ML20008F189

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Certificate of Compliance 9111,Revision 4,for Model CN6-80A
ML20008F189
Person / Time
Site: 07109111
Issue date: 03/04/1981
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20008F187 List:
References
NUDOCS 8103120465
Download: ML20008F189 (3)


Text

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Foim NRC417s U.S. NUCLEAR REGULATORY COMMIS$ TON U

I CERTIFICA*s'E OF COMPLIANCE 10 CFR g For Radioactive Materials Packages 1.(c) Pack 1.(d ) Pages No. 1 (el Total No. Pages USA /913e identification No.1 3

1.ial Certificate Number 1.(b) Hevision No.

1/A 9111 4

2. PRC AMBLE 2.tal This certeficate is issued to satisfy Sections 173.333a.173.394.173.395 and 173.396 of the oepartrnent of Transportation Hazardow Materials Regulations (49 CFR 170-189 and 14 CFR 1031 and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulatior.s (46 CFR 146-149). as amendet 2.(b)

The packagirsg and contents descrrbrd in item 5 below, meets the safety standvds set forth in Subpart C of Title 10. Code of Federal Regulations, Part 71, ' Packaging of Radioactive Materials for Tran port and Transportation of Ra6.ective Material Under Certain Conditions.-

2.(c)

This certificate does not relieve the consignor frorn compliance with any requirement of the regulations of the U.S. Depwtment of Transportation or other applicable regulatory egencies, including the riovernment of any country through or into which the package will be transported.

3. This certificate is issued on the basis of a safety arsalysis report of the packa2e design or application-3,(a)

Prepared by flJame and address):

3.(b)

Title and. identification of report or application:

Nuclear Packaging, Incorporated Nuclear Packaging, Inc., application dated 815 South 28th Street March 6, 1978, as supplemented.

Tacoma, WA 98409 3.(c3 oocket No.

71-9111 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, Fastsie Class. Other Conditions, and

References:

(a) Packaging (1) Model No.:

CN6-80A (2) Description A steel encased, lead shielded cask for solid radioactive material meeting the requirements for low specific activity radioactive material.

The overall dimensions of the cask are 70-1/2-inch diameter by 78-5/8-inch height.

The cask consists of two concentric carbon steel cylindrical shells surrounding a 4-1/4-inch thick lead shield.

The 3/8-inch thick inner shell has a 59-inch I.D., and the 1-inch thick outer shell has a l

70-1/2-inch 0.D.; the base consists of 4-inch thick *:elded steel plates l

of 60-inch diameter and 70-1/2-inch diameter, and a st.epped welded lid l

comprised of two 4-inch thick steel plates containing a centered 29-inch diameter secondary lid of similar construction with an additional 1-inch thick upper plate.

The containment cavity is 53-inch diameter by 58-inches L

high.

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

Both lids are sealed using silicone gaskets bonded to the lid plates. The secondary lid has a redundant neoprena c &s'i.

A plugged l

drain port is located at the cask bottom.

The cask is lined with 12 gauge stainless steel. Three lift lugs, located on the secondary lid are used for lifting 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.

8108120gg L

Page 2 - Certificate No. 9111 - Revision No. 4 - Docket No. 71-9111 5.

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

l (b) Conte.its (1) Type and fmm of material (i) Greater than Type A quantities of byproduct n.aterial contained in solids and solidified waste, meeting the requirements for low specific activity radioactive materials as defined in 10 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 671.4(g).

(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 7,500 pounds.

The decay heat load shall not exceed 400 watts.

6.

Shoring shall be provided in the shipping cask cavity sufficient to prevent signifi-cant movement of the contents or secondary containers relative to the outer packaging under normal conditions of transport.

7.

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

8.

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.

9.

The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12(b).

10.

Expiration dated:

July.31, 1983.

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~Page 3 - Certificate No. 9111 - Revision No. 4 - Docket No. 71-9111 l

REFERENCES l

t i.

Nuclear Packaging, Incorporated application dated March 6, 1978.

Supplements dated:

June 7 and 28, 1978; and December 17, 1980.

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

i FOR THE U.S.. NUCLEAR REGULATORY COMMISSION t

0 M

f~TransportationCertificationBranch Charles E. MacDonald, Chief j

Division of Fuel Cycle and Material Safety

~

AR 0 41981 1

Date:

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