ML19345B207
| ML19345B207 | |
| Person / Time | |
|---|---|
| Site: | 07109070 |
| Issue date: | 11/14/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19345B203 | List: |
| References | |
| NUDOCS 8011260340 | |
| Download: ML19345B207 (3) | |
Text
.
, ya Form NRC418 U.S. NUCLE AR REGULATORY CoMMISSloN
[CFR 71 CERTIFICATE OF COMPLIANCE Few Ra$icactive Materials Packages 1.fal Certificate Number 1.lb) Revesion No.
I tc) Package Identification No.
1.(d) Pages No. 1.fe) Total No. Pages 0070 1
llSA/0070/R( TF 1
1
- 2. PRE AMBLE 2.f al This certificate s essued to satisfy Sections 173.3934,173.394.173.395, and 173.396 of the oepartment of Transportation Hazardous 8
Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the oepartment of Transportation Dangerous Cargoes Regula* ions (46 CF R 146-149), as amended.
2.tbl The packaging and contents described in item 5 be6ow, 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 j
Certain Conditions!*
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. oepartment of Transoortation 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.f a) Prepared by (Name and address):
3.lb)
Title and identifscation of report or application:
i Department of Energy Nuclear Packaging Incorporated 1333 Broadway application dated June 21,,1976.
Oakland, CA 94612 3.lc) oocket No.
71-9070 4 CONDITIONS This certificate is conditional upon the fulfilling of the reouirements of Subpart o of 10 CFR 71, as applicable, and the conditions specified 2
],
in item 5 below.
- 5. Descript.on of Pacmaging and Authorized Contents. Model Number. Fissile Class. Other Conditions, and
References:
(a) Packaging (1) Model No.: N-55 (2) Description '
A low carbon steel overpack filled with rigid polyureth'ane foam.
The containment vessel is a 55 gallon drum, meeting the requirements of DOT Specification 17H or 17C.
The overpack is a right circular cylinder 48 l
inches high by 32 inches diameter with a 34-1/2-inch high by 24-inch diameter cavity.
The 20 gage galvanized steel shell is filled with 3 pound per cubic foot rigid polyurethane foam.
Closure of the upper and lower (lid and body) sections of the overpack is provided by four toggle clamps, and a neoprene gasket at the stepped joint between the two sections.
Four rings are provided for lifting and tie-down.
The package gross weight is approximately 750 pounds.
(3) Drawing The packaging is constructed in accordance with Nuclear Packaging, Incorporated Drawing No. X-60-200D, Rev. B.
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.801126o340
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Page 2 - Certificate No. 9070'- Revision No. 3 - Docket No. 71-9070 j
(b) Contents (1) Type and form of material f
(i) Radioactive material including fissile material in the form of dry l
solids contained in DOT Specification 17H drums.
Liquids, powders and slurries are not permitted.
(ii) Tritium absorbed on metal backing as titanium tritide held within the container-assembly shown in Lawrence Livermore Laboratory Drawing No. AAA-77-109723, Rev. B.
(iii) Dry, solid forms of plutonium and uranium.
l (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i) greater than Type A quantity radioactive material.
Fissile material contents not to exceed the generally licensed mass limits as specified in 10 CFR 571.11 and plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements.
Internal decay heat not to exceed 3 watts.
(ii) For the contents described in 5(b)(1)(ii) a maximum of six (6) container assemblies held within a DOT Specification 17H drum.
Maximum activity not to exceed 30,000 curies per package.
Internal decay heat not to exceed 1.08 watts per package.
(iii)
For the contents described in 5(b)(1)(iii), 200 grams Pu plus fissile uranium with a heat generation rate of 5 watts.
The radioactive material shall be packaged within sealed metal cans or DOT Specification 2R containers (49 CFR 9178.34); and placed within inner containers constructed as specified on Figures 1, 2, and 3, Appendix 1.10.1, of the application.
Stainless steel tubing wall thicknesses may be increased a maximum of 50 mils.
Prior to each shipment, a helium leak test shall be performed on both the inner and outer containment assemblies capable of detecting a leak no greater than 10 7 atm cc/sec at standard temperature and pressure.
Following the gas leak testing, all inner container welds shall be leak tested using a liquid penetrant method in accordance with Article 6,Section V, ASME Code.
No package with a detectable leak shall be delivered to a carrier for transport.
l (3) Fissile Class II Minimum transport index to For the contents described in be shown on label 5(b)(1)(iii):
Five (5) 9
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Page 3 - Certificate No. 9070'- Revision No. 3 - Docket No. 71-9070 4
6.
The maximum weight of contents including drum not to exceed 550 pounds.
7.
The drum must be securely positioned in the overpack.
8.
Contents must be securely positioned so that protrusions will not puncture the drum under normal or accident conditions.
9.
The packaging. authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12(b).
10.
Expiration date: May 31, 1982.
REFERENCES 4
Nuclear Packaging, Incorporated Safety Analysis Report dated June 21, 1976.
Supplements dated:
February 4, April 4, and May 6, 1977; and October 10, 1980.
]
For The Contents Described In 5(b)(1)(ii) and Limited In 5(b)(2)(ii):
Lawrence Livermore Laboratory application dated March 28, 1978.
i FOR THE U.S. NUCLEAR REGULATORY COMMISSION i
[h Charles E. MacDonald, Chief Transportation Certification Branch 4
Division of Fuel Cycle and 4
Material Safety NOV 141980 Date:
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