ML20246F668
| ML20246F668 | |
| Person / Time | |
|---|---|
| Issue date: | 06/26/1989 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8907130345 | |
| Download: ML20246F668 (2) | |
Text
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UNITED STATES j
8 NUCLEAR REGULATORY COMMISSION o
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- E; W ASHINGTON, D. C. 20555 JUN 2 6 680 MEMORANDUM FOR
- Leland C. Rouse, Chief Fuel Cycle Safety Branch Division'of Industrial and Medical Nuclear Safety FROM:
John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety
SUBJECT:
THE 9th INTERNATIONAL SYMPOSIUM ON THE PACVAGING AND TRANSPORTATION OF RADI0 ACTIVE MATERIALS (PATRAM '89)
DATE/ TIME:
June 11-16, 1989 5:00 p.m.
LOCATION:
Crystal Gateway Marriott Hotel, Arlington, VA ATTENDEES:
Registrants PURPOSE:
As stated under the subject heading above.
DISCUSSION:
Many of the matters involving transportation of spent fuel in casks are common to storage of spent fuel in casks. For example, presentations on structural, thermal, shielding and criticality issues were of equal interest. Charles Marotta, recently retired from NRC, asked me to present a paper sponsored by NRC's Transportation Branch for him due to an illness. I agreed and presented his paper on burnup credit allowance in criticality design and consequences of a criticality excursion.
Other papers of interest concerned ductile cask iron. Of particular interest Wds the Japanese test drop of a loaded approximately 100 ton ductile cast iron F
cask described in the paper entitled, " Full-Scale Tests and Evaluation for Quality Assurance of Ductile Cast Iron Casks." While I was unable to hear the presentation of this paper because it coincided with the session in which I presented Marotta's paper, the following day June 15th, I was able to see a videotape of the test activities. The cask body was deliberately flawed (see Fig. 9, in the Enclosure) for the 9 meter drop tests.
Nuclear Assurance Corporation (NAC) also made a presentation on the NAC S/T cask. A variation on this design is to be submitted in September to us for storage design approval and to the Transportation Branch in January 1990 for Part 71 certification.
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2-Also of. interest was an Ontario Hydro' presentation on the development of a concrete transportation / storage cask.- Slides of scale-model drop tests were-
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