ML19310A495
| ML19310A495 | |
| Person / Time | |
|---|---|
| Site: | 07109094 |
| Issue date: | 05/29/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19310A493 | List: |
| References | |
| NUDOCS 8006170817 | |
| Download: ML19310A495 (2) | |
Text
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. Form NRC 618 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive hierials Packages 1.(al Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Totaf No. Pages i
9094 5
USA /9094/A 1
2
- 2. PREAM8LE a
2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10s 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. "Peckaging 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 ce 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 addressp 3.(b)
Title and identification of report or application:
Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application P.O. Box 1866 dated March 31, 1980.
Bellevue, WA 98009 3.(c)
Docket No. 71 9094 4
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 j
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 14-195-H i
.(2) Description A steel. encased lead shielded cask for low specific activity radioactive material. The cask is a right circular cylinder 83-1/8-inch diameter by 89-7/8-inch with a 77-inch diameter by 80-1/8-inch cavity.
Lead shielding is 2-3/16-inch thick, and is encased in an outer steel shell 3/4-inch thick and inner steel shell 1/8-inch thick. Positive closure of the silicone i
rubber-sealed lid is provided by twelve,1-1/4-inch diameter cap screws.
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A secondary lid with a Neoprene seal uses eighteen, 3/4-10 UNC bolts for t
closure. The ca'sk is welded to a %-inch square based plate, has two lifting _ trunnions, three lid lift rings and one secondary lid lifting ring.
Package gross weight is 56,500 pounds.
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(3) Drawing.
The packaging is fabricated in accordance with Chem-Nuclear Systems, Inc.
Drawing No. 1-189-101, Sheet 1 of 1s Rev. A-F.
'9006170 M
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Page 2 - Certificate No. 9094 - Revision No. 5 - Docket No. 71-9094 5.
(b) Contents (1) Type and form of material (i) Process solids, either dewatered, solid or solidified in secondary containers, meeting the requirements for low specific activity radio-active material, or (ii) Solid reactor components in secondary containers, as required that meet the requirements for low specific activity radioactive material.
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the weight of the contents, secondary containers and shoring not exceeding 17,700 pounds.
6.
Shoring-shall be placed between wcondary containers (or activated components) and the cask cavity to prevent movement during normal conditions of transport.
7.
The lid lifting lugs shall not be used for lifting the cask and shall be covered in i
transit.
8.
Prior to each shipment the lid gaskets shall be inspected. This gaskets shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
9.
Packagings fabricated (10 CFR 571.53(c)) after March 31, 1980, shall be constructed of A-516, Grade 70 carbon steel instead of A-36 carbon steel.
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- 10. The package authorized by this certificate 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.he licensee.
- 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12 (b).
- 12. Expiration date: May 31,1985.
REFERENCE
-Chem-Nuclear Systems, Inc. application dated March 31, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
$$}$ $%
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety N
Date:
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