ML19276G855
| ML19276G855 | |
| Person / Time | |
|---|---|
| Site: | 07109079 |
| Issue date: | 06/14/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19276G854 | List: |
| References | |
| NUDOCS 7908280470 | |
| Download: ML19276G855 (3) | |
Text
..
Form NRC-618 U.S. NUCLE AR REGULATORY COMJISSION U
CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materials Packages Pages No. 1.(e) Total No. Pages 1.(a) Certifica'e Number 1.(b) Revision No.
1.(c) Packaoe Identification No.
9079 3
USA /9079/A 1.(d) 1 3
- 2. PRE AMB LE 2 (a)
This certificate is issued to satisf y Sections 173.393a,173.394,173.395, and 173.396 of the Jepartment of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-)Da and 146-10-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CF R 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set furth in Subpart C of Title 10, Code of Federal Regulations, Part 71, " Packaging of Radioactise Materials for Transport and Transportation of Radioactise Material Under Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of t le regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the gasernment of any c. untry 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 application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Hittman fluclear & Development Hittman Nuclear & Development Corporation, application Corporation dated January 12, 1977, as supplemented.
9190 Red Branch Road Columbia, Maryland 21045 3.(c)
Docket No. 71-9079 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requiram* 's of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 tielow.
5.
Description of I'ackaging arvi Authorimi Contents Model Number, Fissile Class, Other Conditions, and References (a)
Packaging (1) Model fio.:
HN-100 Series 2 (2) Description A steel encased, lead shielded cask for low specific activity material.
The cask is a right circular cylinder 81-1/2 inches high by 81-3/4 inches in diameter.
The cask cavity is 73-3/8 inches high by 75-1/2 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 stcel shell.
The base is comprised of two, 2-inch thick steel plates welded together to form a 4-inch thick bas _e which is integrally welded to the inner and outer steel shells of the side wall. A steel flange is welded to the inner and outer steel shells of the side wall at the top. The lid is comprised of two, 2-inch thick steel plates, which are stepped and welded together to mate with t;ie steel flange. The cask closure is sealed by a neoprene gasket located between the lid and steel flange, positive closure of the lid is accomplished by eight rachet binders.
The lid contains a centrally located shield plug comprised of two, 2-inch thick steel plates and one,1-inch thick steel plate stepped and welded. The shield plug is sealed by a neoprene gasket, and eight, 3/4-inch studs and nuts are used to provide positive closure.
204i 245 i
7908280f70 C
Page 2 - Certificate No. 9079 - Revision No. 3 - Dv bet No. 71-9079 Tie-down is accomplished Sy four tie-down lugs welded to the cask body. There are four cask lif ting lugs, three lid lifting lugs, and one shield plug lifting lug.
The package gross weight is approxi-mately 48,000 pounds.
(3) Drawings The packaging is fabricated in accordance with Hittman Nuclear &
Development Corp. Drawings No.:
C001-4-9119, Rev. C, Sheets 1, 2, l
3, 4, 5 anJ 6.
(b) Contents (1) Type and form of material Process solids, either dewatered, solid or solidified, meeting the requirements for low specific activity radioactive material, in secondary conta iners.
(2) Maximum quantity of material per pac 6 age Greater than Type A quantities of radioactive material with the weight of the contents and secondary containers not exceeding 14,000 pounds.
6.
Shoring shall be placed between secondary containers and the cask cavity to prevent movement during normal conditions of transport.
7.
The lid and shield plug lifting lugs shall not be used for lifting 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 watercraf t, or hold 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: July 31,1982.
2041 246
Page 3 - Certificate No. 9079 - Revision fio. 3 - Docket tio. 71-9079 REFERENCES Hittman fluclear & Development Corporation application dated January 12, 1977.
Supplements dated: June 6 and 21,1977; September 29, 1978; and May 9, 1979.
FOR THE U.S. f;UCLEAR REGULATORY C0" MISSION ll*
fh Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety JUN 141979 Date:
70Ai 247 9