ML19296D549
| ML19296D549 | |
| Person / Time | |
|---|---|
| Site: | 07105926 |
| Issue date: | 02/20/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19296D548 | List: |
| References | |
| NUDOCS 8003050235 | |
| Download: ML19296D549 (3) | |
Text
Form NRC418 U.S. NUCLE AR REGULATORY COMYlSSION CERTIFICATF M cOMPLI ANCE 10 C R 71 For Radioa
- -ials Packages 1.f a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d ) Pages No. 1.(e) Total No. Pages 5926 4
USA /5926/B( )F 1
2
- 2. PRE AMB LE 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 la6-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2Jb1 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 consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies including the governinent 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 application-3.(a)
Prepared by (Name and addrest):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated P.O. Box 460 January 25, 1980 Pleasanton, CA 94566 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart C of 10 CFR 71, as applicable, and the conditions specified in item 5 beto.v.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.:
GE-100 (2)
Description A steel _ encased lead shielded shipping cask.
The cask is a double-walled steel circular cylinder, 20-1/4-inch diameter by 27-1/8-inch high with a central cavity 7-5/8-inch diameter by 10 inch _es high. Approximately 5-7/8 inches of lead surround the central cavity.
The cask is equipped with a cavity drain line and lifting device.
Closure is accomplished by a gasketed and bolted steel lead filled plug.
For additional shielding lead, tungsten or uranium liners may be inserted in the cask cavity.
The maximum weight of the packaging is 3,520 pounds.
(3)
Orawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
913E390, Rev. 2 135C5371, Rev. 2 6120137, Rev. 5 153F902, Rev. 5 612D139, Rev. 5 135C5529, Rev. 3 693C292, Rev. 5 706E594, Rev. 7 9d5C540, Rev. 2 153C4270, Rev. 2 9d6Cb76, Rev. 2 12904702, Rev. 0 693Cz93, Rev. 3 8003050
Page 2 - Certificate No. 5926 - Revision No. 4 - Docket No. 71-59?6 5.
(b) Contents (1) Type and form of material Byproduct and irradiated special nuclear material in solid metal or solid oxide form; or other non-decomposable (at 650 F) solid materials.
(2) Maximum quantity of material per package Radioactive decay heat not to exceed 400 watts and 500 grams U-235 equivalent mass fissile material.
(U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.)
Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor elements.
(c) Fissile Class II fiinimum transport index to be shown on label 5.6 6.
The byproduct and special nuclear material shall be clad, encapsulated or contained in a metal encasement in accordance with the statements and representations contained in paragraph 2.0(a) of the General Electric Company's application dated January 25, 1980, or in Special Form (10 CFR 571.4(o)).
New seals shall be, used for each shipment.
7.
At the time of delivery of the loaded package to a carrier for transport, the package contents shall be dry and the fissile material unmoderated (H to X atomic ratio less than 2).
8.
Prior to each shipment the lid gasket shall be inspected.
The gasket shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
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, 1930.
REFERENCE General Electric Company application dated January 25, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION fkew Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety 7980
.0 ate:
General Electric Company Model No. GE-100 Packaging USA /5926/B F
Ltr dtd: FEB 2 01980 1.
Submit a consolidated set of drawings for the packaging.
These drawings should clearly summarize the safety features considered in the analysis.
These drawings should include such things as materials of construction, dimensions, valves, gaskets, and weld specification, but should not be the detailed construction drawings.
2.
Develop a containment acceptance criteria for normal conditions of transport and accident damage conditions for the normal form shipments.
Show that the sensitivities and testing schedules are adequate for safe use of the packages.
Regulatory Guide 7.4 may be used for periodic testing.
For assembly verification, it is recommended that a test of sufficient sensitivity to limit the maximum release to a Type A quantity in 10 days is used; 3
however, a leak test sensitivity greater than 1x10 3 at-cm /sec, would not at-cm sec (air at 1 atm and 3
be required. The minimum sensitivity of lx10 3 25 C leaking to a 10 at ambient) as specified in ANSI N14.5 should be 2
met.
e e