the statement made in Section 1.6 of the application dated November 30, 1984, the licensee shall separate the residues in batches no larger than 350 g contained U-235 and shall maintain a minimum separation of 12 feet between batches.
Norman Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS Approved by:
W. T. Crow, Section Leader
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OFFICIAL RECORD COPY