ML20137R561

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Summary of 851120 Meeting W/Gesselshaft for Nuklear Svc, Chem-Nuclear,GNSI,Fracture Control Corp & Swanson Svc Corp in Silver Spring,Md Re Tests for Demonstrating Fracture Toughness of Nodular Cast Iron Shipping Cask
ML20137R561
Person / Time
Site: 07109190
Issue date: 11/25/1985
From: Odegaarden R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8512060016
Download: ML20137R561 (2)


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Richard !!. Odegaarden, FCTC, WSS SUOJECT:

SU!?tARY OF fiEETING HITil GNS CONCERNING NODilAR CAST IRON SilIPPING CASK (CASTOR-MTR)

Attendees.

GNS Chem-Nuclear GNSI Fracture Control Coro Jack Rollins Paul Highberger Robert Anderson Paul PcConnell Juergen Higenda Kevin R. Kingsley Heinz'Geiser Dieter Rittscher Swanson Service Corp.

N9C Bill Jones C. E. MacDonald R. H. Odegaarden C. R. Chappell

. Introduction At the request of GNS, a ceeting was held at Silver Spring, Maryland, on flovember 20, 1985, to discuss tests for demonstrating fracture toughness 4

of nodular cast iron.

Discussion The NRC staff reiterated its letter of February 23, 1984, concerning nodular cast iron. The need for a full scale test with one or more flaws and the need to establish natorial properties was discussed at length.

Five casks have been built. to the prop? sed CASTOR-MTR design. One cask will be used for drop test purposas. Each cask will have four core bores and K values measured from 12 samples. The size of the induced I

cracks will he based on the properties of the cask with the worst fracture control properties. The effect of cutting the crack in the test specinen with a laser needs to be evaluated to detemine raterial properties in the crack area. Applicable items in the February 23. 1904, letter are to be followed in conducting the tests and satisfying that production

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casks are at least as good as the. test cask.

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The Files L The tests may be conducted with or without a fuel basket. The staff pointed out the need to denonstrate the presence of neutron flux traps if needed, in the structural analysis.

I An English translation of the detailed safety analysis report for the package is also needed as part of the revalidation process for this package.

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Richard H. Odegaarden, Project l',anager Transportation Certification Branch Division of Fuel Cycle and Paterial Safety, WSS h

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