ML19338C401
| ML19338C401 | |
| Person / Time | |
|---|---|
| Site: | 07109050 |
| Issue date: | 08/04/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19338C383 | List: |
| References | |
| NUDOCS 8008150358 | |
| Download: ML19338C401 (3) | |
Text
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.V Form NRC 618 U.S. NUCLEAR REGULATORY CoMMISSloN 1
H2 731 CERTIFICATE OF COMPLIANCE 3g gpq 7, For Radioactive Materials Packages
)
1 1.tal Certificate Nurrser 1.ib) Revision No.
1.f c) Packaos identification No.
1.(d) Pages No. 1.(e) Total No. Pages 9050 2
USA /9050/B( )
i 3
- 2. PREAMBLE 2.fal This certificate is essued to satisfy Sections 173.393a.173.394,173.395. and 173.396 of the Deoartment of Transportation Hazardous Materials Requistions (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the espartment of Transportation cangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.tbl The packaging and coritents 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 Certsen Conditions.**
2.(c)
This certificate does not relieve the corsegnor from compliance with any reovirement 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 peckage will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or aposication-3.fal Prepared by (Name and address):
3.fb)
Title and identification of report or application:
General Electric Company General Electric Company application dated l
P. O. Box 460 April 18, 1980, as supplemented.
Pleasanton, CA 94566 3.tc) oocket No. 7].9050 4 CoNOITIONS This certificate is conditional uport the fulfilling of the recuirements of Subpart D of 10 CFR 71. as applicable. and the condit ons specified i
in item 5 below.
- 5. oescription of Packaging and Autnorited Contents. Model Numoor. Fissde Class, otner Conditions, and
References:
(a) Packaging (1) Model No.:
GE-900 (2) Description Steel encased lead shielded shipping cask.
A double-walled steel cylinder protective jacket encloses the cask during transport.
It is bolted to a steel pallet.
The cask is closed by a lead-filled flanged plug fitted with a silicone rubber gasket and bolted closure.
The cavity drain line is closed by a stainicis steel pipe plug.
The physical description is as follows:
Cask height, in 22.6 Cask diameter, in 20.0 Cavity height, in 3.0 Cavity diameter, in 3.0 Lead shielding, in
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Protective jacket height, in 26.9 Protective jacket width, in 32.0 Packaging weight, lbs 3,750 800815036F
Page 2 - Certificate No. 9050 - Revision No. 2 - Docket No. 71-9050 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
277E418 (Budd Co. No. 1-559, Mark D) 106D3976, Rev. 1 277E409, Rev. 2 106D3983, Rev. 1 (b) Contents (1) Type and form of material (i) Byproduct material meeting special form requirements of 10 CFR 671.4(o);
or (ii) Solid non-fissile irradiated metal hardware.
(2) Maximum quantity of material per package Radioactive decay heat not to exceed 400 watts.
6.
Shoring shall be provided to minimize movement of contents during accident conditions of transport.
7.
Package contents shall be delivered to a carrier dry.
8.
Prior to each shipment the silicone rubber lid gasket shall be inspected.
This gasket shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
Cavity drain line shall be sealed with appropriate sealant applied to threads of pipe plug.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date:
July 31, 1985.
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Page 3 - Certificate No. 9050 - Revision No. 2 - Docket No. 71-9050 REFERENCES General Electric Company application dated April 18, 1980.
l Supplements dated:
February 20 and 27, 1969.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION f
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety 1
0 Date:
T l
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