ML20034A792
| ML20034A792 | |
| Person / Time | |
|---|---|
| Site: | 07109226, 07109227 |
| Issue date: | 04/18/1990 |
| From: | Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9004240297 | |
| Download: ML20034A792 (2) | |
Text
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io UNITED STATES l'
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APR 181990 SGTB:NLO 71-9226,71-9227 MEMORANDUM FOR:
The Files FROM:
Nancy L. Osgood, TB/SGTR/NMSS
SUBJECT:
. MEETING
SUMMARY
CONCERNING GENERAL ATOMICS LEGAL
' WEIGHT TRUCK CASKS Attendees E
E M
Ross Chappell (Human Factors Maria Koploy Dan Huang Portion Only)
Richard Meyer Henry Lee John Cook-Larry Pickering Nancy Osgood John Jankovich Li Yang Chuck MacDonald EGM Dennis Serig Tom Bridges DOE-HO Ray Chapman Bill Lake Weston Mel Jensen 1
Meraj Rahimi DOE-Idaho introduction A meeting was held at the request'of General Atomics (GA) at-Rockville, Maryland, on March 21, 1990,. to discuss the GA-4 and GA-9 spent fuel. shipping casks. The GA-4 (4 PWR assemblies) and the GA-9..(9 BWR. assemblies) are-being designed by GA for the Department of Energy for spent fuel shipment by truck--
under the Nuclear Waste Policy Act. These casks are.in the final design-phase.
Discussion 1.
Structural analysis of fuel basket.
j Structural analysis of fuel support structure and the cavity liner'was I
discussed. The GA-4 and GA-9 have similar basket structures.
Because the GA-4 basket is the most limiting case structurally, the discussion ~
centered on the GA-4 basket.
~
The fuel support structure is a cruciform structure made of stainless steel plate. Cores of B4C neutron poison _ are inserted in holes drilled
-j in the plate. The tolerances required in fabricating the basket structures are small.
Tolerances will be considered when performing structural analyses of the baskets, i
The tips of the cruciform structure are captured in shallow keyways in the cavity liner.
It was suggested that the interface be modified 'to ~
allow a larger overlap between the fuel support structure and the cavity liner.
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2 2-The structural analysis was performed using two loading cases:
a uniform loading due to the fuel distributed uniformly over the area of the' assembly and a concentrated load case where the fuel load is distributed only on the fuel element spacer grids.
The fuel support structure is designed so that buckling cannot occur.
The loads considered were the depleted uranium shielding, fuel, fuel support structure, and cask bending.: Maximum normal operating. pressure -
(MN0P) was also considered for the cavity liner.
It was recommended
-that asymmetric loads due to partially filled casks, cavity pressures other than MNOP, and thermal transients be considered.
2.
Testing Program The. testing sequences include puncture tests at the closure and on the flat cask body surface. Thirty foot drops include an oblique drop on-the bottom end which would include a secondary impact on the lid (slapdown).
It was suggested that the-oblique drop on the lid end might be a more severe test for the closure.
The test package will be leak tested after the test sequence.
3.
Human Factors GA has included human factors consideration in the design process, but has no separate human factors review function.
Specific examples of design requirements based on human factors were interchangeable impact limiters, no loose parts (use of-captured bolts), use of a side drain -
versus a bottom drain.
GA has used operating experience with the FSV cask to evaluate human factors.
It was noted by DOE that a separate task evaluation program will be implemented by DOE for all NWPA casks.
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Nancy L. Osgood Transportation Branch, NMSS' Distribution:
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Meeting Attendees Meeting Notebk-bFb$bbhbh.........$bbhb $
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NAME:N0sgood
- CRchappell DATE:4/I2/90
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