ML19257B748
| ML19257B748 | |
| Person / Time | |
|---|---|
| Site: | 07105980 |
| Issue date: | 12/31/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19257B744 | List: |
| References | |
| NUDOCS 8001180245 | |
| Download: ML19257B748 (3) | |
Text
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Form NRC4i18 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revisior. No.
1.(c) Package identification No.
1.(d) Pages No. 1.(e) Total No. Pages 5980 4
USA /5980/Bf )F 1
3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.3933,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 1D3) and Sectioris 146-19-10a and 146-19-100 of the Department of Transportation Cangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
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, "Packagmg of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
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 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 application-3.(a)
Prepared by IName and address):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated P. O. Box 460 October 10, 1979 Pleasanton, California 94566 71-5980 3,,c3 o,c,,, y,,
- 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 Cor.ditions, 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 lead. The cavity is 20-1/2 inches ID by 46 inches high, 3/8-inch thick 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 froni the cavity to the outer shell.
The. drain line is closed with a plug which has a melting temperat!ure of.200 F.,
The. cask is shipped in the upright position.
The total weight of 'the package is approximately
~
18,500 pounds when loaded.
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Page 2 - Certificate No. 5980 - Revision No. 4 - Docket No. 71-5980 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Co. Drawings Nos. -
212E247, Rev. 5 106D3898, Rev. 3 144F650, Rev. 1 693C293, Rev. 3 161F470, Rev. 2 106D3892, Rev. 3 129D4685, Rev. 0 129D4684, Rev. 0 195F162, Rev. 0 (b) Contents i
(1) Type and form of material (i) Byproduct material and irradiated special nuclear material in solid or solid oxide form, but specifically not loose powcers.
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 load and the 1475 F fire with the closure pre-tested for leak tightness.
Also, byproduct material and irradiated special nuclear material in special form.
(ii) Neutron sources in special form.
(2) Maximum quantity of material per package Plutonium in excess of twenty 1 20) curies per package must be in the form of metal, metal alloy or reactor fuel elements, and (i)
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 o.f U-235, 300 grams U-233, 300 grams Pu, or a prorated quantity of each such t. hat. the sum of the ratios does riot exceed unity; or not to exceed 1200 grams fissile provided:
(i) the fissile material is contained in schedule waste liners constructed of 5-inch schedule 40 pipe with a maximum inside length of 39-5/16 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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Y Page 3 - Certificate No. 5980 - Revision No. 4 - Docket No. 71-5980 5.
(b) Contents (continued)
(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 external dose rate.not to exceed 1000 mrem /hr at 3 feet from the surface of a package wit,hout internal shielding.
l (c) Fissile Class III Maximum number of packages 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 ma;s 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 dry and the fissile material unmoderated (H to X atomic ratio less than 2).
8.
Prior to each shipment, the packaging primary lid closure seal shall be inspected.
The primary lid closure seal shall be replaced with a new seal if inspecticr. shows any defects or every twelve (12) months, whichever occurs first.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date:
December 31, 1984.
REFERENCES General Electric Company's application dated October 10, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION i
kCharlesE.MacDonald, Chief I)
Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
r769 250
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