ML20135G334
| ML20135G334 | |
| Person / Time | |
|---|---|
| Site: | 07105828 |
| Issue date: | 08/06/1985 |
| From: | Regan N BABCOCK & WILCOX CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25663, 85-113, NUDOCS 8509180427 | |
| Download: ML20135G334 (4) | |
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/0 8 Babcock & Wilcox u...i soci..,ru.ioivi. ion a McDermott company P. O. Box 785 August 6,1985 Lync.hburg, Virginia 24505 0785 (804) 522 6000
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U.S. Nuclear Regulatory Ccmnission Charles E. MacDonald, Chief
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m Gentlemen:
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he Babcock & Wilcox Cmpany, Naval Nuclear Fuel DivisioNrequests revision to Certificate of Compliance 5828 for shipping container USA /5828/B()P.
An increase in the U-235 maximm limit is needed for shipnents of higher loaded research reactor fuel cmponents.
Revise Section 5 (b)(2)(ii), last sentence, to permit total U-235 not to exceed 800 grams.
Nuclear safety for this increased limit is based on the J.T. Smas mmo, dated Novmber 8,1982, entitled Use of the " Treat Capsule Assembly Shipping Container for Transport of 'IWo ORR Shim Rods" (attached) indicates that two (2)
ORR elements with 400 grams maximum U-235 per elment are subcritical. %is mmo I
was further supported with reference to the " Safety Analysis Report for the Treat Capsule Assembly shipping Container", Ins Alamos Scientific Laboratory, IA-6606-MS (1976).
Wis change has been determined by B&W as a minor amendnent and a check for
$150.00 for the fee is enclosed.
If you need any additional information, please feel free to contact us at any time. We would appreciate any assistance that you can give us in expediting this endorsement.
Sincerely, BABCOCK & WIILOX, NNPD 8509100427 O N PDR ADOCK 0710Se2B ltv N. A. Regan Docurre Nuclear Safety & Licensing Officer UsN.7c A
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,t os November 8, 1982 Glenn Bowdon Bldg. 7910 a for Transport of Use of the "TPEAT Cnosuje Asserbiv Shippine Containcr
_Two ORR Shim Fods.
Reference Document:
" Safety Analysis Report for the TREAT Capsule Assembly Shipping Container," Los Alamos Scientific Laboratory, LA-6606-P.S (1976).
The inner container, as described in the above reference, will be codified by only the recoval of three oak blocks usc4 to position the two TREAT assemblics during transport.
The inner container is a 1-in thick plywood box, covered with 14 gauge steel, with an interior "T" beam spaccr-etiffener having a 0.5 c= thick cadmium lining on the top, bottom and sides of coe; art-monts formed by the "T" spacer.
Each fuel elecent would be separated from any other by the cadmium lining.
Nuclear criticality is not possibic, dr{,or subterced, with any numbcr of innce containers in any arrangccent, when the contents are two ORR fuel eletents (max 400 g 2ssU per elecent).
It follows that two ORR shl=
rods as centents would also result in s,'uberiticality and the transport index assigncent is zero (i.e., Fissile Class I package) for the shipping container.
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2 References 1.
J. K. Fox and L. W. 0111cy, " Critical Experiments with Arrays of ORR and BSR Fuel Elements," ORNL-2609, Oak Ridge National Laboratory (1958).
'2.
E. B. Johnson and R. K. Recdy, " Critical Expericents with SPERT-D Fuel Ele'monts," ORNL/T!!-1207, Oak Ridge National Laboratory (1965).
3.
J. T. Thomas, "nucicar Criticality Assesscent of Oak Ridge Research (Reactor) Fuel Element Storage, ORNL/CSD/111-58, Oak Ridce National Laboratory (1978).
11.
J. T. Thomas, " Nuclear Criticality Safety' Assessment of ORR, NBS, and HFBR Fuel Elecent Shipping Package," ORNL/CSD/Tli-77, Oak Ridge National Laboratory (1979).
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Ohbd>3 CONTROL NO, 8[/[bd6 DATE OF DOC.
Obh DATE RCVD, FCUF PDR_
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