ML19250C131
| ML19250C131 | |
| Person / Time | |
|---|---|
| Site: | 07105980 |
| Issue date: | 10/31/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19250C125 | List: |
| References | |
| NUDOCS 7911080266 | |
| Download: ML19250C131 (3) | |
Text
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Form NRC413 U.S. NUCLE AR REGULATCAY COMMISSION igcFH71 CERTIFICATE OF CO.*."PLI ANCE For Radioxtive Matere. sis Pachges 1.f a) Cet tific. = %mt>er 1.tbl Revision No.
1.tc) Pac. ace laentificatio#, No.
1.id ) Pages No. 1 (e) Total No. P uc..
59a0 3
USA /5930/B( )F 1
4
- 2. PRE AMBLE 2.f al TNs certificate is maed to satisf y Sections 173 3334.173.304.173.395, and 173.396 of the Depa,tment of Transportstion H: izar <taus Wterials Regulations #49 CFR 170120 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation D.ingerous Cargoes Requtations (46 CF R 146-143), as amended-2.(b)
The packaging and con e'its described in item 5 below, meets the safety :tandards set forth in Subpart C of Title 10. Code of Federal Regulations, Pa.t 71. " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.
2.fc)
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 gove-nment 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 application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application P. O. Box 460 received January 13, 1969, as supplec.ented.
Pleasanton, California 94566 3.(c)
Docket No.
71 6980 4 CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditiont spec:fied in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number. Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.: GE-600 (2) Description A steel-encased lead shielded shipping cask.
The basic cask body is a cylinder 34 inches in diameter by 60 inches high formed by two concentric steel shells whose annular region is filled with 6 inches of lecd. The cavity is 20-1/2 inches ID by 46 inches high, 3/d-inch thi,:k stainless steel cylinder. A recessed plug-type cask lid, consisting of a steel weldment filled with lead, is secured to the cask body by six,1-inch diameter steel bolts. A silicone rubber gasket provides the seal.
A protective jacket consisting of a double-walled structure of 1/2-inch thick carbon steel plates is placed over the cask and bolted to a steel pallet by eight, 2-inch diameter steel bolts. The cask has one 1/2-inch diameter drain line from the cavity to the outer shcIl.
The drain line is closed with a plug which has a melting temperature of 200 F.
The cask is shipped in the apright position.
The total weiet of the package is approxiir.ately 18,500 pounds den loJded.
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Page 2 - Certificate No. 5980 - Revision No. 3 - Occket No. 71-5980 5.
(a) Packaging (continued)
(3) Drawings The packaging is cons 1.ructed in accordance with the ?ollowing General Electric Co. 1rawings Nos.:
GE Orawina No.
Title 212E247, Rev. 3 600 Series Shipping Cask 10603895, Rev. 1 600 Series Cask Ass'y.
211A7528, Rev. 0 Name Plate 144F650, Rev. O Cask Line--
693C293, Rev. 2 Liner 161F470, Rev.1 Jacket T0603892, Rev. 1 Base (b) Contents (1) Type and form of material (i) Byproduct material and irradiated special nuclear material in solid or solid oxide form, but specifically not loose powders.
Contents are to be clad, encapsulated or contained in a metal encasement of such material as to withstand the combined effects of the internal heat loac and the 1475 F fire with the closure pre-tested for leak tightness.
(ii) Neutron sources in special form.
(2) Maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements, and (1) For the contents described in 5.(b)(1)(i) the maximum decay heat not to exceed 600 watts and the fissile content not to exceed 500 grams of U-235, 300 grams U-233, 300 grams Pu, or a prnrated quantity of each such that the sum of the ratios does not exceed unity; or not to exceed 1200 grams fissile provided:
(1) the fissile material is contained in schedule waste liners constructed of 5-inch schedule 40 pipe with a maximum inside length of 39-5/15 inches, (2) no more than four such liners are shipped at one time, (3) each liner contains no more than 300 grams fissile, and (4) the cask is provided with a positioning lattice to maintain separation between the liners.
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a l'
Page 3 - Certificate flo. 5980 - Revision flo. 3 - Docket flo. 71-5980 l
l 5.
(b) Contents (continued) i (2) Maximum quantity of material per package (continued)
(ii) For the contents described in 5(b)(1)(ii) the maximum decay heat not to exceed 50 watts and not more than 500 grams U-235 equivalent mass. The exte-ra? h&rry.e et to exceed 1000 mrem /hr at 3 feet from the surface of a cry package.
(c) Fissile Class III Maximum number of package per shipment Two (2) 6.
The U-235 equivalent mass shall be determined by the following method:
U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.
7.
Except for the neutron sources in special form (10 CFR 571.4(o)), the package contents shall be cry and the fissile material unmoderated (H to X atomic ratio less than 2).
d.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
9.
Expiration date: January 31, 1980.
l REFERENCES General Electric Company's application received January 13, 1969.
Supplements dated:
February 12 and March 10, 1969; and May 21, 1974.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
$<a
+Y Charles t. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety OCT 311979 oate:
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