ML20009H331
| ML20009H331 | |
| Person / Time | |
|---|---|
| Site: | 07105980 |
| Issue date: | 07/28/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20009H328 | List: |
| References | |
| NUDOCS 8108070271 | |
| Download: ML20009H331 (4) | |
Text
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i Farm NRC418 U.S. NUCLEAR REGULATORY QoMMissioN 3
to C R g CERTIFICATE Or COMPLI ANCE For Radioactive Materials Packages 1.( ) Certifecate Number 1.(b) Revision No.
1.(c) Package identification No.
1.(d) Pages No. 1.(e) Total No. Peges M
A USA /5990/ ( )F
?
- 2. PRE AMBLE 2 a)
This certificate is issued to satisfy sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Ha.zardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and sections 14C-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended i
2 (b) The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regvations, Part 71. " Packaging of Radioactive Materials for Transport and Transportation cf Radioactive Material Under Certain Conditions."
I' This certificate does not relieve the consignor from compli oce with any requirement of the regulations of the U.S. Department of l
2.(c)
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.(a), Prepared by (Name and address):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated l
P. 0. Box 460 October 10, 1979, as supplemented.
j
.Pleasanton, CA 94566 3.k oocket No.
- 4. CONDITIONS l
This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified I
in item 5 below.
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- 5. Desctf' a}n oPackaging i
Packaging and Authorized Contents. Model Number, Fissile Class, Other Conditions, and
References:
(1) Model No.:
GE-600 (2) Description A steel encased lead shielded shipping cask.
The basic cask body is a cylinder 34 inches in diameter by 60 inches high formed by two concentric steel shells whose annular region is filled with 6 inches of lead.
The cavity is 20-1/2 inches 10 by 46 inches high, 3/8-inch thick stainless steel cylinder.
A recessed plug-type cask lid, consisting of a steel weldment filled with lead, is secured to the cask body by six, 1-inch diameter steel bolts.
A silicone rubber gasket provides tne sea'.
A protective jacket consisting of a double-walled structure of 1/2-inch thick carbon steel plates is placed over the cask and bolted to a steel i
pallet by eight, 2-inch diameter steel bolts.
The cask has one 1/2-inch l
diameter drain line from the cavity to the outer shell.
The cask is shipped in the upright position.
The total weight of the package is approximately 18,500 pounds when loaded.
8108070271 810728 PDRADOCK0710Sg C
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d Page 2 - Certificate No. 5980 - Revision.'!o. 6 - Docket No. 71-5980 5.
. (a). ~ Packaging (continued)
(3) Drawings The packaging is constructed in accordante with the following General Electric Company Drawing Nos.:
212E247, Rev. 5-106D3892, Rev. 3 10603898,~ Rev. 3 12904685, Rev. O' 144F650, Rev. 1 129046E4, Rev. O i'
693C293, Rev. 3 195F162 Rev. 0 161F470, Rev. 2 (b) Contents (1) Type and form of material (i) Byproduct material and irradiated special nuclear material in solid or solid oxide form, but specifically not loose powders.
Contents are to be clad, encapsulated or contained in a metal encasement of such material as to withstand the combined effects of the internal j
heat load and the 1475 F fire with the closure pre-tested for leak tightness.
Also, byproduct material and irradiated special nuclear j
material in special form.
(ii) Neutron sources in special 'orm.
(2) Maximum quantity of material per package
.A Plutonium in excen of twenty (20) curies per package must be in the form i
of met-i, metal alioy or reactor fuel elements, ar.d l
(i) For the contents described in 5.(b)(1)(i) the maximum uecay heat not to exceed 600 watts and the fissile content not to exceed 500 grams of U-235, 300 grams U-233, 300 grams Pu, or a prorated quantity of each such that the sum of the ratios does not exceed unity.
When
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the contents of this paragraph are in the form of irradiated reactor fuel, the fuel must have been cooled for a minimum of 90 days, and no more than 1000 Ci of noble gases must be available for release.8 from the fuel rod plenums.
The cask must be leak tight to 1 x 10 a
atm-cm /sec under normal conditions of transport; or (ii)
For the contents described in 5.(b)(1)(i) the maximum decay heat not to exceed 600 watts and the fissile content not to exceed 1200 grams fissile provided:
(1) the fissile material is contained in schedule waste liners constructed'of 5-inch schedule 40 pipe with a maximum inside length of 39-5/16 inches, (2) no more than four such liners are shipped at one time, (3) each liner contains no more than 300 grams fissile, and (4) the cask is provided with a positioning lattice to maintain separation between the liners.
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Page 3 - Certificate.No. 5980 - Revision No.'6 - Docket No.- 71-5980 (iii)-
For the contents described in'5(b)(1)(fi) the maximum decay heat not to exceed 50 watts and not more than 500 grams U-235 equivalent mass.
The external-dose rate not 'a exceed 1000 mrem /hr at 3 feet from the surface of.a package without internal shielding.
5.
(c) Fis 'le Class II and III l
(1)- Minimum transport index to For the contents specified in shown'on label for Class II 5.(b)(1)(i) and limited in 5.(b)(2)(1).
8.4 2
-(2) Maximum number of packages For the contents specified in per shipment for Class III.
5.(b)(1)(f) a'nd 5.(b)(1)(ii) and limited in 3.(b)(2)(ii) and.
5.(b)(2)(fii).
Two (2) 6.
The U-235 equivalent mass must be determined by the following method:
U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times i
Pu mass.
7.
Except for the neutron sources in special form (10 CFR 971.4(o)), the package contents must be dry and the fissile material unmoderated (H to X atomic ratio i
less than-2).
8.
For wet shipments the drain line must be closed with a plug which has a melting i
temperature of 200 F, and for dry shipments the drain line is closed with a solid stainless steel pipe plug.
9.
Prior to each shipment, the packaging primary lid closure seal must be inspected.
The primary lid closure seal must be replaced with a new seal if inspection shows any defects or every twelve (12) months, whichever occurs first.
10.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12(b).
j 11.
Expiration date:
December 31, 1984.
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.r Page 4 - Certificate No. 5980 - Revision ido. 6 - Docket No. 71-5980 REFERENCES G3neral Electric Company's application dated October 10, 1979.
-Supplements dated:
May 21, and October 8, 1980.
FOR THE U.S. NUCLEAP 'AEGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
JUL 2 51381
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