ML19294A479

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Safety Eval of Model HN-300,USA/9092/A.Concludes Package Does Meet 10CFR71 Requirements
ML19294A479
Person / Time
Site: 07109092
Issue date: 11/14/1978
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML19294A478 List:
References
NUDOCS 7811270033
Download: ML19294A479 (2)


Text

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U.S. NUCLEAR REGULATORY COMMISSION SAFETY EVALUATION BY THE TRANSPORTATION BRANCH OF THE MOD f4 ti-300 PACKAGE Encl to ltr dtd:

Summary By application dated July 13, 1977, as supplemented, Hittman Nuclear &

Development Corporation requested approval for the Model No. HN-300 packaging to be used for shipment of low specific activity radioactive material.

Based on the statements and representations contained in the application the staff has concluded that the Model No. HN-300 shipping package and its contents as described meet the requirements of 10 CFR Part 71.

References 1.

Hittman Nuclear & Development Corporation application dated July 13, 1977.

2.

Supplement dated: November 6, 1978 Drawing The packaging is fabricated according to Hittman Nuclear & Development Corporation Drawing No. C001-4-9300, Rev. 4.

Packaging Descrip;; ion The packaging is an end-loaded, welded steel primastic cask, for low specific activity radioactive material,151 inches long, 61-1/2 inches wide and 47 inches high.

The cavity is 144 inches by 52-1/2 inches by 40-1/2 inches. The sides are 3-3/4 inches of steel and the end, doors, top and bottom are 3-1/4 inches of steel. The two side-hinged doors are provided with neoprene 0-rings and closed with fourteen 1-1/8-inch steel bclts each. The cask has four top-mounted welded lifting lugs and four welded tie-down plates along the base. The package gross weight is 43,000 pounds.

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Contents The packaging is for the shipment of solid and solidified waste within secondary containers. The contents shall meet the requirements for low specific activity radioactive materials as defined in 10 CFR 571.4(g). The secondary containers which meet t.he requirements for Type A packaging as specified in 49 CFR 5173.389(j) are secured within the cask cavity using shoring to prevent movement during normal condi-tions of transport. The maximum weight of contents, secondary containers and shoring shall not exceed 8,000 pounds.

Structural / Thermal Evaluation The applicant has shown that the general standards of 10 CFR Part 71 have been met.

If the lif ting and tie-down devices were overloaded to failure the ability of the packaging to meet other requirements in the regulations would not be impaired nor would the shielding properties of the packaging significantly decrease.

By analysis, the applicant and staff have shown that the packaging meets the performance requirements for normal conditions of transport when subjected to the normal conditions in 10 CFR Part 71.

Since the packaging is used for shipment of low specific activity radioactive material. it need not satisfy the hypothetical c 'ident conditions of 10 CFR Part 71 when the package is transported on a

) tor vehicle, railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for sole use of the licensee. While there may be localized damage as a :esult of the one-foot free drop, containment for normal conditions of transport is assured by the secondary containers which will be retained in the cask.

Containment The structural / thermal evaluation provided by the applicant has demonstrated that there will be no significant reduction in containment adequacy for Type A secondary containers for normal conditions of transport. The rectangular steel box is not intended to provide containment capability, and therefore approval has been conditioned to require Type A secondary containers.

Shielding There will be no significant reduction of shielding effectiveness for the normal conditions of transport.

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Charles E. MacDonald, Chief Transporation Branch Division of Fuel Cycle and Material Safety ff0V 141978 Date: