ML19270F477
| ML19270F477 | |
| Person / Time | |
|---|---|
| Site: | 07106697 |
| Issue date: | 01/24/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19270F476 | List: |
| References | |
| NUDOCS 7902140089 | |
| Download: ML19270F477 (3) | |
Text
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Form NRC418 U.S. NUCLE AR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 CFR 71 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 P39es 6697 3
USA /6697/B( )
1 3
- 2. PRE AM8LE 2.(a)
This certificate is issued to satisfy Sections 173.393a 173.394.173.395, and 173.306 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-104 and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CF R 146-149), as amended.
2.(t)
The packaging and conttnts 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 Yaterial Unoer Certain Conditions.'
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Cepartment of Transportatioh 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 application-3.(a)
Prepared by (Name Jnd 4ddress):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated P. O. Box 460 September 27, 1971, as supplemented.
Pleasanton, California 945665 3.(c)
Docket No.
7l-6697 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart 0 of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissiie 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-l/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 00 x 10-1/2-inch, high x 1/8-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 pallet made of wood, plastic, or aluminum. The protective jacket is 15-1/4 inches 00 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. 2.
Gross weight at loaded package is approximately 285 counds.
79021400 @
Page 2 - Certificate No. 6697 - Revision No. 3 - Docket No. 71-6697 5.
(a) Packaging (continued)
(3) Drawings The package is constructued in accordance with the following General Electric Company Drawings Nos. : 277E695, Rev. 2; 277E712, Rev.1; 174F482, Rev.1 anc.161F443, Rev. 2.
The p'ackaging may be modified by the addition of a slot of 1.5 inches long by 0.12 inch in depth in the bottom of the casi cavity as shown on General Electric Company Drawings Nos.
289E795; 195F169, Rev.1, and 289E796.
(b) Contents (1) Type and form of material Radioactive materials in solid or liquid form.
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the decay heat load not exceeding 50 watts for solids or 10 watts for liquids. Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements.
6.
Liquids shall be further packaged in a leak tight polyethylene bottle within the 2R type insert.
Each polyethylene bottle shall be sealed and tested in accordance with Attachment B of General Electric's letter dated April 13, 1972.
7.
The 23 type insert shall be pretested to ensure leak tightness prior to each use in accordance with Attachment B of General Electric's letter dated April 13, 1972.
8.
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.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
Page 3 - Certificate No. 6697 - Revision No. 3 - Docket No. 71-6697 10.
Expiration date:
December 31, 1979.
REFERENCES General Elbetric Company application dated September 27, 1971.
Supplements dated: January 20 and April 13, 1972; and August 13 and 23 and September 19, 1974.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION frf4u Charles E. MacDonald, Chief Transportation Branch Fuel Cycle and Material Safety JAN 2 41979 Date:
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