ML19225C954
| ML19225C954 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 07/12/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19225C952 | List: |
| References | |
| NUDOCS 7908030358 | |
| Download: ML19225C954 (3) | |
Text
.
Form NRC 618 U.S. NUCLE AR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE O
For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1.id ) Pages No. 1.te) Total No. Pages 9019 2
USA /9019/B( )F 1
3
- 2. PREAMBLE 2.ta)
This certificate is issued to satisf y Sections 173.393a.173.394,173.395, and 173.39G 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 Danqerous Cargoes Regulations (46 CF R 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 F ederal Regulations, Part 71, Packaging of R:idioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions /
2 (c)
This certsfecate 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 (Name and address).
3.(b)
Title and identification of report or application' General Electric Company General Electric Company application dated P.O. Box 780.
May 24, 1974.
Wilmington, NC 28401 3.(c)
Docket No. 71_g919 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, arul the conditions specified in item 5 below.
5.
Description of Packaging arn Authorized Contents, Model Number, Fissile Class Other Conditions, and References (a) Packaging (1) Model No.:
BU-7.
(2) Description The packaging consists of either two, 5-gallon or three, 2.5-gallon, ll.25-inch ID, minimum 24-gauge steel pails contained in a 13.75-inch diameter by 27-inch long inner container constructed of minimum 18-gauge steel, with bolted and gasketed top flange closure. The inner container is centered and supported in a 22.5-inch ID,18-gauge steel 55-gallon capacity DOT Specification 17H drum by solid insulating material composed of fire-retardant phenolic foam.
The maximum weight of the package is 350 pounds.
(3) Drawing The container is constructed in accordance with Fig.1.8.1, Appendix D, of General Electric Company's application dated fiay 24, 1974.
(b) Contents (1) Type and form of material h]
10 (i)
Uranium oxide powder with a maximum bulk density 'ot greater than 2.3 grams /cc. Uranium may be enriched to not more than 4.0 w/o in the U-235 isotope. The maximum H/U-235 atomic ratio considering all sources of the hydrogenous material within the inner container shall not exceed 0.45.
,7908030T5s
Page 2 - Certificate No. 9019 - Revision No. 2 - Docket No. 71-9019 (b) Contents (continued)
(ii) Uranium oxide as pellets with a maximum bulk density of 10.96 grams /cc. Uranium may be enriched to a maximum 4.0 w/o in the U-235 isotope.
(2) Maximum quantity of material pe. package (i) For the contents described in 5(b)(1)(i):
The maximum contents per package and pail for the maximum U-235 enrichment shall be limited in accordance with the following table:
Maximum U-235 Maximum UO Maximum UO 2
2 enrichment, per pail, per package, w/o kgs kgs 3.0 44.5 89.0 3.2 38.9 77.8 3.4 34.6 69.2 3.6 31.1 62.2 3.8 28.3 56.6 4.0 25.7 51.4 (ii) For the contents described in 5(b)(1)(ii):
The maximum contents per package and pail for the maximum U-235 enrichment shall be limited in accordance with the following table:
Maximum U-235 Maximum UO Maxin.um U0 2
2 enrichmen t, per pail, per package, w/o kg s kgs 2.7 45.0 90.0 2.8 42.9 85.8 2.9 40.1 80.2 3.0 38.1 76.2 3.2 34.1 68.2 3.4 31.0 62.0 3.6 28.5 57.0 3.8 26.4 52.8 4.0 24.7 49.4 A'7
'C
!04
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Page 3 - Certificate No. 9019 - Revision No. 2 - Docket No. 71-9019 (c) Fissi' Class I
6.
For mixtures of contents (powders and pellets) described in 5(b)(1), the maximum quantity of material per package shall be limited to the quantity given in 5(b)(2)(ii).
7.
The density of the package insulation shall not be less than 8 lbs/cu ft for the side and bottom and 20 lbs/cu f t for the top.
8.
The four,1/4-inch diameter holes located near the top of the outer DOT Speci-fication 17H drum as shown in Fig.1.8.1 shall be covered with weatherproof tape to preclude the entry of water.
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: July 31, 1984.
[
REFERENCi General Electric Company application dated May 24, 1974.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION c441bM Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JUL 121979 Date:
453 105
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