ML19290D575
| ML19290D575 | |
| Person / Time | |
|---|---|
| Site: | 07104949 |
| Issue date: | 02/12/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19290D573 | List: |
| References | |
| NUDOCS 8002220210 | |
| Download: ML19290D575 (2) | |
Text
e Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package ld antification No.
Pages No. 1.(e) Total No. Pages 4949 3
USA /4949/AF 1.(d) 1 2
- 7. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Trarmportation 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, 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 goveinment 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 address):
3.(b)
Title and identification of report or application:
United Nuclear Corporation United Nuclear Corporation application dated Recovery Operations October 4, 1979, as supplemented.
l Wood River Junction, RI 02894 3.(c)
Docket No.7] _4949
- 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 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class Other Conditions, and
References:
(a) Packaging (1) Model No.: UNC-1484 (2) Description Containment vessel consists of a 51/4" ID x 361/2" long and 3/8" thick steel pipe with welded bottom plate and bolted top flange closure.
Containment vessel is centered and supported within a 65 gallon minimum 16-gage steel drum with D0T Specification 17H closure by plywood spacers, benelex, tubular steel spokes, and insulation material.
(3) Drawings Container is constructed in accordance with United Nuclear Corporation Drawing No. D-5005-8017, Rev. 1.
(b) Contents (1) Type and form of material Uranium oxide and compounds which will withstand a temperature of 750 without pressure generating decomposition.
Density may not exceed 5.3 g U/cc.
The theoretical-density-moderator relationship for "U compounds" shown in Figure 309 XXIV, dated 800222o 2.1 O
~
Page 2 - Certificate No. 4949 - Revision 3 - Docket No. 71-4949 5.
(b) Contents (1) Type and form of material (Continued)
February 6,1970, Docket No. 70-36, or in Figure 1.D.17 of the UK Handbook may not be exceeded.
Uraniu..i may be enriched to any degree in the U-235 isotope. The maximum H/X atomic ratio considering all sources of hydrogenous material interspersed with the fissile material shall not exceed 0.5.
(2) Maximum quantity of material per package Total contents not to exceed 65 pounds with the U-235 content not to exceed 25.4 kg.
(c) Fissile Class II and III (1) Minimum transport index to 2.0 be shown on label for Class II (2) Maximum number of packages per 50 shipment for Class III 6.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
7.
Expiration date: December 31, 1984.
REFERENCES United Nuclear Corporation application dated October 4,1979.
Supplement dated:
November 14, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
& $k Charles E. Mt.cDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date: