ML20039F128
| ML20039F128 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 12/18/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20039F126 | List: |
| References | |
| NUDOCS 8201120024 | |
| Download: ML20039F128 (6) | |
Text
Forrr. NFIC418 U.s.. NUCLEAR StEGULAToRY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R For Radioactive Materizls Pschages 1.ta) Ce*tificat de" 1.(b) Revision No.
1.(c) P P f o
1.(d) Pa No. 1.fel Totg No. Pages 2 PRE AMBLE 2.la)
This cervficate is inued to satisf y Sections 173.333a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 1701E9 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 m item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations Pert 71,
- Packaging of Reioactive Materials for Transport and Transportation of Radioactive Material Under Ce tain Conditions."
2.tc)
This certificate ooes not relieve the consignor from compisance with any recuirersent of the regulations 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 cf a safety analysis report of the package design or apolication-3.(a)
Prepared by (Name and addres:)-
3.lb)
Tit 6e and identification of roert or application:
~
General Electric Company General Electric Company application dated P. O. Box 460 January 8, 1969, as supplemented.
Pleasanton, CA 94566 3.lcl Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requiremer:ts of Subpart D of 10 CFR 71, as appUcable, 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-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.
The 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 Protectite jacket width, in 68.0 Packaging weight, lbs 23,050 3
8201120024 811218.
~
Page 2'- Certificate No. 9044 - Revision No. 9 - Docket No. 71-9044
- 5'.
(a)
Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General i
l Electric Company Drawing Nos.:
212E255, Rev. 7 106D3973, Rev. 5 106D3986, Rev. 4 129D4687, Rev. 0 174F237, Rev. 4 129D4688, Rev. 1 135C5598, Rev. 2 106D3989, 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 mater.ial 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 of 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., and U0 fuel rods clad in zircaloy or stainless 2
steel.
Decay heat not to exceed 600 watts.
All fuel rods shall.
i be contained within a closed 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.
(iv) Irradiated UC and ThC fuel particles clad -in graphite and contained within a standard HTGR hexagonal cross-section graphite block.
i Decay heat not to exceed 600 watts. -Each graphite block'shall be contained withih a sealed cylindrical inner container constructed 1
in accordance with General Atomic Company Drawing No.,021583, Issue A, with three, 1/2-inch by 4-1/2-inch radial fins to proyide centering within the cavity.
~
1,400 grams U-235 equivalent mass in each inner container with no more than one inner container per' package.
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l Page 3 - Certificate fio. 9044 - Revision No. 9 - Docket !io. 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.
(vi)
Solid nonfissile irradiated metal hardware, reactor control rods (blades), reactor start-up sources, and segmented boron carbide tubes (tube contents not to exceed a Type A quantity).
l (vii)
Radioactive (Hot Cell) waste materials imobilized with cement grout and contained in a 55-gallon (or extended 55-gallon drum)
DDT Specification 17H or 17C steel drum, lid and closure. The Waste material must be packaged in accordance with the Procedural Outline of the Imobilization of Cell Waste Using Cement Grout, of the December 1,1981 supplement.
The cement grout must be at least 50 volume percent (estimated) of the drum contents and relatively uniformly distributed throughout the drum. ~At least 3/4" thick layer of grout must cover all radioactive waste contents.
Decay heat not to exceed 100 watts, and fissile material not to exceed 500 grams U-235 equivalent mass.
(c)
Fissile Class III Maximum number of packages (i)
Contents 5.(b)(1)(1), 5.(b)(1)(ii),
per shipment 5.(b)(1)(iii),or5.(b)(1)(vii):
Two(2);or (ii) Contents 5.(b)(1)(iv):
One (1) 6.
The U-235 equivalent mass is detemined 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 must be closed with a plug with a melting temperature of 200*F and the cask cavity must be filled with water with a 5-inch air space within the cask cavity.
When needed, sufficient antifreeze in the cask must be used to prevent damage to any component of the package due to freezing.
8.
For packaging of other than neutron sources, the cask must be delivered to a carrier dry and the cavity drain line must be closed with a plug which will maintain its seal at temperatures up to at least=620*F.
Page 4 - Certificate No. 9044 - Revision No. 9 - Docket No. 71-9044 9.
Shoring must be provided to minimize movement of cortents during accident i
conditions of transport.
10.
Prior to each shipment the silicone rubber lid gasket (s) must be inspected.
This gasket (s) must be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.. Cavity drain line must be sealed with appropriate sealant applied to threads of pipe plug.
11.
For packaging of neutron sources, measurements must be made to detemine that the dose rate does not' exceed 1,000 mrem /hr at 3 feet from the surface of a dry cask with no additional shielding within the cask.
- 12. The contents described in 5.(b)(1)(v) must be transported on a motor vehicle, railroad car, aircraft, inland water crafts, or hold or deck of a seaaoing vessel assigned for sole use of the licensee.
- 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: March 31, 1982.
' REFERENCES General 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 Augus.t 31 and December 1,1981.
l Nuclear Plant Services supplement dated: July 7, 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Sk
%h Charles E: MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Materials Safety Date: DEC 181931 ie
U.S. Nuclear Reculatory Commission Transportation Certification Branch Approval Record Model No. GE-1600 Docket No. 71-9044 By application dated December 1,1981, General Electric Company requested an amendment to Certificate of Compliance No. 9044 to permit additicnal contents for the Model No. GE-1600 packaging.
The applicant proposes to immobilize contaminated particles present on radioactive waste materials generated in their Vallecitos Nuclear Center (VNC) Hot Cell Complex by grouting the wastes into 55-gallon drums which are then placed within the Model No. GE-1600 shipping package.
The grouted fom of the waste material is intended to assure adequate containment of the radioactive material to satisfy the requirements of 10 CFR Part 71 for normal conditions of transport and accident damage conditions.
The applicant has shown that the configuration of the grouted drums is maintained for normal conditions of transport, and that the radioactive wastes maintain their protective coating of grout.
Thus, the fom of the material precludes release of radioactive contamination particles for nomal conditions of transport.
The applicant has tested grout samples, and used the results to demonstrate that there can be no significant release of radioactive material for the package when wastes are shipped in the grouted form.
A sample grout cylinder was tested to determine the extent of damage to ths waste in grouted fom when subjected to accident damage tests of 10 CFR Part 71.
The extent of cracking, and the amounts and sizes of fragments and powder produced by the failed grout was detemined from the test. The tests results were used along with reasonably conservative estimates of the contamination product release fractions and mechanisms ta estimate the maximum quantities of radioactive material that could be released.
The driving force was assumed as the maximum internal pressure due to expanded gas within the drum, heated to maximum temperature predicted for the fire test. The applicant estimated that the maximum quantities of mixed fission products (MFP) and Co-60 released would not exceed 0.018 Ci and 0.01 Ci, respectively. This is well within the criteria recommended by Regulatory Guide 7.4 for Type B(M) packages: 0.4 Ci and 7 Ci over one week for MFP and Co-60, respectively. Thus, the fom of the material limits the maximum release of radioactive material for accident damage conditions of quantities that are sufficiently insignificant to satisfy the containment regiments of 10 CFR Part 71.
2 In addition, the applicant requested that the previously required sealed
~
secondary containers for the shipment of irradiated segmented boron carbide ~ tubes be deleted. The. certificate has been revised to limit the dispersible material'(B C) to a Type A quantity of radioactive material.
4 Thus, the amount of' radioactive material contained within the B C and i
available for release under accident conditions, could not exce8d a Type j
A quantity.
The requested approval of the revised drawings (submitted October 2, 1981) for the Model No. GE-1600 packaging was not approved at this time because of the concerns raised in our letter to the a~pplicant on November 12, 1981.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS DatePEC 1 3 1981 9
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