ML20147B681

Certificate of Compliance 9089, Revision 1, for Model NH-100

ML20147B681
Person / Time
Site:	07109089
Issue date:	12/07/1978
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20147B685	List: ML20147B681
References
NUDOCS 7812180007
Download: ML20147B681 (3)

Text

. _ _ _ _ _

t Form NRC-618 U.S. NUCLE AR REGULATORY COMMISSloN U 5}

g cl a H CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.

1.(c) Package identification No.

1.(d) Pages No. 1.(e) Total No. Pages 9089 1

USA /9089/A 1

2

2. PF'.F AMB LE 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 (40 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regt lations (46 CFR 146-149), as amended.

2.(b)

The packae:ng and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal P sgulations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Materia. Under Certain Conditions.**

2.(c)

This certificate does not reHeve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agent,,es, including the government of any country through or into which the package will be transported.

3. This certificate is issued on the basis of a safety analysis report of the package desim or application-3.(a)

Prepared by (Name and address):

3.(b)

Title and identif. cation of report or application:

Hittman Nuclear & Development littman Nuclear & Development Corp.

Corporation application dated April 6,1977.

9190 Red Branch Rodd

. Columbia, Maryland 21045 71-9089 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. HN-100S (2)

==

Description:==

The cask is a steel annulus 84-1/4 inches high by 81-5/8 inches in diameter.

The cavity is 74-1/2 inches high by 75-5/8 inches in diameter.

The side walls consist of two plys of 1-1/2-inch steel.

The 3-inch steel base is integrally welded to the cylinder.

The lid is a 3-inch steel plate, stepped to mate with the upper flange of the cylinder. A centrally located shield plug is similarly constructed.

The lid and plug are attached with stud-bolts and nuts and sealed with Buna N 0-ring gaskets. A plugged drain line is provided.

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

Three lugs welded to the outer shell are used for cask lifting.

The lid and plug have three and one shackles, respectively, for lifting.

The package gross weight is approximately 43,000 pounds.

(3)

Drawings The packaging is fabricated in accordance with PX Engineering Company, Inc., Drawing No. : 449-A, Sheet 1, Rev. 0; Sheet 2, Rev.1; Sheet 3, Rev.1; and Sheet 4, Rev. O.

78121800o~l

Page 2 - Certificate No. 9089 - Revision No. 1 - Docket No. 71-9089 5.

(b) Contents (1) Type and form of material.

Process solids, either dcwatered, solid or solidified, meeting 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 17,000 pounds.

6.

Shoring shall be placed between the secondary containers and cask cavity to minimize movement during normal conditions of transport.

7.

The lid and shield plug lifting lugs shall not be used for lifting the cask, and shall be covered in transit.

8.

The drain line shall be appropriately plugged and sealed prior to transport.

9.

The package authorized by thic certificate shall be transported on a motor vehicle, railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the licensee.

10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).

11.

Expiration date: June 30, 1983.

REFERENCES Hittman Nuclear & Development Corporation application dated April 6,1977.

Supplement Dated:

September 11, 1978.

l FOR THE U.S. NUCLEAR REGULATORY COMMISSION Y

Cliarles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety DEC 0 71978 Date:

ADDENDUM N0.1 FOR U.S. NUCLEAR REGULATORY COMMISSION TRANSPORTATION BRANCH SAFETY EVALUATION OF THE HITTMAN NUCLEAR & DEVELOPMENT CORPORATION MODEL No. HN-100S PACKAGING USA /908_9]A Encl to Ltr dtd DEC 0 71978 Summary By application dated September 11, 1978, Hittman Nuclear & Development Corporation requested revision to the approval for shipment of low specific activity radioactive material in the Model No. HN-100S packaging.

It was requested that the weight limit of the contents, secondary con-tainers and shoring be increased to 17,000 pounds and the total package weight be increased correspondingly to about 43,000 pounds.

The applicant has additional structural evaluations to show that the ef fects of the one-foot free fall test required under normal conditions of transport will not significantly reduce the package containment ability and that the lifting and tie-down requirements are met.

Based on the statements and representations contained in the application, the staff has concluded that the Model No. HN-100S packaging and contents, as described, satisfy the requirements of 10 CFR Part 71.

Reference Hittman Nuclear & Development Corporation application dated September 11, 197'.

Structt. cal Evaluation The conditions significantly affected by the specified weight changes are lifting, tie-down and normal free drops.

By analysis, it was shown that the packaging meets the requirements of 10 CFR 571.31 for the 18%

increase in lifting and tie-down loads.

The end and side normal condi-tion free drop analysis results were not substantially changed with the 18% increase in impact kinetic energy.

It was shown by analysis that the packaging lid and base plate, sub,iected to 62% greater loads for the respective corner free drop impacts, would still meet the requirements of 10 CFR 571.35.

Charles E. MacDonald, Chief

' Transportation Branch Division of Fuel Cycle and Material Safety DEC 0 71978 Date:

l