ML20054K915
| ML20054K915 | |
| Person / Time | |
|---|---|
| Site: | 07105595 |
| Issue date: | 06/24/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Prichard R ENERGY, DEPT. OF |
| References | |
| NUDOCS 8207060283 | |
| Download: ML20054K915 (2) | |
Text
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Distribution: w/enci Docket file 7 NRC PDR IE HQ Region I JUN 2 4 IS82 WHLake DTHuang FCTC:WHL NMSS R/F /kw /o 71-5595 FCTC R/F gjp,c[f]
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U.S. Department of Energy ATTN: Mr. Reuben P. Prichard MS-E-201 Washingon, DC 20545 s
Gentlemen:
This refers to your letters dated August 3,1978 and July 8,1981, requesting our review of the Model Nos. L and M packages.
In connection with our review of these packages, 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, Original signed by CuMES E "C**UA'*-
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, MMSS
Enclosure:
As stated cc w/ encl:
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OFFICI AL.. RECORD, COP _Y____
A. '
Request for Additional Information Model Nos. L and M Docket No. 71-5595 Encl to ltr dtd: JM 2 41982 STRUCTURAL For a side drop orientation, the Model L relies on the closure bolts, stainless steel welds, and uranium welds to prevent lid separation. The total load bearing capacity of these three components is calculated to 6
6 be 3.29x10 lbs. The applied load on the lid is calculated to be 3.17x10 lbs. for the side drop. The uranium weld accounts for approximately 17%
of the load-bearing capacity. The application assumes that uranium welds are as strong as the base material; however, no justification of this is given. We need information which justifies that the uranium weld strength will be as presented in the application. This should also include assurance that the weld strength reflects weldability, and is for uranium having the same physical and chemical properties as used in the package.
CONTAllMENT I
1.
Containment capability for the packages cannot be demonstrated without first establishing a containment criteria. Regulatory Guide 7.4 may be used to establish a containment criteria.
2.
The DOT Specification 2R container tested (Appendix C, ORNL/ENG/TM-4) is not the container specified in Section 1.9.
The specific container design used to provide containment for normal form material must be identified and shown to satisfy the containment criteria established.
TESTING AND MAINTENANCE 1.
Verify that the air bubble, vacuum, and glycol leak test proposed for special form and DOT Spec 2R containers prior to each use i
satisfies the established containment criteria.
sitivity reported for the proposed leak test (i.e.,1x10-6 2.
The seg/sec) is better than nominal values geported for the air ata-cm 3
bubble, vacuum and glycol test (e.g., lx10~ atm-cm /sec, ANSI N14.5). Provide justification for the higher sa-sitivity reported.
DATEf
""C' OFFICIAL RECORD COPY
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