ML20027C019
| ML20027C019 | |
| Person / Time | |
|---|---|
| Site: | 07106703 |
| Issue date: | 10/01/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20027C015 | List: |
| References | |
| NUDOCS 8210120192 | |
| Download: ML20027C019 (3) | |
Text
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o Forni NRC418 U.S. NUCLEAR REGULATORY COMMIS$10N
- U CERTIFICATE OF COMPLIANCE 10 CFR 71 lor Radioactive Materials Packages l'
4 1 (b) Revisica No.
1.(c) Package identificat Pages No. 1.(e)Iotal No. Pages j
6703 3
USA /6703/B( ) ion No.1,(d) 1 1.le) Certificate Number j
- 2. PREAMBLE 2.(s).This certificate is t. sued to satisfy Sections 171.393a,173.394,173.395, and 173.3GG of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 1C 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 packagb5 ?nd contents described in item 5 Mow, 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."
{
t 2.fc) This certificata 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 govn nment of any country through or into whide 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.(e)
Propered by (Name red address):
3.(b)
Title and identification of report or application:
f GA Technologies, Inc.
General Atomic Company application dated l
P.Os Box 81608 December 16, 1975.
San Diego, CA 92138 71-6703 3.(c)
Docket No.
. 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 e
in item 5 below.
t
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
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(a) Packaging (1) Model No.: RG-1
.}
(2) Description
)
The package, a thennoelectric generator, is 18 inches high and has a
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base diameter of 14 inches. The components include the main housing, uranium and tungsten shield, housing flange, electrical connector and lifting lugs. A notch at the base provides the tie-down flange. The 1.75-inch thick cover flange is bolted to the housing by 16 or 20 steel bolts depending on the generator configuration.
The electrical receptacle is bolted to the cover flange with an 0-ring being provided between the interfaces and on the lateral surface of the feed plug.
The lifting lug is threaded into the cover flange and is removable if necessary for an operational installation.
Package weilght is approximately 800 pounds.
s t
s a
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4 8210120192 821001 PDR ADOCK 07106703 C
Page 2 - Certificate No. 6703 - Revision No. 3 - Docket No. 71-6703 F
5 (a) Packaging (continued)
(3) Drawings:
The packaging 16-Bolt configuration is constructed in accordance with the detailed drawings listed on Gulf General Atomics Generator Assembly Drawing fio. 1699-0001, and modified for the 20-bolt configuration by Drawing !!os.: J346-3000, Rev. K; D346-3020, Rev. F; and D346-3021, Rev. G.
(b) Contents (1) Type and form of material Strontium-90 titanate doubly encapsulated in a Type 304L stainless steel liner and Hastelloy C capsule.
'2) Maximum quantity of material per package 8,300 curies.
6.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12(b) 7.
Expiration date: February 28, 1985.
REFERENCE General Atomic Company application dated December 16, 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION 4
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety 2
Date:
4
e
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U.S. Nuclear Regulatory Commission T'ransportation Certification Branch Approval Record By application dated June 23,1982, as supplemented, General Atomic Company requested that Certificates of Compliance for the following packages be issued to GA Technologies, Inc. as a successor to the licensee:
Docket No.
Model No.
71-6346 FSV-1 t
71-6745 FSV-2 71-6347 FSV-3 71-9057 FPD-1 71-6703 RG-1 71-9034 TRIGA-1 71-9037 TRIGA-2 GA Technologics, Inc. letter dated August 30, 1982, adopts the General Atomic Company Quality Assurance program (Docket No. 71-0030), at the time it becomes the successor to General Atomic Company and to incorporate its own organizational structure into the program. The registration of GA Technologies, Inc. is to be effective upon its anticipated succession l
to General Atomic Company.
f Yk Charles E. HacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, N4SS OCT 11982 Date:
i e
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