ML20126C297
| ML20126C297 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 03/14/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20126C292 | List: |
| References | |
| NUDOCS 8003280607 | |
| Download: ML20126C297 (4) | |
Text
7 O. .
Fcrm NRC418 U.S. NUCLE AR REGULATORY COMMISSION U ' CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materials Packeges 1.tel Certificate Number 1.(b) Revision No. 1.(c) Package identification No. 1,(d ) Pages No. 1.(e) Total No. Peges 9019 3 USA /9019/B( )F 1 3
- 2. PRE AMBLE 2.ta) This certificate is issued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Departmoset 'of Transportation Heza'dous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10e and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), es amended.
2.(b) The packaging and contents described in item 5 below, rnests the safety standards set forth in Subpart C of Title 10, Code vf Federal Requietens. Port 71,"Peckaging of Radioactive Materials for Transport and Transportetion of Radioactive Meterial 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 reguletory agencies, including the government of any country through or into which the package will be transported.
- 3. This cartificate is issued on the basis of a safety onelysis report of the package design or application-3.(a) Prepared by (Narne and address): 3.(b) Title end identification of report or applicatiori:
General Electric Company General Electric Company application. dated P.O. Box 780 May 24,1974, as supplemented. l Wilmington, NC 28401 3.(ci Dock. No. 71-9019
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpert D of 10 CFR 71.as applicabie.and the conditions specified
- in item 5 below.
- 5. Description of Peckaging eno Authorized Contents. Model Nurnber, Fiuile Ctess. Other CoNitions, and
References:
(a) Packaging (1) Model No.: BU-7.
(2) Description The packaging consists of either two, 5-gallon or three, 2.5-gallon, l 11,25-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 steel drum by solid insulating material composed of fire-retardant phenolic foam. The maximum weight of the package is 282 pounds. l (3) Drawing The container is constructed in accordance with Fitj. 1.8.1 of General l Electric Company's application dated March 14, 1980.
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6W 3200 w
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Page 2 - Certificate No. 9019 - Revision No. 3 - 00cket No. 71-9019 (b) Contents (1) Type and form of material (1) Uranium oxide powder with a maximum bulk density not greater than 2.3 grams /cc. Uranium nay be enriched to not more than 4.0 w/o in the U-235 isotope. The maximum H/V atomic ratio considering all l sources of the hydrogenous material within the inner container shall not exceed 0.45.
(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 per package (i) For the contents described in 5(b)(1)(1):
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 UO2 Maximum UO2 enrichment, per pail, per package, w/o kas kas 3.0 30.0 60.0 3.2 30.0 60.0 3.4 30.0 60.0 3.6 30.0 60.0 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 UO2 Maximum UO2 enric hment, per pail, per package, w/o kas kas 2.7 30.0 60.0 2.8 30.0 60.0 2.9 30.0 60.0 3.0 30.0 60.0 3.2 30.0 60.0 3.4 30.0 60.0 3.6 28.5 57.0 3.8 26.4 52.8 4.0 24.7 49.4
I Page 3 - Certificate No. 9019 - Revision No. 3 - Docket No. 71-9019 I
(c) Fissile Class
- 6. For mixtures of contents (powders and pellets) described in 5(b)(1), the maximu;n quantity of material per package shall be limited to the quantity given in S(b)(2)(ii).
- 7. For mixtures of contents as described in 5(b)(1)(i), ammonium oxalate (AO) and/or anrnonium bicarbonate (ABC) additives are permitted in the U02 Powder provided that their presence is taken into account in the determination of the H/U ratio in the package as follows:
Ng (water) + Ng (additive) + 0.038 NC(additive)
H/U =
Ng WO2 powder)
< 0.45 l
= atom density of hydrogen in the U02 Powder Where NH(water) mixture in the form of water .
l li g (additive) = atom density of hydrogen in the U02 powder mixture in the form of A0 and/or ABC NC (additive) = atom density of carbon in the U02 powder mixture in the form of A0 and/or ABC ,
4 l
Ng = atom density of uranium in the U02 powder mixture
- 8. The density of the package insulation shall not be less than 8 lbs/cu ft for the side and bottom and 20 lbs/cu ft for the top.
- 9. The four,1/4-inch diameter holes located near the top of the outer DOT Speci- ;
fication 17H steel drum as shown in Fig.1.8.1 shall be covered with weatherproof l tape to preclude the entry of water.
- 10. An alternative to the S5-gallon capacity D0T Specification 17H steel drum is ,
a drum meeting all requirements of the Specification 17H except the drum may have l two (2) rolling hoops. l
- 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b) ,
- 12. Expiration date: July 31, 1984.
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Page 4 - Certificate No. 9019 - Revisien ilo. 3 - Docket No. 71-9019 !
REFERENCE General Electric Company application dated May 24, 1974.
Supplement dated: March 14,1980.
FOR THE V.S. NUCLEAR REGULATORY COMMISSION
) m ar es E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety ,
Date: MAR 141980 o
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