ML20147F454
| ML20147F454 | |
| Person / Time | |
|---|---|
| Site: | 07109086 |
| Issue date: | 12/07/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20147F458 | List: |
| References | |
| NUDOCS 7812210434 | |
| Download: ML20147F454 (3) | |
Text
Form NP,Q418 U.S. NUCLE AR REGULATORY COMMISSION 3g y CERTIFICATE OF COMPLI ANCE For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No. 1.(c) Package identification No. 1.(d ) Pages No. 1.(e) Total No. Pages 9086 4 USA /9086/A 1 3
- 2. PRE AMBLE 2.(a) This certificate is issued to satisfy Sections 173.393a,173.394.173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b) The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.
2.(c) This certificate does not relieve the conspor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or appiication-3.(a) Prepared by (Name and address): 3.(b) Title and identification of report or application:
Hittman Nuclear & Development Hittman Nuclear & Development Corporation applicatio:
Corporation dated January 13, 1977, as supplemented 9190 Red Branch Road Columbia, Maryland 21045 3.(c) Docket No. 71-9086
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified i's item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: HN-100 Series 1 (2) Description A steel encased, lead shielded cask for low specific activity material. The cask is a right circular cylinder 81.5 inches high by 81.5 inches in diameter. The cask cavity is 73.5 inches high by 75.5 inches in diameter. The cask side wall consists of a 3/8-inch thick inner steel shell, a 1-3/4-inch lead shell, and a 7/8-inch thick outer steel shell. The base is a 4-inch thick steel plate which is welded to the inner and outer steel shells of the eide wall. A steel flange is welded to the inner and outer steel shells of the side wall at the top. The lid is a 4-inch thick steel plate which is stepped to mate with the steel flange. The cask closure is sealed by a Viton 0-ring gasket located between the lid and steel flange. Positive lid closure is accomplished by thirty,1-inch bolts. The lid contains a centrally located 4-inch stepped steel shield plug. The shield plug is sealed by a Viton 0-ring gasket, and sixteen, 1/2-inch bolts are used to provide positive closure.
781221043
Page 2 - Certificate No. 9086 - Revision No. 4 - Docket No. 71-9086
- 5. (a) Packaging (cont'd) /
(2) Description (cont'd) y Tie-down is accomplished by four tie-down lugs welded to the cask body. There are three casks lifting lugs, three lid lifting lugs, and one shield plug lifting lug. The package gross weight is approximately 50,000 pounds.
(3) Drawing l
The packaging is constructed in accordance with Hittman Nuclear
& Development Corporation Drawing No. C001-5-9100, Sheets 1, 2 and 3, Revision C.
(b) Contents (1) Type and form of material Process solids either dewatered, solid or solidified meeting the requirements for low specific activity radioactive material, i'1 secondary containers. -
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the weight o# t!ie contents, secondary containers and shoring not exceeding 14,500 pounds.
- 6. Shoring shall be placed between secondary containers and the cask cavity l to minimize movement during normal conditions of transport.
- 7. The 1*d and shield plug lifting lugs shall not be used for lif ting the cask, and shall be covered in transit.
- 8. The package authorized by this certificate shall be transported on a motor vehicle, railroad car, aircraf t, inland watercraft, or hold or ,
deck of a seagoing vessel assigned for the sole use of the licensee. '
- 9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 10. Expiration date: August 31, 1982.
e
i Page 3 - Certificate No. 9086 - Revision No. 4 - Docket No. 71-9086 REFERENCES ,
Hittman Nuclear & Development Corporation application dated January 13, 1977.
Supplements dated: October 6,1977; and September 11, 1978.
FOR THE U.S. NUCLEAR REGULATORY COM41SSION M[A Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety '
Da te: DEC 0 71978 s
I
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ADDENDUM NO. 2 FOR U.S. NUCLEAR REGULATORY COMMISSION TRANSPORTATION BRANCH SAFETY EVALUATION OF THE HITTMAN NUCLEAR & DEVELOPMENT CORPORATION MODEL HN-100, SERIES 1 PACKAGING USA /9086/A Sumary By application dated September 11, 1978, Hittman Nuclear & Development Corporation requested revision to the approval for shipment of low specific activity radioactive material in the Model No. HN-100, Series 1, packaging.
It was requested that the weight limit of the contents, secondary containers and shoring be increased to 14,500 pounds and the total package weight be increased correspondingly to about 50,000 pounds.
The applicant has submitted additional structural evaluations to show that the effects of the one-foot free fall test required under normal conditions of transport will not significantly reduce the package containment ability and that the lifting and tie-down requirements are met.
Based on the statements and representations contained in the application, the staff has concluded that the Model No. HN-100, Series 1, packaging and contents, as described, satisfy the requirements of 10 CFR Part 71.
Reference Hittman Nuclear & Development Corporation application dated September 11, 1978.
Structural Evaluation The conditions significantly affected by the specified weight changes are lifting, tie-down and normal free drops. By analysis it was shown that the packaging would meet the requirements of 10 CFR 571.31 for the 9% increase in lifting and tie-down loads. The end and side normal condition free drop analysis results were not significantly changed with the 9% increase in kinetic energy at impact. It was shown by analysis that the packaging lid and base plate, subjected to 38% greater loads for the respective corner free drop impacts, would still meet the requirements of 10 CFR 571.35.
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety DEC 0 71973 Date:
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