ML19320D726
| ML19320D726 | |
| Person / Time | |
|---|---|
| Site: | 07105971 |
| Issue date: | 07/09/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19320D719 | List: |
| References | |
| NUDOCS 8007220125 | |
| Download: ML19320D726 (3) | |
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U F4rm NRC.618 U.S. NUCLEAR.REGUL/ TORY CoMMISSloN o2 3 CERTIFICATE OF COMPLIANCE 3n g p For Radioactive Materials Packages 1.h) Certificate Number 1.tb) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.le) Total No. Pages 5071 7
USA /5971/Bf 3 F 1
3
- 2. PREAMBLE 2.fa)
This certificate is issued to satisfy Sections 173.393a.173.394,173.39s. and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and sections 146-19-10e and 146-19-100 of the Department of Transportation Dangersus Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, rneets the safety standards set forth in Subpart C of Title to. Code of
, Federal Regulations, Part 71, Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Unser Certain Conditions.-
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2.(c)
This certificate does not relieve the consignor fbm compliance with any requirement of the regulations of the U.S. Department of Transoortation or other applicable regulatory agencies,induding the government of any country through or into which the package will be transported.
- 3. This cartificate 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:
General Electric Company General Electric Company application dated P.O. Box 460 February 20, 1980.
Pleasanton, CA 94566 3.(c)
Dociet No.
71-5971 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 in item s below.
- 5. Description of Packaging and Authorized Contents. Model Number. Fissile Class. Other Conditions, and
References:
(a) Packaging (1) Model Nod:
GE-200 (2) Description A steel encased lead shielded shipping cask.
The cask is a double-walled steel circular cylinder, 20-1/4-inch-diameter by 53 inches high with a central cavity 7-5/8-inch-diameter by 37 inches 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 silicone rubber gasketed l and bolted steel lead filled plug.
For additional shielding, lead-filled stainless. steel liners may be inserted in the cask cavity.
A protective jacket consisting of an upright circular cylinder with open bottom and a protruding box section diametrically across the top and vertically down the sides attaches to a square pallet.
Dimensions of the protective jacket are 65-3/8 inches high by 37-5/8 inches wide across the box section.
The outer cylindrical diameter is 26-3/4 inches and the pallet is.47-1/2 inches square.
The maximum weight of the packaging is approximately 10,000 pounds.
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Page 2 - Certificate No. 5971 - Revision No. 2 - Docket No. 71-5971 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
612D136, Rev. 5 693C293, Rev. 3 985C540, Rev. 2 706E788, Rev. 2 106D3852, Rev. 3 212E236, Rev. 3 693C292, Rev. 5 12904702, Rev. 0 (b) Contents (1) Type and form of material Byproduct and special nuclear material in the form of fuel rods, or plates, fuel assemblies, or meeting special form requirements of 10 CFR 571.4(o).
(2) Maximum quantity of material per package Radioactive decay heat not to exceed 780 watts and 500 grams U-235 equiva-lent mass.
(U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.)
(c) Fissile Class II Minimum transport index to be shown on label 2.3 6.
Shoring shall be provided to minimize movement of contents during accident conditions of transport.
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 silicone rubber lid gasket shall be inspected.
This gasket shall be replaced if inspection shows any defects or every twelve (12)
- months., whichever occurs first.
Cavity drain line shall be sealed with appropriate sealant applied to threads of pipe plug.
j 9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR @71.12(b).
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-Page 3 - Certificate No. 5971 - Revision No. 2 - Docket No. 71-5971 10.
Expiration date:
June 30, 1985 REFERENCE General Electric Company application dated February 20, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION t=S CharlesE.MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and JUL 0 91980 Material Safety Date:
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