ML20032A024
| ML20032A024 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 10/14/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20032A014 | List: |
| References | |
| NUDOCS 8110280162 | |
| Download: ML20032A024 (5) | |
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- orm NRC418 U.S. NUCLE AR REGULATORY COMMISSION t;ERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.fsl Certifir:a e N mber 1.(b) Revisio No.
1.(c) a de t f e No.
1.(d) P es No. 1.(e) Togi No. Pages
- 2. PRSAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.3934,173.394,173.395, 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 Trennortation Dangerous Cargoes Regulations (46 CFR 146--149), as amended.
2.(b)
Tne 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 Certain Conditions."
2.(c)
This certificate does not relieve the consigmr from compliance with any requirement of the regulations of the U.S. Department of Transportat;on or other applicabia regulatory agencies, inc!uding 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.lal Prepared by (Name and address).
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated P. O. Box 460 January 8,1969, as supplemented.
Pleasanton, CA 91566 3.lc)
Docket No. 71-9044 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the ccnditions specified in item 5 ' elow.
o
- 5. Description of Packagina and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: GE-1600 (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. Jhe cavity is equipped with a drain line and the physical description is as follows:
Cask height, in 67.5 Cask diameter, in 38.5 Cavity height, in 54.0 Cavity diameter, in 26.5 Lead shielding, in 5.0 Protective jacket height, in 81.4 Protective jacket width, in 68.0 Packaging weight, lbs 23,050 Yo?lo@lj4 PDR
Page 2 - Certificate No. 9044 - Revision No. 8 - Docket No. 71-9044 5
(a)
Packaging (continued) 7 (3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
212E255, Rev. 7 106D3973, Rev. 5 106D3986, Rev. 4 12904687, Rev. 0 174F237, Rev. 4 129D4688,'Rev. 1 135C5598, Rev. 2 106039 %, Rev. 1 913E307, Rev. 1 (b)
Contents (1) Type, form and maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements; and (i) Byproduct material and special nuclear material as solid metal or oxides.
Decay heat not to exceed 600 watts. ~The radioactive material shall be in the form of fuel rods, or plates, fuel assemblies, or meeting special form requirements ( f 10 CFR 571.4(o).
500 gm U-235 equivalent mass; or (ii) Neutron sources in special form.
500 gm U-235 equivalent mass.
Decay heat not to exceed 50 watts; or (iii)
Irradiated Pu0,3 and 00 fuel rods clad in zircaloy or stainless 2
steel.
Decay heat not to exceed 600 watts. All fuel rods shall be contained within a cicsed 5-inch Schedule 40 pipe with a maximum useable length of 39-5/8 inches.
1,200 gm fissile material with no more than 300 gm fissile material per 5-inch Schedule 40 pipe.
I (iv) Irradiated UC and ThC fuel particles clad in graphite and contained within a standard HTGR hexagonal cross-section graphite block.
Decay heat not to exceed 600 watts.
Each graphite block shall be contained within a sealed cylindrical inner container constructed in accordance with G.:neral Atomic Company Drawing No. 021583, 1; sue A, with three, 1/2-inch by 4-1/2-inch radial fins to provide centering within the cavity.
1,400 grams U-235 equivalent mass in each inner ccntainer with no mre than one inner container per package.
A
Page 3 - Certificate No. 9044 - Revision No. 8 - Docket No. 71-9044 5.
(b)
(1)
Contents (continued)
(v)
Process solids, either dewatered, solid, or solidified in a secondary sealed container meeting the requirements for low specific activity radioactive material.
t Solid nonfissile irraciated met'l hardware, reactor control rods (vi) a (blades),reactorstart-upsources,andsegmentedboroncarbide tubes contained in a secondary sealed container (s).
(c) Fissile Class III or5.(b)(1)(b)(1)(i),5.(b)(1)(ii),
Maximum number of packages (i)
Contents 5. (iii):
per shipnient Two(2);or i
(ii) Contents 5.(b)(1)(iv):
One(1) 6.
The U-235 equivalent mass is determined by U-235 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.
7.
For packaging of neutron sources, the cavity drain line shall be closed with a plug with a melting temperature of 200*F and the cask cavity shall be filled with water with a 5-inch air space within the cask cavity. When needed, sufficient antifreeze in the cask shall be used to prevent damage to any component of the packsge due to freezing.
8.
For packaging of other than neutron sources, the cask shall be delivered to a carrier dry and the cavity drain line shall be closed with a plug which will maintain its seal at temperatures up to at least 620*F.
9.
Shoring shall be provided to minimize movement of contents during accident conditions of transport.
- 10. 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.
11.
For packaging of neutron sources, measurements shall be made to determine that the dose rate does not exceed 1,000 mrem /hr at 3 feet from the surface of a dry i
cask with no additional shielding within the cask.
- 12. The contents aescri-bed in 5.(b)(1)(v) shall be transported on a motor vehicle, railroad car, aircraft, inland water crafts, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
Page 4 - Certificate No. 9044 - Revision No. 8 - Docket No. 71-9044
- 13. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 14. Expiration date: December 31, 1981.
REFERENCES Genei.21 Electric application dated January 8, 1969.
Supplements dated: February 12, 20, and 27, and March 10 and 24,1969; November 20, 1970; January 29 and March 12, 1971; July 3 and November 15, 1973; December 4, 1979; August 26, 1980; and August 31, 1981.
Nuclear Plant Services supplement dated:
July 7, 1975.
FOR THE U.S. NUCLEAR REGULATORY CO M ISSIGN
[L
=Y Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Materials Safety Date:
I f
U.S. Nuclear Regulatory Commission I
Transportation Cartification Branch
[
Approval Record t
Model No. GE-1600 Docket No. 71-9044 By application dated August 31, 1981, the General Electric Company requested an amendment to Certificate No. 9044 to authorize additional contents consisting of irradiated segmented boron carbide tubes contained in secondary sealed containers.
The packaging has not been shown to provide containment for dry powder.
Dispersible material consists of B C, however, the total activity of 3
dispersible material does not exceHd a Type A quantity. As a practical matter it is unlikely that more than a Type A quantity of B C would be 4
available for release under accident conditions.
Ab Charles E. MacDona'id, 'Ch ef Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS 00T 14 E81 Date:
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