ML19263D911
| ML19263D911 | |
| Person / Time | |
|---|---|
| Site: | 07109081 |
| Issue date: | 03/30/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19263D910 | List: |
| References | |
| NUDOCS 7904170051 | |
| Download: ML19263D911 (3) | |
Text
Form NRC 618 U.S. NUCLE AR REGULATORY COMMtSSION
(
CERTIFICATE OF COMPLlANCE 10 l R 71 For Radioactive Materials Packages 1.(a) C i te Number 1.(b) Re ision No.
1.(
! e ic ion No.
1.(d Pages No 1.le) T I No. Pages
- 2. PRE AM8LE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.294,173.395, 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 I'6-19-100 of the Department of Transportat6on Dangerous Cargoes Regulations (46 CF R 146-149), as amenced.
2 (b)
The packageng and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of Fer2eral 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 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)
'repared by (Name and address).
3.Ib)
Title and identification of report or applicat on:
Chem-Nuclear Systems, Inc.
Nuclear Plant Services application dated P.O. Box 1866 February 4,1977, as supplemented.
Bellevue, WA 98009 3.(c) oocket No.
71-9081 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.: CNS-1600 (2) Description A steel encased lead shielded shipping cask. The packaging is a steel double-walled, lead-filled circular cylinder. A steel, plug-type, lead-filled lid is attached with twelve,1-1/4" bolts; and a silicone gasket. Outer steel sheets are separated from the cask walls with small diameter wires. The lead shielding is 5" in the sides, 6" in the base and 5-3/4" in the lid. Two bolted-on steel lugs are for lifting only.
The lid has a steel U-bar for lifting. The cavity drain line is closed with a plug. The cask is 39" in diameter and 68-1/2" long. The cavity is 26-1/2" in diameter and 54" long. The packaging weight is about 26,000 pounds.
(3) Drawings The packaging is constructed in accordance with Chem-Nuclear Systems, Inc., Drawings NPS-ll477, Rev. O, and NPS-ll577, Rev. O.
(b) Contents Type, form and maximum quantity of material per package
~
(i) Greater than Type A quantities of byproduct material as solid metal.
Decay heat not to exceed 600 watts and maximum weight not to exceed 5,000 pounds; or 790417006l
Page 2 - Certificate No. 9081 - Revision No. 2 - Docket flo. 71-9081 5.(b) Contents (Continued)
(ii) Greater than Type A quantities of neutron sources in special form.
Decay heat not to exceed 50 watts and fissile material and corresponding minimum transport index as specified in 10 CFR 571.11(b) (2).
(iii) Process solids, either dewatered, solid, or solidified in a secondary sealed container meeting the requirements for low specific activity radioactive material, or Solid reactor components in secondary containers, as required, that meet the requirements for low specific activity radioactive material.
6.
The lid closure to the cask shall be secured by twelve, SA-354, Type BD, 1-1/4-7UNC bolts.
7.
For packaging of other than neutron sources, the cask shall be delivered to a carrier dry and the cavity drain line snall be closed with a plug which will maintain its seal at temperatures up to at least 620 F.
8.
For packaging of neutron sources, the cavity drain line shall be closed with a plug with a melting temperature of 200*F and the cask cavity shall be filled with water with a 5-inch air space within the cask cavity. When needed, sufficient antifreeze in the cask shall be used to prevent damage to any component of the package due to freezing.
9.
For packaging of other than neutron sources, measurements shall be made to
. determine that the dose rate does not exceed 30 mrem /hr at 3 feet from the surface of a dry loaded cask.
- 10. For packaging of neutron sources, measurements shall be made to determine that the dose rate does not exceed 1,000 mrem /hr at 3 feet from the surface of a dry cask with no additional shielding within the cask.
- 11. The contents described in 5.(b)(iii) shall be transported on a motor vehicle, railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
- 12. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 13. Expiration date: July 31, 1982.
~
Page 3 - Certificate flo. 9081 - Revision flo. 2 - Docket flo. 71-9081 REFEREilCES fluclear Plant Services application dated February 4,1977.
Supplement dated: June 14,1977.
FOR THE U.S. IlVCLEAR REGULATORY COMMISSI0il du Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Date:
.