ML19262A741
| ML19262A741 | |
| Person / Time | |
|---|---|
| Site: | 07105768 |
| Issue date: | 11/30/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19262A740 | List: |
| References | |
| NUDOCS 7912100466 | |
| Download: ML19262A741 (5) | |
Text
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Form NRC4i18 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 CFR M 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 5768 2
USA /5768/AF 1
4
- 2. PREAMBLE 2.ta)
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 170-189 and '4 CFR 103) and Sections 146-10-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packsging and contents described in item 5 beiow, 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 Cond;. ions.**
g 2.(c)
This certificate does not relieve the consignor from comphance with any requirement of the egulations 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 i sued on the basis of a safety analysis report of the patiage design or application-3.(a)
Perpared by (Name and address):
3.(b)
Title and identification of report or application:
General Electric Company Combustion Engineering, Inc. epplication P.O. Box 780 dated September 11, 1972, as supplemented.
Wilmington, NC 28401 3.(c)
Cocket No.
71-5768 4 CONDITIONS This certificate is conditional upon the fulfihing 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 C: ass, Other Conditions, and
References:
(a) Packaging (1) Model No.: BB-250-2 (2) Description Inner ccntainer 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 weignt of packaging and contents is approximately 575 pounds.
(3) Drawings The 88-250-2 packcging is constructed in accordance with Westinghouse Electric Corporation sketch SKA-252-1 (Appendix L to Westingnouse Electric Corporation letter dated March 1,1968). Jhe outer cover is secured by either a 12-gage closure ring or six (6),1/2" diameter bolts.
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Page 2 - Certificate No. 5768 - Revision No. 2 - Docket No. 71-5768 (b) Contents (1) Type and form of material (i) Uranium oxide pellets. Uranium may be enriched
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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 con-tainer shall not exceed 1.5.
(ii) Uranium oxide enriched to a maximum 3.5 w/o in the U-235 isotope. Chemically-bound or pnysically-bound water in mixtures is permi'.ted.
Slips or slurries tnat exhibit a visually discernible liquid second phase are prohibited.
2 or U 0 ) powder with a maximum (iii) Bulk uranium oxide (UO 38 density of 2 g U/cc and enriched to a maximum 4 w/o in the U-235 isccope. The maximum H/U atomic ratio, con-sidering all sources of hydrogenous material within the inner container snall not exceed 1.13.
(iv) Uranium compounds which will not decompose at tem-peratures 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 nydrogenous 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 nydrogenous material within the
- ner container, snall not exceed 3.0.
(2) tiaximum 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 tne 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), 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. 2 - 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 con-tained 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 25C-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 tne 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 witn twelve (12),1/2" diameter bolts.
(c) Fissile Class II and III (1) Minimum transport indes, 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):
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Page 4 - Certificate No. 5768 - Revision No. 2 - Docket No. 71-5768 (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):
9.7 (2) Maximum number of packages per snipment for Fissile Class III (i) For the contents described in 5(b)(1)(i), 5(b)(l;(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 tne contents described in 5(b)(1)(ii) and limited in 5(b)(2)(iii):
14 6.
The package autnorized by this certificate is hereby approved for use under tne general license provisions of.10 CFR 571.12(b).
7.
Expiration date: February 28, 1980.
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Page 5 - Certificate No. 5768 - Revision No. 2 - Docket No. 71-5768 REFERENCE _S 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 letter dated March 30, 1973.
The Babcock & Wilcox Company letter dated February 16, 1977. '
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
- 1526, 308
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