ML20210U855

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Summary of 860925 Meeting W/Ge in Silver Spring,Md Re Model 2000 Package Design & Approach Licensee Should Use in Demonstrating That Proposed Design Meets Requirements of 10CFR71
ML20210U855
Person / Time
Site: 07109195
Issue date: 09/30/1986
From: Odegaarden R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8610100255
Download: ML20210U855 (2)


Text

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MEMORANDUM FOR: The Files FROM:

Richard H. Odegaarden, FCTC, NMSS

SUBJECT:

SUMMARY

OF MEETING CONCERNING MODEL N0. 2000 PACKAGE DESIGN A meeting was held at the request of General Electric Company (GE) on September 25, 1986, at the NRC offices in Silver Spring, Maryland. The following persons attended the September 25, meeting:

General Electric NRC R. W. Darmitzel R. H. Odegaarden R. J. Pomaros H. W. Lee D. T. Huang C. R. Chappell Discussion On February 27, 1986, a denial was issued to GE for their application dated October 31, 1984, as supplemented on October 22, 1985.

The meeting centered on the general approach a licensee should use in demonstrating to the NRC staff that a proposed package design meets the requirements of 10 CFR Part 71. This included a general description of the computercode(s)used. Modeling and boundary conditions for each type of calculation, results, illustrative sketches of the problem being analyzed, and verification of the computer program (s).

For the Model No. 2000 cask design, the staff indicated a special concern for the possible lack of rigidity in the closure seal area and the bottom of the cask (cask drain line). The lead values used in determining the effects of lead slump on the cask are not consistent with the Cask Designers Guide (0RNL-NSIC-68) and need to be further justified. The use of a constant force being exerted by the overpack on the cask during a side drop also needs to be justified.

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NAME: Odegaarden: alm DATE:09/ /86 :

OFFICIAL RECORD COPY

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