ML19323G038
| ML19323G038 | |
| Person / Time | |
|---|---|
| Site: | 07109072 |
| Issue date: | 05/20/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19323G035 | List: |
| References | |
| NUDOCS 8005300188 | |
| Download: ML19323G038 (3) | |
Text
.
J Fcrm NRC418 U.S. NUCLEAR REGULATORY Commission gg c;738 CERTIFICATE OF COMPLIANCE U2
,7, For Radioactive Materials Packages 1.tz) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1,(dl Pages No. 1.(e) Total No. Pages 9072-1 USA /9072/B( )F 1
3
- 2. PREAMBLE 2.fa)
This certificate is issued to satisf y Sections 173.393a,173.394,173.395. and 173.396 of the Departrnent of Transportation Hazardous Materlats 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 deecribed in item $ below, meets the safety standards set forth in Subpart C of Title 10. Code of
- Federal Regulations, Part 71,
- Pu. aging of Radioactive Materials for Transport and Transportation of Radicactive Material Under Certain Conditions.
2.(c)
This certificate does not relieve the consignor from compliance with any recuirement of the regulations of the U.S. oepartment of Transportation or other aoolicable r,gulatory 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 applicatior,-
3.fa)
Prepared by (Name and address):
3.!b)
Title and identification of report or aponication:
C:teral Atomic Company General Atomic Company application P.O. ?ox 81608 dated October 1, 1976, as supplemented.
San Dieta, CA 92138 3.tc) oocket No.71-9072
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the recuirements of Subpart D of 10 CFR 71, as applicable, and the condit' ens specified in item 5 below.
- 5. Description of Packaging and Authorised Contents, Model Number, Fissile Ctans. Other Conditions, and
References:
(a) Packaging (1) Model No.: GAHC-1
+.
(2) Description Steel encased lead shielded shipping cask. The cask is provided with recessed plug-type lid and gasketed, bolted closure, lifting and tie-down devices and drain line penetrations.
Containment for the contents is provided by inner can assemblies.
The cask has dimensions, weight, and shielding as follows:
Exterior height, in 64.2 Exterior diameter, in 26.0 Cavity height, in 42.5 Cavity diameter, in 6.0
, Lead shielding, in 8.5 Loaded weight, lbs 12,500 (3) Drawing The packaging is constructed in accordance with Battelle Memorial Institute Drawing No. ECL4-01, Sheet 2, Rev. A.
I D"O "Dy 8005800)p 1 W dj
Page 2 - Certificate No. 9072 - Revision No.1 - Docket No. 71-9072 5.
(b) Contents Type and form and maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor elements; and byproduct material, source
,naterial and special nuclear material not to exceed 200 watts decay heat in solid metal or oxide form packaged with inner can assembly and limitations on fissile loading for the Fissile Class as follows:
Inner can assembly:
Gulf General Atomic Drawing No. 'iC-178, Issue C
' Fissile Class I 650*
Fissile Class III 2000*
- (grams U235 equivalent mass)
(c) Fissile Class I and III Maximum number of packages per shipment for Class III One (1) 6.
The U-235 equivalent mass shall be determined by the following method:
U-235 equivalent mass equals U-235 mass plus 1.75 times U-233 mass plus 1.60 times Pu mass.
7.
At the time of delivery of the loaded cask to a carrier for transport, the cask contents shall be:
(1) dry (contents of inner can assembly shall not decompose up to a temperature of 750 F) and the fissile material unmoderated (H to X atomic ratio less than 2) and (2) so limited that the dose rate will not exceed 4 millirem per hour at three (3) feet from the external surface of the package.
8.
The maximum gross weight of the cavity contents shall not exceei 180 pounds (inner can assembly, radioactive material, etc. ).
9.
The package authorized by this certificate is hereby approved for under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date: May 31, 1981.
Page 3 - Certificate No. 9072 - Revision No.1 - Occket No. 71-9072 REFERENCES G:neral Atomic Company application dated October 1,1976, for Model No. GAHC-1 shipping package.
Gulf 011 Corporation supplement dated: October 14, 1971.
Battelle Memorial Institute supplements dated: September 20 and October 29, 1968; January 8 and February 19, 1969; and May 9, 1975.
FOR U.S. NUCLEAR REGULATORY COMMISSION Ch Ma d, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety MAY 2 01980 Date:
i 9
e e