ML19308C635
| ML19308C635 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 01/23/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19308C632 | List: |
| References | |
| NUDOCS 8002010032 | |
| Download: ML19308C635 (4) | |
Text
'D
\\)
Farm NRC418 U 3. NUCLEAR REGULATORY COMMISSION I'
CERTIFICATE OF COMPLIANCE
,g CFR 71 For Radioactive Materials Packages 1.tal Certificate Nurnber 1.(b) Revision No.
1.(c) Package identification No.
1.(d) Pages No_ 1.te) Total No. Pages 5942 3
USA /5942/B( )F 1
3
- 2. PREAM8LE 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 CF R 146-149), as arnereed.
2.(ts)
The packagmg and contents described in item 5 below, meets the safety standards set forth in Suopart C of Title 10, Code of Federal Aequiations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certam 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 applicaole regulatory agencies metuomg 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.(al Prepared by (Name and address):
3.(b)
Title and dentification of report or application:
General Electric Comapny General Electric Application dated December 23, P.O. Box 460 1968, as supplemented.
Pleasanton, CA 94566 3.f c) Docket No.
71-5942 4.
CONDIT'ONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71, as applicante, and the conditions specified m item S below.
- 5. Description of Packaging and Authorized Contents, Model Numoer, Fissde Class, Other Co eitions. and
References:
(a) Packaging (1) Model No.: GE-700 (2) Description A steel encased lead shielded shipping cask enclosed by a double-walled protective jacket of the same shape with a rectangular base-plate. The cask is a double-walled steel circular cylinder, 37-inch-diameter by 65-inch high with a central cavity 15-inch-diameter by 40-inen high. Approximately 10.25 inches of lead surround the central cavity. The cask is equipped with a cavity drain line and lifting device. Closure is accomplished by a gasketed and bolted steel lead filled plug. The maximum weight of the packaging is 23,000 pounds.
The cask may be modified with a 14-inch nigh cavity extension.
The modified cask is 79 inches high and weigns 28,000 pounds.
.f b~
8062010 NM
Page 2 - Certificate No. 5942 - Revision No. 3 - Docket No. 71-5942 5.
(a) Packaging (Continued)
(3) Drawings The packaging is constructed in accordance witn the following General Electric Company Drawings Nos.:
237E325, Rev. 2 106D4150, Rev. 0 106D4331, Rev. 0 195F127, Rev. 0 289E646, Rev. 3 l
289E647, Rev. 1 289E642, Rev. 2 12904059, Rev. I j
(b) Contents (1) Type and form of material Byproduct, source, and special nuclear material contained in solid or metal oxide form.
(2) Maximum quantity of material per package (i) 740 gm U-235, provided that the maximum U-235 enrichment does not exceed 6 weignt percent; or (ii) 1,200 gm U-235, provided that the fuel material is in the form of MTR-type fuel elements with a minimum active fuel length of 23 inches; or (iii) 220 gm fissile material; or (iv) 1,650 gm U-235, provided that the maximum U-235 enrichment does not exceed 3.5 weight percent and the fuel material is in the form of 88 rods loaded with 0.376-inch-diameter pellets with a minimum active fuel length of 37 inches; or (v) those values presented in Figure 1. UO, Weicht Limits for Model 700 Shipping Container, of GE application dated February 25, i
1970, applicable to fuel material in the form of rods with a minimum pellet diameter of 0.40-inch; or (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel elements (GETR Fuel) with each element containing no more i
than 510 gm U-235 and inserted in the spaced stainless steel fuel shipping basket described in GE application dated February 25, 1970 and GE Drawing No. 10604150, Rev. O.
4 I
Page 3 - Certificate No. 5942 - Revision No. 3 - Docket No. 71-5942 5.
(b) Contents (Continued)
(2) Maximum quantity of material per package (Continued)
(vii) 6,200 gm U-235, provided the fuel is in the form of MJRR TRTR type elements containing not more than 775 gm U-235 per element; loaded and spaced in the stainless steel fuel shipping basket as described in MURR Drawing No. 1228, Sheets 1 thru 5, Revision 0.
Fuel elements shall have at least 150 days cooling time since last reactor operation.
(3) tiaximum quantity of radioactive decay heat per package (i) 6,500 watts for dry shipments, or (ii) 1,500 watts for wet shipments, provided that the cavity shall contain at least a 1,000 cu in air void (at standard temperature and pressure) at the time of delivery to a carrier for transport.
(c) Fissile Class III Maximum number of packages per snipment 2
6.
Tne material specified in Paragraph 5.(b)(1) shall be clad, encpasulated, or contained in a metal encasement of such material and construction as to with-stand the combined effects of internal heat load and the 1475 fire with the closure pretested for leak tightness or in accordnace with the statements and representations contained in GE application dated February 4,1969. Shoring may be provided to minimize movement of contents during transport.
7.
The applicant shall confirm annually that the p'ressure relief valve is operable at 100 psig.
8.
When needed, sufficient antifreeze in the cask shall be used.to provent damage of any component of the package due to freezing.
9.
The total radioactivity in the coolant shall not exceed the limits specified in 10 CFR 571.36(a)(2).
- 10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 11. Expiration date: April 30,1980.
71-5942 Pa9e 4 - Certificate flo. 5942 - Revision No. 3 - Docket No.
REFERENCES General Electric application dated December 23, 1968.
Supplements dated:
February 4, 8, and 27, 1969; February 25,1970; April 4 and June 7,1972; and December 3,1979.
l Additional References Required for the Contents Limited In Item 5.(b)(2)(vii).
University of Missouri application dated January 10, 1979.
Supplement dated: May 22,1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and 14terial Safety M 311980 Date: