ML20238D257

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Summary of 870901 Meeting W/Transnuclear,Inc in Silver Spring,Md Re Design for Package to Transport contact- Handled Transuranic Wastes
ML20238D257
Person / Time
Site: 07109213
Issue date: 09/03/1987
From: Odegaarden R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8709110070
Download: ML20238D257 (2)


Text

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SGTB:RH0 71-9213 D

MEMORANDUM FOR:

The Files FROM:

Richard H. Odegaarden, SGTB, NMSS

SUBJECT:

TN-TRU CASK Attendees l

TN NRC i

E V. Margotta Ross Chappell A. G. Eggers W. rl, Lee Alan S. Hanson E. P. Easton Tara Neider D. T. Huang R. H. Odegaarden Introduction, A meeting was held at the request of Transnuclear, Inc. (TN) at Silver Spring, Maryland, on September 1, 1987, concerning the design for a package _to transport contact-handled transuranic wastes (TRU).

Discussion A general description of the package is given in a memorandum for the Files (R. H. Odegaarden). dated August 6, 1987.

j TN discussed their test program, test results to date, correlation between tests and analysis, and an overview of future tests.

Based on previous discussions with the NRC (June 25,1987) and additional analysis several changes were made to.the packaging, e.g., gas sample ports, tie-down lugs, method of attaching top and bottom impact limiters, emissivity of packaging, and a shear ring added to outer containment vessel closure. A1.1 changes appeared to be improvements in the package design-to meet the requirements of 10 CFR Part 71.

TN has performed several static tests (1/3 scale model) to determine the packaging containment will not be effected by the puncture test.. These static'

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tests will be followed by dynamic tests which are not expected to j

significantly effect the ability of the packaging to meet the requirements of i

Part 71. Seal-leakage rates were determined on a.1/3 scale model of the.

packaging with full size 0-ring gaskets. Based nn these tests and other structural tests and analysis, the package is expet.ted to be leak tight before and after the accident conditions of transport, j

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Discussion centered on the performance of the impact limiters. The current design consisting of separate pieces of balsa and redwood would be difficult to analyze and would probably have to rely on either scale or full size model tests. The NRC staff suggested that LN conduct scale model or full scale drop tests to confirm the performance of the impact limiters in various drop orientations. TN is planning to submit a full size package to the accident sequence based on analytical and scale model drop tests.

The number of tests and orientations were not agreed upon due to a lack of information. TN is planning to meet with the NRC staff prior to performing full size drop, puncture, and fire tests.

odgh:alsgned hF Richard H. Odegaarden, Project Manager Transportation Branch Division of Saftouards and Transportation, NMSS 1

DISTRIBUTION:

Meeting attendees NMSS r/f SGTB r/f Meeting Notebook CEMacDonald cNRC.PDRV Docket" File m i 4??

0FC :SSTBp

5GTB j:

NAME:RH0degaarden:kd:CRChappell:

DATE: 9/09k787

9/S?/87 :

OFFICIAL RECORD COPY l