ML20051X338

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Forwards Request for Addl Info to Complete Review of ORNL Foamglas Package,Per 810724 Request.Response Should Be Submitted within 30 Days
ML20051X338
Person / Time
Site: 07105795
Issue date: 05/05/1982
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Ross D
ENERGY, DEPT. OF
References
NUDOCS 8205180138
Download: ML20051X338 (2)


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MAY 0 51982 Region I

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Washington, DC 20545 4V 12 Gentleren:

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This refers to your letter dated July 24, 1981 requesting ou

" of the Model No. ORNL Foamglas package.

In connection with our review of this package, we need the information identified in the enclosure to this letter.

Please advise us within thirty (30) days from the date of this letter when this information will be provided.

Sincerely, 0%# jh.

crisi Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, HMSS

Enclosure:

As stated cc w/ enc 1:

DOE, Oak Ridge Operations Office ATTN: Mr. William H. Travis P.0 Box E Oak Ridge, TN 37830 8205180F5%

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I NRC FORM 318 00 80) NRCM 0240 OFFICI AL RECORD C OPY

U.S. De artment of Energy Model to. ORNL Foamglas Docket No. 71-5795 Encl to 1tr dtd: MAY 0 51982 DRAWINGS Provide engineering drawings and specifications of the containment vessel (DOT Spec 2R) and the separate inner container required for I

plutonium in excess of 20 C1 (10 CFR 571.42).

STRUCTURAL 1.

Evaluate the performance of the seal ring bolt for the 30-foot drop test. The consequences of bolt damage, if any, for a drop onto the bolt must be considered in terms of any reduction in package effectiveness.

2.

Identify the orientations for the puncture tests. Justify that they represent the most damaging orientation. What effect would puncture impact onto the plywood disk have on the package?

CONTAINMENT 4

1.

Establish a containment criteria based on consideration of the package contents, and normal and accident conditions of transport.

Regulatory Guide 7.4 may be used.

2.

Show that the package satisfies the established containment criteria following normal and accident condition tests of 10 CFR Part 71.

3.

Show that the requirements of 10 CFR 571.42 are satisfied for plutonium shipments in excess of 20 C1.

OPERATING PROCEDURES, TESTS, AND MAINTENANCE Show that the sensitivities and testing schedules are adequate for safe use of the packages. Regulatory Guide 7.4 may be used for periodic testing. For assembly verification it is recommended that a test of sufficientsensitivitytolimitthemaximumreleasetoatypeAquantity in 10 jays is used, however, a leak test sensitivity greater than 1x1{

ata-cm /sec (air at 1 atm and 25'C leaking to a 10 gsitivity of 1x10~

atm-cm /sec, would not be required. The minimum se 3

at ambient) as i

specified in ANSI N14.5 should be met.

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