ML19323G493
| ML19323G493 | |
| Person / Time | |
|---|---|
| Site: | 07109096 |
| Issue date: | 05/20/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19323G492 | List: |
| References | |
| NUDOCS 8006020585 | |
| Download: ML19323G493 (2) | |
Text
.
Il S
Lm)
Form NRC 618 U.S. NUCLEAR REGULATORY Cor.EllCSION
].
U CERTIFICATE OF COMPLIANCE l
,g c 71 For Radioactive Materials Packages
,6 1.fa) Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1.(d) Pages No. 1.(e) Total No. Pages onog 3
USA /9096/A 1
2
- 2. PREAMBLE 2.tal This certificate is issued to satisfy Stetions 173.3934,173.394,173.395. and 173.096 of the Departmeet of Transportation Hazardous Materials Regulations (49 CFR 170129 and 14 CFR 103) and Sections 146-19-104 and 146-19-100 of the Cepartment 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 reauirement of the regulatiem of the U.S. Department of Transportation or other applicable regulatory agencaes, including th9 government of any country through or into which the pacnage will be transported.
- 3. This certificate is issued on the basis rA a safety analysis report of the package design or acotication-3.(a)
Prepared by (Narne an'd address):
3.(b)
Title and identification of report or application:
Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application P.O. Box 1866 dated April 14, 1980.
l Bellevue, WA 98009 71-9096 3,g,3 g,,,, y,,
4 CONDITtONS This car *ificate is conditional upon the fulfilling of the requirements of Cubpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized '.mdn,, Model Number, Fissde Class Other Conditions, and
References:
(a) Packaging (1) Model No.: CNS 21-300 (2) Description A steel encased lead shielded cask for low specific activity radioactive ma terial. The cast is a right circular cylinder with 86-3/4-inch OD by 117-1/4-inch height, and a cavity 83-inch 10 by 109-1/4-inch height. The 1-inch thick lead shield is supported by outer and inner stainless steel shells 3/4-inch and 1/8-inch thick. The inner plates of the lid and base are laminated steel plates with a total thickness of 1/2-inch.
Positive closureofthesiliconerubber-sealedlidisprovidedbytwelve,1-1/4-inch l diameter cap screws. A secondary lid with a Neoprene seal uses eighteen, 3/4-inch diameter bolts for closure.
The cask is welded to a 96-inch square base plate and has two lifting trunnions, three lid lif t rings and one secondary lid lift ring.
Package gross weight is 57s450 pounds.
i (3) Drawing Tne packaging is fabricated in accordance with Chem-Nuclear Systems, Inc.
Drawing No. 1-298-101, Rev. J.
l 900602o S E
Page 2 - Cortificate No. 9096 - Revision No. 3 - Docket T:o. 71-9096 5.
(Continued)
(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 radioactive 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 27,250 pounds.
6.
Shoring shall be placed between secondary containers (or accivated 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 l
transit.
8.
Prior to each shipment the lid gaskets shall be inspected. Thc gaskets shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
9.
Packagings fabricated (10 CFR 571.C3(c)) after April 14, 1980, shall be constructed of A-516, Grade 70 carbon steel instead of A-36 carbon steel.
1.0.
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 the 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. 3pplication dated April 14, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION k
Charles E. MacDonala, Chief' Transportation Certification 3 ranch Division of Fuel Cycle and Material Safety
.gv 9 0 M Cate:
=m mv v
m n
4