ML19262A735

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Certificate of Compliance 9111,Revision 2,for Model CN6-80A
ML19262A735
Person / Time
Site: 07109111
Issue date: 11/30/1979
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML19262A734 List:
References
NUDOCS 7912100462
Download: ML19262A735 (3)


Text

,

Form NRC418 U.S. Nt, _iAR REGULATORY COMMiSSloN

,g g;731 CERTIFICATE OF COMPLIANCE U2 g 7, For Radioactive Materials Packages Pages No. 1.(e) Total No. Pages 9111 2

USA /9111/A 1.(d)1 3

~

1.(a) Certificate Number L(b) Revision No.

1.(c) Package identification No.

2. PREAMBLE 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 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 cont ents described in item 5 below, meets the safety s*andards set forth in Subpart C of Title 10. Code of Federal Regulations, Par' 71, " Packaging of Radioactive Materials for Trasport and Transportation of Radioactive Matenal Under Certain Conditions.*

2.(c)

This certificate does not relieve the consignor from compiiance with any requirement of the regulations of the U Department of Transportation or other applicable regulatory agencies, including the government of any country through or into w.ch 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 repert or application:

Nuclear Packaging, Incorporated Nuclear Packaging, Incorporated, application 1733 South Fawcett dated March 6,1978, as supplemented.

Tacoma, Washington 98402 3.(c)

Docket No. 71-9111

4. CONDITIO tv S This cert ficate is conostona upon the fulfilling of the requirements of Sucpart D of 10 CFR 71, as applicable, and the conditions scecified in item 5 below.
5. Description of Packaging and Authorizeo Contents, Model Number, Fissile Class, Other Conditions, and

References:

(a) Packaging (1) Model f;o. :

C:15-20A (2) Description A steel encased, lead shieldec cask for solid radioactive material meeting the requirements for low specific activity radioactive material. The verall dimensions of the cask are 70-1/2-inch diameter by 73-5,8-inch height.

The cask consists of t,,o car. centric K lead carbon steel cylindrical shells surreurding a 4-1/4-incn th::

shield.

The 3/3-inch tnick inner shei' has a 59-inch I.D., and the 1-inch thick outer shell has a 70-i/2-Mch 0.D., the base consists of 4-inch thick welded steel plates of 60-inch diameter and 70-1/2-inch diameter, and a stepped welded lid ccmorised of two 4-incn tnick steal plates containing a centered 29-inch diametar seccadry lid of simiir construction with an additional 1-inch tnick upper plate.

The containment cavity is 59-inch diameter by Ed-incne.s high.

Closure of the primary lid is accomplished by eight, 1-1/4-inch bolts with j

nuts.

Both lids are sealed using silicone gaskets bonded to the lid plates. The secondary lid has a redundant neoprene seal.

A plugged drain port is located at the cask bottom.

The cask is lined with 12 gauge stainless steel.

Three lift lugs, located on tne 1526 294 ER 3R3M '""#

a Page 2 - Certificate No. 9111 - Revision No. 2 - Docket No. 71-9111 5.

(a)

(2) Packaging Description (Continued) secondary lid are used for lif ting both the cask and the primary lid.

Four lugs, welded to the outer shell are used for tie-down.

The package gross weight is approximately 51,500 pounds.

(3) Drawing The packaging is fabricated in accordance with Nuclear Packaging, Incorporated Drawing No. BC-20-200D, Sheets 1 and 2 of 2, Revision C.

(b) Contents (1) Type and form of material (i) Greater than Type A quantities of byproduct material contained in solids and solidified waste, meeting the requirements for low specific activity radioactive materials as defined in

~0 CFR 571.4(g), in secondary containers.

(ii) Greater than Type A quantities of byproduct material contained in activated solid components meeting the requirements for low special activity radioactive material as defined in 10 CFR 571.4(g).

(2) Maximum cuantity of material per package Greater than Type A quantities of radioactive material with the weight of the contuts, secondary conc.iners and shoring not exceedin 7,500 pounds.

The cecay her icac sball not exceed 400 watts.

6.

Shoring shall be provided in the shipping cask cavity sufficient to prevent significant movement of the contents or secondary cantainers relative to the outer packaging under normal conditions of transpart.

7.

The drain line should be plugged and sealed prior to transport.

8.

The package authori..ed by this certificate shall te transported on a motor vehicle, railroad car, aircraf t, inland water craf t, or hold or deck of a seagoing vessel assigned for sole use of tne licensee.

9.

The pxkage authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 371.12(b).

10.

Expiration dated: July 31, 1983.

300RORl8lNJ1 1526 2 %

Page 3 - Certificate flo. 9111 - Revision tio. 2 - Docket tio. 71-9111 REFEREt1CES tiuclear Packaging, Incorporated application dated March 6,1978.

Supplements dated: June 7 and 28, 1978.

Chem-fluclear Systems, Inc. Supplement dated June 29, 1979.

FOR THE U.S. P:UCLEAR REGULATORY COMMISSI0tl fh

_ - !f Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:

1526 296

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