ML19320D733
| ML19320D733 | |
| Person / Time | |
|---|---|
| Site: | 07105768 |
| Issue date: | 07/10/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19320D731 | List: |
| References | |
| NUDOCS 8007220135 | |
| Download: ML19320D733 (4) | |
Text
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q Farm fdRC.618 U.S. NUCLEAR. REGULATORY CoMMIEStoN II CERTIFICATE OF tOMPLIANCE lo C R 71 For Rad;oactive Materials Packeges
- 1.(1) Certificate Nu 1.(b) Revision o.
1.(c) Pack eI ii No.
1.{d) Page Nr. 1.(e) Total g. Pages
- 2. PREAMBLE 2.la)
This certificate is issued to satisfy Sections 173.393a.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 Dangen..s Cargoes Regulations (46 CFR 146-149), as amended.
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2.(b)
The packaging and contenu 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 Ce tain Conditions.**
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2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.s. Departrnent of Transportation or other applicable regulatory agencies, including the government of any cc.mtry through or into which the package will be transported.
- 3. This czrtificate is issued on the basis of a safety analysis report of the package design or application-
'*(a)
Prepared by (Name and address):
3.ib) ' Title and identification of report or:ss piication:
' General Electric Company Combustion Engineering, Inc. application P.O. Box 780 dated September 11, 1972, as supplemented.
Wilmington, NC 28401 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional opon the fulfilling of the requirernents of Subpart D of 10 CFR 71. as applicable, and the conditions specified din item s below,
- s. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and References; (a)- Packag'ing (1) Model No.:
BB-250-2 (2) Description Inner container is 11.5" ID, 16 gage steel cylinder, 63.5" long, with bolted and gasketed top flange closure and seal welded bottom plate.
Inner container.is centered and supported in a-22.5" ID by minimum 74" long 16 gage steel drum by 1/4" diameter spring steel rods and vermicu-lite.
Maximum weight of packaging and contents is approximately 575 pounds.
(3) Drawings The BB-250-2 packaging is constructed in accordance with Westinghouse Electric' Corporation sketch SKA-252-1 (Appendix L to Westinghouse Electric Corporation letter dated March 1, 1968).
The outer cover is secured by either a 12 gage closure ring or six (6),.1/2" diameter bolts.
9 80"07220/3[
Page 2 - Certificate No. 5768 - Revision No. 4 - Docket No. 71-5768 (b) Contents (1) Type and form of material (i) Uranium oxide pellets.
Uranium may be enriched to a maximum 3.5 w/o in the U-235 isotope.
The maximum H/U atomic ratio, considering all sources of hydrogenous material within the inner container shall not exceed 1.5.
(ii) Uranium oxide enriched to a maximum 3.5 w/o in the U-235 isotope.
Chemically-bound or physically-bound water in mixtures is permitted.
Slips or slurries that exhibit a visually discernible liquid second phase are prohibited.
2 or U 0 ) powder witL..naximum censity of 2 (iii) Bulk uranium oxide (U0 33 g U/cc and enriched to a maximum 4 w/o in the U-235 isotope.
The maximum H/U atomic ratio, considering all sources of hydrogenous material within the inner container shall not exceed 1.13.
(iv) Uranium compounds which will not decompose at temperatures up to 750 F.
Uranium may be enriched to a maximum 5 w/o in the U-235 isotope.
The maximum H/U atomic ratio, considering all sources of hydrogenous material within the inner container shall not exceed 1.5.
(v) Uranium oxide pellets, enriched to a maximum of 3.5 w/o in the U-235 isotope.
The maximum H/V atomic ratio, considering all sources of hydrogenous material withir. the inner container, shall not exceed 3.0.
(2) Maximum quantity of material per package (i)
For the contents described in 5(b)(1)(i):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed 1.96 kilograms.
The pellets shall be contained within sealed 9.5" to 9.75" diameter steel cans.
(ii)
For the contents described in 5(b)(1)(ii):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed 2.95 kg.
The contents shall be contained within two (2),
i 9.75 inch diameter by 12 inch high sealed stainless steel cans.
Empty stainless steel cans will be used to make up the remaining space within the inner containers.
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Page 3 - Certificate No. 5768 - Revision No. 4 - Docket No. 71-5768 (iii) For the contents described in 5(b)(1)(ii):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed 2.95 kg.
The contents shall be contained within three (3),
9.75 inch diameter by 12 inch high sealed stainless steel cans.
Empty stainless steel cans will be used to make up the remaining space within the inner container.
(iv) For the contents described in 5.(b)(1)(iii):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed four (4) kilograms.
(v) For the contents described in 5.(b)(1)(iv):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed five (5) kilograms.
Four (4). steel drums containing not more than 1.3 kilograms U-235 each shall be packaged in the shipping insert within the inner container as shown in Westinghouse Electric Corporation Sketch SKA-252-1 and Drawing C7108D10.
The steel drums shall be constructed in accordance with US Military Standard MS 24347 with a maximum ID of 8.5" and a nominal height of 15.4".
(vi) For the contents described in 5(b)(1)(v):
Total contents not to exceed 250 pounds, with the U-235 content not to exceed 3.5 kilograms.
The contents shall be transported in the inner container shown in Nuclear Materials and Equipment Corporation Drawing No. 10-F-676, Revision 2.
The inner container shown in Westinghouse Electric Corporation sketch SKA-252-1 shall be secured with twelve (12), 1/2"' diameter bolts.
(c) Fissile Class II and III
.(1) Minimum transport index to be shown on label for Fissile Class II.
(i)
For the contents described in 5(b)(1)(i),
5(b)(1)(iii),5(b)(1)(iv):
0.5 (ii)
For the contents described in 5(b)(1)(ii) and limited in 5(b)(2)(ii):
2.0 (iii)
For the contents described in 5(b)(1)(ii) and limited in 5(b)(2)(iii):
8.3 (iv)
For the contents described in 5(b)(1)(v):
0.7
Pag'e~4 - Certificate No. 5768 - Revision No. 4 - Docket No. 71-5768 (2) Maximum number of packages per shipment for Fissile Class III (i) For the contents described in 5(b)(1)(i),
5(b)(1)(iii), and 5(b)(1)(iv):
200 (ii) For the contents described in 5(b)(1)(ii) and limited in 5(b)(2)(ii):
59 (iii) For the contents described in 5(b)(1)(ii) and limited in 5(b)(2)(iii):
14 6.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
7.
Expiration darc October 31, 1980.
REFERENCES r
Combustion Engineering, Inc. application dated September 11, 1972.
Supplements dated:
December 19, 1973 and March 8, 1974.
Westinghouse Electric Corporation letter dated July 13, 1973.
General Electric Company lette'r dated March 30, 1973.
The Babcock & Wilcox Company letter dated February 16, 1977.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION t'
A~
Charfes E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety 10 W Date:
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