ML19320A678
| ML19320A678 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 06/18/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Cunningham G GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19320A679 | List: |
| References | |
| NUDOCS 8007020500 | |
| Download: ML19320A678 (2) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION L i E
WASHINGTON, D. C. 20555 S
%.. *....o JUN 181980 FCTC; RHO 71-5942 General Electric Company ATTN: Mr. G. E. Cunningham P.O. Box 460 Pleasanton, CA 94566 Gentlemen:
Enclosed is Certificate of Compliance No. 5942, Revision No. 4, for the Model No. GE-700 shipping package. This certificate supersedes, in its entirety, Certificate of Compliance No. 5942, Revision No. 3, dated January 23, 1980.
Changes made to the enclosed certificate are indicated by vertical lines in the margin.
Those on the attached list have been registered as users of this package under the general license provisions of 10 CFR 571.12(b) or 49 CFR fl73.393a.
This approval constitutes authority to use this package for shipment of radioactive materal and for the package to be shipped in accordance with the provisions of 49 CFR 5173.393a.
Sincerely, M!
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated cc: w/ encl Mr. Richard R. Rawl Department of Transportation 8007020 E
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Model No. GE-700 Packaging USA /5942/B( )F
/
Addresses: w/ encl Ltr dtd:
JUN 18 ;980 Allied Chemical Corporation ATTN: Mr. F. H. Anderson 560 Second Street Idaho Falls, ID 83401 General Electric Compar,y ATTN: Mr. G. E. Cunningham P.O. Box 460 Pleasanton, CA 94566 Lawrence Livermore Laboratory
~
' ATTN: Mr. Stephen Chin P.O. Box 808 Livermore, CA 94550.
Los Alamos Scientific Laboratory ATTN: Mr. John Ramsay P.O. Box 990 Los Alamos, CA 87545 Nuclear Engineering Company
- ATTN:
Dr. Thomas S. Baer P.O. Box 7246 Louisville. KY 40207 Southwest Nuclear Company ATTN: Mr. James L. Harvey 7066-A Commerce Circle Pleasanton, CA 94566 University of Missouri ATTN: Mr. Don M. Alger Research Park.
Columbia, MO 65201 hM, r-n
m F;rm NRC418 U.S. NUCLEAR REGUt.ATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 C A 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pepts No. 1.te) Total No. Pages 5942 4
USA /5942/B( 4 1
7
- 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 CFft 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.
2.(b)
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 4
Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any recuirement of the regalations of the U.S. Department of Transportation 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.la)
Prepared by (Name and address):
3.(b)
Title and identification of report or' application:
General Electric Company General Electric Application dated March 18, 1980, P.O. Box 460 as supplemented.
Pleasanton, CA 94566 3.(c)
Docket No. 71 - 5?42
- 4. CONDITIONS This certificate is conditional upon the fulfitting of the requirements of Subpart D of 10 CFR 71, as applicable and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents. Model Number, Fissile Class, Other Conditions, 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 baseplate. The cask 1
is a double-walled steel circular cylinder, 37-inch-diameter by 65-inch high with a central cavity 15-inch-diameter by 40-inch high. Approximately 10.25 inches of lead surround the central cavity.
The cask is equipped with a cavity drain line, pressure relief valve set at 100 psig, and lifting device.
Closure is accomplished by a silicone rubber 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 high cavity extension with an additional. silicone rubber gasket.
The modified cask is 79 inches high l
and weighs 28,000 pounds.
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
237E325. Rev. 2 289E646, Rev. 3 106D4150, Rev. 0 289E647 Rev. 1 I
106D4331 Rev. 0 289E642, Rev. 2 l
195F127, Rev. 0 12904059, Rev. 1 800702g 3 06
- Page 2 - Certificate No. 5942 -' Revision No. 4 - Docket No. 71-5942 j
5.
(b) Contents
-(l) 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 weight 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 i',
(v) :those values presented in Figure 1 U0, Weight Limits for Model 700 Shipping Container, of Exhibit A to this application, 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 than 510 gm U-235 and inserted in the spaced stainless steel fuel shipping basket described in GE Drawing No. 10604150, Rev. O.
(vii). 6,200 gm U-235, provided the fuel is in the form of MURR TRTR type 4
elements containing not more than 775 gm U-235 per element; loaded and
-spaced in the stainless steel fuel shipping br.sket as described in MURR Drawing No. 1228, Sheets 1 thru 5, Revis1on O.
Fuel elements shall have at least 150 days cooling time since last reactor operation.
(3) Maximum quantity of radioactive decay heat per package (i) 6,500 watts for dry shipments, or I
(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 i
4 Maximum _ number of packages.per_ shipment 2
4 e
i.
Page 3 - Certificate No. 5942 - Revision No. 4 - Docket No. 71-5792 6.
The radioactive material shall be in the form of fuel rods, or plates, fuel assemblies, or meeting special form requirements of 10 CFR 571.4(o).
7.
Shoring shall be provided to minimize movement of contents during accident conditions of transport.
8.
Prior to each shipment'the silicone rubber lid gasket (s) shall be inspected. This gasket (s) 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 applicant shall confirm annually that the pressure relief valve is operable at 100 psig.
- 10. Len needed, sufficient antifreeze in the cask shall be used to prevent damage of any component of the package due to freezing.
- 11. The total radioactivity in the coolant shall not exceed the limits specified in 10 CFR571.36(a)(2).
- 12. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 13. Expiration date: June 30, 1985.
l REFERENCES General Electric application dated liarch 18, 1980.
l Additional Reference Required for the Contents Limited In Item 5.(b)(2)(vii).
University of Missouri letter dated March 20, 1980.
Appendix 6-A regarding University of Missouri's quality assurance program is not considered part of this application.
FOR THE U.S. NUCLEAR REGULATORY C0W4ISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date: