ML20151G524
| ML20151G524 | |
| Person / Time | |
|---|---|
| Issue date: | 07/05/1988 |
| From: | Odegaarden R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8807280410 | |
| Download: ML20151G524 (3) | |
Text
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4 JUL 0 51988 SGTB: RHO MEMORANDUM FOR: The Files FROM:
Richard H. Odegaarden, SGTB, NMSS t
SUBJECT:
SUMMARY
OF MEETING ON NWPA SHIPPING CASK - WESTINGHOUSE Attendees WESTINGHOUSE EG&G NRC B.R. Nair G ange G. Chappell W.J. Severson E.P. Easton H.W. Lee R.H. Odegaarden L. Yang Introduction A meeting was held at tM request of Westinghouse (W) at Rockville, Maryland, on May 24, 1988, concerning a legal weight truck cask for NWPA BWR and PWR fuel assemblies.
Sumary c
The Transportation Branch met with Westinghouse and EG&G on May 24,.1988 to discuss Westinghouse's plan for a legal weight truck cask for NWPA shipments. The TITAN cask would be designed to transport either up to four PWR or up to nine BWR assem-blies containing ten year old fuel with a burnup of 30,000-35,000 mwd /t. The current design does not take credit for fuel burnup. The cask would consist of a stainless-
-steel outer shell, a depleted uranium gamma shield, a stainless steel inner shell, and an aluminum basket for holding the assemblies. Neutron shielding would be provided by a layer of borosilicone rubber fastened to the outer shell. The use of tita.iium alloy as a structural material for the outer shell was also discussed.
An application is expected by the end of 1990.
Discussion The legal weight truck cask would hold eithar two PWR assemblies or six BWR assemblies. The cask would be constructed of stainless steel with an internal depleted uranium gama shield and an externa; borosilicone rubber neutron shield.
The top and bottom of the cask would be provided with identical l
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Files - Westingi:ouse 2
toroidal impact limiters constructed of aluminum. _The cavity is 24" ID by 181" high.
The gross overall dimensions of the cask are 58.5" 0D by 224" high. The fuel basket is constructed of aluminum with Boral neutron absorbing plates. The cask is provided with an outer and inner cask lids. The inner is the primary lid.
An alternate cask design may be constructed of a titanium alloy rather than stainless steel. This cask could contain four PWR assemblies or nine BWR assemblies. The cavity dimensions would be 27.25" ID by 180" high.
The cask design would either be constructed of stainless steel or titanium but not both. Two safety analyses reports would be submitted in 1990 if the BWR and PWR contents resulted in different outside packagings.
The criticality analyses would assume fresh fuel, no burnup.
It was suggested that the boron content of the Boral be reduced by 25% in order to take clumping and uncertainties of the boron into consideration.
Either.a static or dynamic elastic analysis is planned for the cask (s).
Regulatory Guides 7.6 and 7.8 would be followed.
Lid bolts would not be allowed to yield.
Theimpactlimiterswouldbetestedfullscale(includingwelds)with temperature effects taken into accoun+, (both hot and cold -20*F).
Slap down would be addressed.
Force / deflection curves would be developed for the impact angles considered in the safety analysis report. The curves would be developed statically. The depleted uranium would not be treated as a structural material (gravel). For each drop, the stress data should be tabulated for the same points, with the points shown on a sketch.
The punch tests should be for the maximum damage to the package such as seal or containment penetration areas.
N0P would be determined, in part, based on all pins rupturing inside the cask.
The fuel basket should be shown not to buckle.
The fuels would have the following characteristics:
10 10 burnup,MD/MTU 30,000 35,000 enrichment, w/o U-235 4.0 4.5 heat, watts per assembly 8.50 8.50
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Files - Westinghouse 3
Engineering drawings should be submitted which include materials of construction, dimensions, critical tolerances, standard weld symbols, welder qualifications, non-destructive weld tests, acceptance criteria, etc.
ASME code, Section NB should be followed for construction.
Full scale tests are preferable to. scale tests.
Both W and the NRC staff would be expected to have difficulties in analyzing the aluminum fuel basket. The use of titanium (a non-code material) would be a research project.
WEhm?$bi R. R. Otegendes Richard H. Odegaarden, Project Manager Transportation Branch SGTR, NMSS DISTRIBUTION:
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PDR Heeting Attendees Meeting Note Book RH0degaarden(2)
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