ML19294B654
| ML19294B654 | |
| Person / Time | |
|---|---|
| Site: | 07106697 |
| Issue date: | 02/21/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19294B652 | List: |
| References | |
| NUDOCS 8003050227 | |
| Download: ML19294B654 (3) | |
Text
=
Form NRC418 U.S. NUCLE AR REoVLATORY CcMMISSION (12 731 CERTIFICATE OF COMPLI ANCE 3a cpg 7, 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 6697 6
USA /6697/Bf )
1 3
- 2. PRE AMBLE.
2.fa)
This certificate is issued to satisf y 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, 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 Under Certain Conditions."
2.lc)
This certificate does not relieve the consignor from compliarm with any requirement cf the regulations of the U.S. Department of Transportation or other applicable reguistory agencies, including the government of any country through or into w'lich the package will be transported.
- 3. This certificate 6-issued on the basis of a safety ar.alysis 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 November 29, 1979.
Pleasanton, California 94566 3.(ci Dockei No. 71-6697
- 4. CONOtTIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71, as applicable, and the conditions specified in. -n S below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fiss:le Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: GE-8500 (2) Description The packaging is a steel, uranium shielded shipping cask surrounded by a laminated plywood protective jacket.
The inner shielded cask is an upright circular cylinder, consisting of an inner shell, 2-7/8 inches ID x 6-1/8 inches high, made of 1/8-inch thick stainless steel which is surrounded by 1-13/16 inches of depleted uranium and enclosed in a 7-inch OD x 10-1/2-inch high x 1/d-inch thick stainless steel outer shell.
Closure is by means of six, 3/8-inch diameter bolts and a 1/8-inch thick neoprene rubber gasket between body and lid. The shielded cask is positioned in a two-piece protective jacket of solid plywood laminations which is bolted to a rectangular palle't made of aluminum.
The protective jacket is 15-1/4 inches OD x 20-1/2 inches high and together with the pallet, weighs 80 pounds.
The cavity of the shielded cask contains a leak tight, 2R type, steel insert, shown on GE Drawing No.161F443, Rev. 5 or 135C5982, Rev. 4, or 106D3830, Rev. d (the latter to be used with the liner shown on 153C4613, Rev. 1). The gross weight of the loaded package is approximately 286 pounds.
~
8003050
e Page 2 - Certificate No. 6697 - Revisior No. 6 - Docket No. 71-6697 5.
(a) Packaging (continued)
(3) Drawings The package is constructed in accordance with the following General Electric Company Drawing Nos.:
277E696, Rev. 6; 277E712, Rev. 6; 174F482, Rev. 5; 289E795, Rev. 3; 195F169, Rev. 2; 289E796, Rev. 5; 161F443, Rev. 5; or 135C5982, Rev. 4; or 106D3830, Rev. 8 with 153C4613, Rev. 1.
(b) Contents (1) Type and form of material Radioactive materials in solid or liquid form.
l (2) Maximum quantity of material per package Greater than Type A quantities of solid radioactive material with the l
decay neat load not exceeding 50 watts.
Plutonium in, excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements.
Liquid radioactive material is limited to 100 ci of Mo-Tc solution.
l 6.
Liquids shall be further packaged in a leak tight polyethylene bottle within the 2R insert.
Each polyethylene bottle shall be sealed and tested in accordance with Attachment 0 of General Electric's letter dated November 29, 1979.
7.
Prior to each shipment, the package lid Neopoene gasket shall be inspected. The gasket shall be replaced with a new Neoprene gasket if inspection shows any defects or every twelve (12) months, whichever occurs first.
In each shipment, a new Viton 0-ring shall be used to seal the 2R type insert.
d.
The a type insert shall be pretested to ensure leak tightness prior to each use in accordance with Attachment D of General Electric's letter dated November 29, 1979.
9.
The radiation dose level shall not exceed 1000 millirem per hour, at a distance of 3 feet.from the surface of the depleted uranium cask, when the wooden protective jacket is not in place.
- 10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 11. Expiration date: February 28, 1985.
Page 3 - Certificate No. 6697 - Revision No. 6 - Docket tio. 71-6697 REFERENCE General Electric Company application dated November 29, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
&fd4u e m/]
Charles E. PacDonald, Chief Transportation Certification Branch Fuel Cycle and Material Safety 0
Date:
O e