ML19337B229
| ML19337B229 | |
| Person / Time | |
|---|---|
| Site: | 07105957 |
| Issue date: | 08/25/1980 |
| From: | Burian R Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19337B230 | List: |
| References | |
| 17263, NUDOCS 8010010645 | |
| Download: ML19337B229 (2) | |
Text
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@Baffelle m-Columbus Laboratories 505 King benue Columbus, Ohio 43201
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Mr. Charles E. Mcdonald Transportation Certification Branch 5"
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Division of Fuel Cycle and Material Safety U. S. Nuclear Regulatory Commission NM55 Washington, D.C.
20555 MAIL SECTICR S
DOCKET CLETOC
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Dear Mr. Mcdonald:
g Docket No. 5957, certificate of Compliance
_ for the Model BMI-1 Shipping Cask Battelle's Columbus Laboratories requests an amendment to the subject Certificate of Compliance for the transport of process uranium oxide powder in the BMI-l cask. The powder is a recovery product of the Union Carbide Corporation's Medical Products Division.
In support of this request we are enclosing eight (8) copies of replacement pages for the Safety Analysis Report for the Model BMI-l Shipping Cask.
The replacement pages
' dress the use of a specially designed Union Carbide process uran. m oxide container and a special form capsule proposed as the containment vessel for the uranium oxide.
Both of P.hese containments will be transported in the existing BMI-l cask and baskets. We request that the amendment specifically oermit the j
following:
235
- 1) Transport of up to 352 grams of U in oxide form in each of the twenty-four (24) process containers described by Union Carbide Corporation Drawing No. 101501, Rev. O.
The maximum decay heat load per capsule is 20 watts.
2)
Transport of a mixture of Union Carbide process containers (maxi-mum of 352 grams of U235 in oxide form) and MTR type fuel elements in any proportion up to a combined total of twenty-four (24). The MTR type fuel elements shall comply with the specifications for MTR type fuel elements stipulated by Revisior. 6 of the subject Certificate of Compliance.
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50 Years Of Senice 1929-1979 17263 804001 g
v-h Mr. Charles E. Mcdonald 2
August 25, 1980
- 3) Transport of up to 100 grams of U in oxide form in each of twenty-four (24) special form capsules. The decay heat load per capsule may vary.
However, the combined heat load of all capsules may not exceed 1500 watts (rating of the BMI-l cask).
- 4) During transport, the three types of contents described above will be securely confined in the existing BMI-l baskets so as to preclude secondary impacts during accident conditions of transport.
The fee for your review of this application was sent to you on July 14, 1980, by Mr. Marcus H. Voch, Manager, Nuclear Operations, Union Carbide Corporation.
A copy of his letter is attached for your reference.
Also attached is an index of the replacement pages indicating the safety related features of the changes. All replacement pages are identified by the legend "Rev. B. 8-1-80" centered on the bottom margin.
If only part of the text on any one page is changed, that part is identified by a vertical bar in the outside page margin opposite the revised or added material.
If the entire page is revised or added, no bar is used.
If you have any questions concerning this application, please telephone me at FTS 976-7502.
Sincerely, W
s5 Richard J. Burian Principal Research Engineer Nuclear and Flow Systems Section RJB/llj Enclosures (10) cc:
Mr. Marcus H. Voth, Manager, UCC 9
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Mr. Charlen E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Materr.als safety U.
S.1;uclear Regulatory Ccmmission Washington, D.
C.
20555 l
Re:
Recuest for Amendmeat to Certificate of Compliance 5957
Dear Mr. MacDonald:
Union Carbide hereby requests that Certificate of Compliance 5957 for the Model BMI-1 shipping cask be amended to include in the con'-
l tents approved for shipment, containers of irradiated fissile target material.
This material, which is the end product of our process for l
irradiating and separating medical radicisotopes, has been disposed of as radioactiite waste in the past.
In the future we will recover the material and ship it to a reprocessor.
The centainers we propese to use are of similar materials, dimensions, and materials as MTR fuel elements which are already ap-proved for the BMI-1 shipping cask.
The same baskets can be ured as are already designed fabricated and licensed.
We have engaged Battelle Columbus Laboratories, the primary licensee of the cask, to perform a safety analysis of the differences between the propcsed and already approved contents.
The safety analysis will be sent to you directly by Battelle in early August.
Since we will be shipping spent reactor fuel in the BM1-1 shipping cask during the month of September we ask that the license be amended as soon as possible to allow us to make cur first shipment cf reclaimed target material in September while we have the cask.
I This matter has been discussed with Pr. Richard odegaarden cf your staff some weeks age.
In an attempt to expedite matters we are filing the license amendment fee at this time to avoid any delay when.
the safety analysis is available to you.
Attached you will find a check for $2,800.00 to cover the fee for a minor amendment to Certifi-cate of Compliance 5957.
Yours very t_mly, I
M.HV:ltm Marcus H. Voth l
l Manager Nuclear Operations
' cc: 'Mr. Richard J. Burian - Battelle Mr. Richard Cdegaarden - NRC N
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