ML20003H411
| ML20003H411 | |
| Person / Time | |
|---|---|
| Site: | 07109070 |
| Issue date: | 04/30/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20003H408 | List: |
| References | |
| NUDOCS 8105050811 | |
| Download: ML20003H411 (3) | |
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION ti2 3)
CERTIFICATE OF COMP'LIANCE 3n g p 7, For Radioactive Materials Packages 1.(1) Certificate Number 1.(b) Revision No.
1.lc) Package identification No.
1.(d) Pages No. 1.(e) Total No. Pages 4070 8i IK A /Q070 /53 / W 1
'2
- 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 Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
-e 2.lb)
The packaging and contents described in item 5 below, rneets 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 <soes not relieve the, consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other snrlicable 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 apodication-3.(a)
Propered by (Name and address):
3.(b)
Title and identification of report or application:
Nuclear Packaging, Inc.
Nuclear Packaging, Incorporated 815 South 28th Street application dated June 21, 1976, Tacoma, WA 98409 as supplemented.
E 3.(c)
Docket No.
7].g070
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpert D of 10 CFR 71, ar applicable, and the conditions specified in item s b.ior.
- 5. Description of Packaging rid Authorized Contents, Model Number, Fissile Class, Other Conditir ns, and Referenas:
(a) Packaging (1) Model No.: N-55 (2) Description A low carbon steel overpack filled with rigid polyurethane 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 l
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-60-2000, Rev. C.
l T105 0 59 E// /
J Pag 2 2 - Certificate No. 9070 - Revision No. 5 - Docket No. 71-9070 (b) Contents (1) Type and form of material (1) Radioactive material including fissile material in the form of dry solids contained in 00T Specification 17H or 17C drums.
- Liquids, l
powders and slurries are not peraitted.
(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.
(2) Maximum quantity of material per package (1) 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 fissile plus fissile uranium provided the total Pu content ooes not exceed 200 grams, 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 gl78.34); 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 thickrassas 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 gontainment 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.
(3) Fissile Class II Minimum transport index to For the contents described in be shown on label 5(b)(1)(iii):
Five (5)
Page 3 - Certificate No. 9070 - Revision No. 5 - Docket No. 71-9070 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 571.12(b).
10.
Expiration date:
May 31, 1982.
REFERENCES Nuclear Packaging, Incorporated Safety Analysis Report dated June 21, 2976.
Supplements dated:
February 4, April 4, and May 6, 1977; October 10, 1980; and March 30, 1981.
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For The Contents Described In 5(b)(1)(ii) ard Limited In 5(b)(2)(ii):
Lawrence Livermore Laboratory application dated March 28, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMiSSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety APR 3 01981 Dste: