ML19211C415
| ML19211C415 | |
| Person / Time | |
|---|---|
| Site: | 07106574 |
| Issue date: | 12/21/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19211C412 | List: |
| References | |
| NUDOCS 8001110317 | |
| Download: ML19211C415 (4) | |
Text
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Form NRC.618 U.S. NUCLE AR REGULATORY CoMMIS$1CN I-"
U CERTIFICATE OF COMPLIANCE 10 C R 71 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 6574 4
USA /6574/B( )
1 1
- 2. PRE AMBLE 2.f a) This certificate is issued to satisfy Sections 173.333a.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 Transportation Dangerous Cargoes Rer,ulations (46 CFR 146--149), as amended.
2.tb)
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."
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2.(c)
This certificate does not relieve the consig'cr from comoliance with any requirement of the regulations of the U.S. Departrnent of Transportation or other soplicable regulate ry agene: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 design or applicaten--
3.la)
Prepared by (Name and address):
3.tbl Title and identification of reoort or acolicat on:
Hittman Nuclear and Development Hittman Nuclear and Development applica-Corporation tion dated December 10, 1979.
9190 Red Branch Road Columbia, MD 21045 3-(c)
Doc"*t Na-71-6574 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 i.em 5 below.
- 5. Description of Packaging and Authorized Contents, Model Nurnber, Fossile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: HN-200 (2) Description The packaging consists of a steel-lead-steel annulus cask fabricated in tne form of a rignt circular cylinder and three different types of inner containers. Tne shielded cask, closed at one end and a lid closure at tne other, is 66.25 inches in diameter by 74.5 inches in heignt. The cask wall consists of a 3/8-inch inner steel shell, 3-3/4 incnes of lead snielding, one inch outer steel shell, and a steel flange connecting the two shells.
The cask outer shell is surrounded by a one inen layer of insulating material and canned in 14-gauge steel.
Tne lid, sealed by a Viton 0-ring, is of similar construction and is bolted to tne cask body.
A cylindrical snield plug is located in the center of tne cask lid and is sealed by a Viton 0-ring.
Lifting and tie-down devices are attached to tne cask body and impact skirts, consisting of removable rings of snock absorbing foam, are attacned to tne ends of the cask.
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(3) Drawing ine package is fabricated in accordance witn ene following Hittman
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Nuclear and Development Corp. Drawing No. : C001-5-9200, Sheets 1 througn 6, Revision I.
80011103 17
Page 2 - Certificate No. 6574 - Revision No. 4 - Docket No. 71-6574 5.
(b) Contents (1) Type and form of material The package contents consist of large quantities of nonfissile radioactive _ wastes solids.
These solids include spent ion exchange rasins, filter sludges, evaporator concentrators and spent fuel cartridges.
( 2,) Maximum quantity of material per package The cask contents shall be contained within one of the following inner containers and limited as follows:
(a) A single disposable inner container consisting of a rignt circular steel cylinder witn a positive leaktignt closure cap at tne top. A maximum decay heat load of 205 Btu /hr.
(b) Tne HN-200-30 inner configuration consists of two tiers of four, 30-gallon DGT Specification 17H steel drums and two steel four-drum pallets.
A maximun cecay heat load of 84 Btu /hr.
(c) The HN-200-55 inner configuration consists of one tier of three 55-gallon, DOT Specification 17H steel drums positioned on one steel pallet. A maximum decay neat load of 116 Btu /hr.
6.
The total weight of tne shipping container shall not exceed 47,000 pounds and tne weight of the contents shall not exceed 7,a00 pounds.
7.
Wooden battens shall be provided in tne shipping cask cavity sufficient to prevent significant movement of ti,e contents relative to the shield plug under normal or accident conditions.
8.
The package autnorized by this certificate is nereby approved for use under the general license provisions of 10 CFR 171.12(b).
9.
Expiration date: March 31, 1980.
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Page 3 - Certificate No. 6574 - Revision flo. 4 - Docket No. 71-6574 REFERENCE Hittman Nuclear and Development Corporation applicated dated December 10, 1979.
FOR THE U.S. NUCLEAR REGULATORY C0f1 MISSION Charles E. MacDonald, Cnief Transportation Certification Branch Division of Fuel Cycle and DEC 211979 Material Safety Date:
1735 333
Hittman Nuclear and Development Corporation
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USA /6574/B
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UE0 2 I l379 Ltr dtd:
1.
The evaluation of g-loads under top-corner impact conditions (pg. 74) should be revised to consider peak g-load. Note that the equation used
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to calculate g-loads in Section F.l(e) is valid when the impact force is constant and should not be used to estimate peak g-loads when impact force varies with crush depth.
2.
Justify the use of 105,000 psi as the allowable bolt stress (pg. 76),
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considering the need to maintain a sealed closure following the 30-foot top corner impact test.
3.
The analysis of bending of the cask lid assembly under top end impact conditions (pg. 93) is unclear and confusing.
Revise the evaluation to clearly show how inertia loads are supported by the two plates and that the stresses in each plate are within allowable limits.
Justify the assumption that the foam at the center of the plate can be considered as a rigid structural support. Also, show that the lead between the two plates is adequate to provide sufficient shear transfer for the two plates to act as an integral structural section as was apparently assumed in the analysis.
1735 534