ML20147B524
| ML20147B524 | |
| Person / Time | |
|---|---|
| Site: | 07106601 |
| Issue date: | 10/04/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20147B529 | List: |
| References | |
| NUDOCS 7810110038 | |
| Download: ML20147B524 (3) | |
Text
q V Form NR'C.018 U.S. NUCLE AR REGULATORY COMMISSION 10 CfR 71 U
CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1( Certificate Number 1.(b) R vision No.
1.(c a a d t fic tion No.
1.(d) ages No. 1.{e) T tal No. Pages
- 2. PRE AMBLE 2.ta)
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 146-19-10a and 146-19-100 of the Department of Transpor'ation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.to)
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 government of any country through or ir to which the package will be transported.
- 3. This certificate is issued on the basis of a ufety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Chem-Nuclear Systems, Inc.
ATCOR, Inc. application dated January 29, P.O. Box 1866 1974, as supplemented.
Bellevue, WA 98009 71-660i
~
3.(c)
Docket No.
- 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.:
LL-50-100 (2) Description The packaging is a steel-encased, lead shielded shipping cask which weighs approximately 70,000 pounds when loaded. The cask is 73.5 inches in diameter by 92 inches high, with an effective cavity 62 inches in diameter by 75 inches long.
Gamma shielding equiva-lent to 4.5 inches of lead is provided by lead and steel.
The outer shell is fabricated of two 3/4 inche thick steel plates and the inner shell of 1/2-and 1/4-inch thick plates.
The cavity is closed and sealed by thirty-two,1-3/4 inch bolts and a silicone 0-ring within a recessed groove on the flange of the cask.
A steel collar encircles the outer shell in the lid area.
Shackles are used for lifting the packaging and the lid.
Tie-down is accomplished through a steel structure which is not attached to the package.
The lid provides several threaded and sealed access plugs and the base has a drain line.
(3) Drawings The package is constructed in accordance with the following ATCOR, Inc. Drawing Nos.:
1042-D-0001, Rev. A; 1042-C-0002, Rev. C; 1042-B-0004, Rev. C; and 1042-D-0021, Rev. C.
7&ie 11 W#5f
l Page 2 - Certificate No. 6601 - Revision No. Docket No. 71-6601
)
(b) Contents (1) ' Type form of material 1
(i) Byproduct material in the form of solids and solidified waste l
contained within secondary container (s).
(ii) Radioactive material in the form of activated reactor components.
(2) tiaximum quantity of material per package Greater than Type A quantities bf radioactive material, not to exceed 20 thermal watts and 20,000 pounds including weight of the contents, secondary container (s) vid shoring.
6.
Wood shoring shall be placed between the secondary container (s)'(or activated components) and the cask cavity to prevent movement during normal conditions of transport.
7.
Prior to each shipment, the packaging lid silicone o-ring shall be inspected.
The o-ring shall be replaced with a new silcone o-ring if inspection shows any defects or every six (6) months, whichever occurs first.
8.
The external dose rate at 3 feet from the surface of the package shall not exceed 125 mrem /,*.
9.
The drain line and access plugs shall be appropriately plugged and sealed prior to transport.
- 10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR S 71.12(b).
11.
Expiration date: August 31, 1979.
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Page 3 - Certificate No. 6601 - Revision No. 5 - Docket No. 71-6601 REFERENCES l
ATCOR, Inc. applicated dated January 29, 1974.
l Supplements dated: June 28 and July 29, 1974; October 21 and November 23.and 29, 1977; and March 9,1978.
FOR'THE U.S. NUCLEAR REGULATORY COMMISSION
{
r
'))(Charles E. MacDonald~ Chief Transportation Brantn Division of Fuel Cycle Material Material Safety OCT 0 4 W Date:
_