ML19263B103
| ML19263B103 | |
| Person / Time | |
|---|---|
| Site: | 07109506 |
| Issue date: | 12/18/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Mott W ENERGY, DEPT. OF |
| References | |
| NUDOCS 7901050089 | |
| Download: ML19263B103 (3) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMisslON h
j W ASHINGTON, D. C. 20555 o
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U. S. Department of Energy ATTN: Dr. William E. Mott Washington, DC 20555 Gentlemen:
This refers to your letter dated December 30, 1977, requesting our review of the Model No. MS27684-2 package.
In connection with our review of the subject package, we need the infomation identified in the enclosure to this letter.
Please advise us when this information will be provided.
Sincerely, Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated cc: DOE, Albuquerque Operations Office ATTN: Mr. Jack R. Roeder P.O. Box 5400 Albuquerque,NM 87115
[O/056t87 C
c Model No. MS27684-2 Shiocing Container Encl to ltr dtd: CEC I g 7079 DRAWINGS Provide Mound Research Corporation Drawings Nos. AYC 760065 and AYC 760064 for the inner container body and cove".
These drawings should identify all significant safety features, e.g., dimensions, materials of construction, welds and seals.
CONTAINMENT Show that the containment capabilities of the packaging fo!)owing normal conditions of transport and accident damage conditions are sufficient for packaging containing plLtonium oxide powder.
Regulatory Guide 7.4 may be used to develop an acceptable test to demonstrate adequate con-tainment. Also, the application should address how the requirements of 10 CFR 571.42 will be met.
TESTING AND MAINTENANCE DiscLss the maintenance program to be used to ensure the package contain-ment capability under continued use. This should include initial, periodic and preshipment tests. The maintenance schedule should include the inspection, test and replacenent schedule for components that comprise the containment system.
Regulatory Guide 7.4 may be used for containment tests before first use and for periodic testing.
For assembly verification testing, it is recornded that a test of sufficient sensitivity to detect a release of no more than a Type A quantity of material in 10 days be used. When leak testing is used for assembly verification the maximum sensitivity 3
is 1 x 10~3 atm-cm3/sec and the cinimum sensitivity is 1 x 101 atm-cm / rec (air at 25"C and 1 atm leaking to a 1 x 10 2 atm ambient).
CRITICALITY In order for any package to qualify as Fissile Class I it is necessary to demonstrate that the requirements of 10 CFR 571.38 are met.
In practice, Fissile Class I indicates that controls for criticality in transport are not required. This is possible since there is essentially no neutron interaction between packages under normal conditions of transport and at least 250 damaged packages are subcritical.
It should
" be recognized that Fissile Class I packages could be commingled with other Fissile packages.
In the case of the subject package it has not been shown that any number (infinite array) of packages are subcritical for the normal conditions of transport.
In this regard, we need a description of the criticality model and analysis and results which support a Fissile Class I designation. Also, it should be noted that the Transport Index for Fissile Clcss II should be rounded up to the first decimal place in accordance with 10 CFR 571.39(2)(b).
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