ML20054C732
| ML20054C732 | |
| Person / Time | |
|---|---|
| Site: | 07109156 |
| Issue date: | 03/23/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Gaines T INDUSTRIAL NUCLEAR CO. |
| References | |
| NUDOCS 8204210574 | |
| Download: ML20054C732 (3) | |
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DTHuang MAR 2 31982 Docket File LLGordon NRC PDR FCTC: RHO IE HQ (3) 71-9156 FESS R/F FCTC R F NNp v,y
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Industrial Nuclear Company ATTH: Mr. T. M. Gaines
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Foster City, CA 94404
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Gentlemen:
'k This refers to your application dated December 23, 1981, requesting approval of the Model No. IR-50 packaging.
Thequalityassurance(QA)programsubmittedandapprovedbyNRC(No.0062) is limited to procurement of packages, maintenance, and use.
Prior to your submittal of the additional infomation requested by the enclosure to this letter, we need an application for a QA program which addresses design and fabrication. Annex 1 of the enclosed draft QA guide may assist you in preparing the application.
Please advise us within thirty (30) days from the date of this letter when this information will be provided. The additional package infomation requested by this letter should be submitted in the fom of revised pages.
If you have any questions regarding this matter, we would be pleased to meet with you and your staff.
Sincerely, Original Signed by CluJ' n.S E. MACD31%
J Charles E. MacDonald, Chief I
Transportation Certification Branch Division of Fuel Cycle and Material Safety. NMSS
Enclosures:
1.
Request for additional infomation 2.
Draft QA Guide f
8204210574 820323 PDR ADOCK 07109156
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OFFICIAL RECORD COPY
e Industrial Nuclear Company Model No. IR-50 Docket No. 71-9156 i
Enc 1 to ltr dtd: MAR 2 3 1982 GENERAL 1.
Drawing No. 50-2, Rev. O, should be deleted since the source changes must be within the overpack as presented for transport.
2.
The use of Model No. 50 has been previously assigned. Please indicate whether Model No. IR-50 is acceptable to you, or assign some other unique model number.
DRAWINGS 1.
Provide an engineering drawing of the source changer showing the general arrangement of the package, weld sizes, dimensions, materials of construction, connection of the lock box to the case, positioning of the shield within the case, etc.
2.
It is not apparent how the device and overpack will relieve pressure buildup as a result of the decomposition of the foam potting material j
for the themal test. A positive means for pressure relief and the possible repositioning of the shield in the case in the absence of the foam potting material should be addressed.
3.
Drawing No. 50-4, Rev. O for the overpack should be dimensioned; the specifications for the 10-gallon drum and bolt closure ring should be specified.
STRUCTURAL A discrepancy is noted between the insert tested (Dwg 50-1) and the insert for which approval is requested (Dwg 50-3 and 4).
It is also noted that the application states that the 30-foot drop test was conducted through the center of gravity on the locking ring closure, however Dwg 50-3 indicates that a top drop was conducted.
The above discrepancies should be clarified. Also, justify that the orientation chosen for the 30-foot drop test represents the most damaging orientation, i.e., what effect would side, bottom, or bottom corner drop i
have on the wooden inserts and the lock box.
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OFFICIAL RECORD COPY
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.. SHIELDING We require a ganna dose rate profile on the surface of the package (containing a specified curie content of IR-192) before and after the accident sequence demonstrating no substantial change in these readings.
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