ML19309C060
| ML19309C060 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 03/18/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19309C058 | List: |
| References | |
| NUDOCS 8004080097 | |
| Download: ML19309C060 (4) | |
Text
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l FC'rm NRC418 '
U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materials Packages 1.4) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 4014' 4
USA /9019/B( 1F 1
3
- 2. PREAMBLE 2.(a)
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 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous 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," Packaging 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.la)
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, as supplemented.
Wilmington, NC 28401 3.(c)
Docket No.
7].g0]g
- 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 Conditions, and
References:
(a)
Packaging (1) Model No.:
BU-7.
(2) Description The packaging consists of either two, 5-gallon o'r 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 _ D0T Specification 17H steel drum by solid insulating material composed of fire-retardant phenolic foam. The maximum weight of the package is 320 pounds.
l (3) Drawing The container is constructed in accordance with Fig.1.8.1 of General Electric Company's application dated March 14, 1980.
i l
800.4080097
4 Pag 2 - Certificate No. 9019 - Revision No. 4 - Docket No. 71-9019 (b) Contents (1) Type and form of material (i) Uranium oxide powder with a maximum bulk density not 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 atomic ratio considering all 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 U0 Maximum U0 2
2 enrichment, per pail, per package, w/o kqs kas 3.0 35.0 70.0 3.2 35.0 70.0 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 Maximum U0 2
2 enrichment, per pail, per package, w/o kgs kgs 2.7 35.0 70.0 2.8 35.0 70.0 2.9 35.0 70.0 3.0 35.0 70.0 3.2 34.1 68.2 31. 0 62.0 3.4 3.6 28.5 57.0 3.8 26.4 52.8 4.0 24.7 49.4
Page 3 - Certificate No. 9019 - Revision No. 4 - Docket No. 71-9019 (c) Fissile 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.
For mixtures of contents as described in 5(b)(1)(i), ammonium oxalate (A0) and/or ammonium 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:
g (water) + N (additive) + 0.038 NC(additive) fi H
H/U =
Ng (U02 powder)
< 0.45 Where liH(water)
= atom density of hydrogen in the UO2 powder mixture in the form of water NH (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 N
= atom density of uranium in the U02 powdermixture g
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 D0T Speci-fication 17H steel drum as shown in Fig.1.8.1 shall be covered with weatherproof tape to preclude the entry of water.
- 10. An alternative to the 55-gallon capacity D0T Specification 17H steel drum is a drum meeting all requirements of the Specification 17H except the drum may have two (2) rolling hoops.
- 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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Paga 4 - Certificate No. 9019 - Revision No. 4 Docket No. 71-9019 REFERENCES General Electric Company application dated May 24, 1974.
Supplements dated: March 14 and 17,1980.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION lEnt Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date: MAR 181980 t
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