ML20051U017
| ML20051U017 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 04/30/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20051T864 | List: |
| References | |
| NUDOCS 8205180070 | |
| Download: ML20051U017 (6) | |
Text
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Form NR.C418 U.S. NUCLE AR REGULATO3Y COMMISSION U
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CERTIFICATE OF COMPLIANCE M CFR M F r Radioactive Materials Packages
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1.(2) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 9044 10 USA /9044/B( IF 1
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- 2. PRE AMBLE 2.f 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 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, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, **Packeging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.(c)
This certUicate does not relieve the t:onsignor from compliance with any requirement 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 v.ackage will be transported, m
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Propered 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 February 1,1982, as supplemented.
Pleasanton, CA 94566 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Descriotion 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:
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Cask height, in 67.0 Cask diameter, in 38.5 Cavity height, in 54.0 Cavity diameter, in 26.5 Lead shielding, in 5.0 Protective jacket height, in 81.88 l
l Protective jacket width, in 68.0 Packaging weight, lbs 25,700 l
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O Page 2 - Certifica+.e No. 9044 - Revision No.10 - Docket No. 71-9044 5.
(a)
Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
129D4735, Rev. 1 129D4736, Rev. 1 12904737, Rev. 2 129D4738, Rev. 1 Lifting and/or tie-down devices which are a structural part of the package must be in accordance with the above drawings.
(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 allcy 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 of 10 CFR 571.4(o).
500 gm U-235 equivalent mass; or l
(ii) Neutron sources in special form.
500 gm U-235 equivalent mass. Decay heat not to exceed 50 watts; or (iii)
Irradiated Pu0, and UO fuel rods clad in zircaloy or stainless 2
steel. Decay heat not to exceed 600 watts. All fuel rods shall be contained within a closed 5-inch Schedule 40 pipe with a t
maximum useat,le 1er.gth of 39-5/8 inches.
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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.
Decay heat not to exceed 600 watts.
Each graphite block shall be contained within a sealed cylindrical inner container constructed in accordance with General Atomic Company Drawing No. 021583, Issue 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 container with no
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more than one inner container per package.
Page 3 - Certificate No. 9044 - Revision No.10 - 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.
(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).
(vii) Radioactive (Hot Cell) waste materials immobilized with cement grout and contained in a 55-gallon (or extended 55-gallon drum)
DOT Specification 17H or 17C steel drum, lid and closure. The Waste material must be packaged in accordance with the Procedural Outline of the Immobilization 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), or 5.(b)(1)(vii):
Two (2); or (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 must be closed with a plug with a melting temperature of 200'F and the cask cavity must be dry before delivery of the package to a carrier.
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.
p Page 4 - Certificate No. 9044 - Revision No.10 - Docket No. 71-90.,
9.
Shoring must be provided to minimize movement of contents during accident 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, 50 times the measured neutron dose rate at 3 feet from the surface of a cask must be less than 1,000 mres/hr.
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- 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 seagoing vessel assigned for sole use of the licensee.
- 13. The packeqe authorized by this certificate is hereby approved for use under the general lionse provisions of 10 CFR 571.12(b).
14.
Expiration date:
April 30,1987.
REFERENCES General Electric application dated February 1,1982.
Supplement dated March 30, 1982.
Nuclear Plant Services supplement dated:
July 7, 1975.
FOR THE V.S. NUCLEAR REGULATORY COMMISSION
^-2 Charles E. MacDor.ald, Chief Transportation Certification Branch Division of Fuel Cycle and Materials Safety Date:
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y U.S. Nuclear Regulatory Comission Transportation Certification Branch Approval Record Model No. GE-1600 Docket No. 71-9044 By application dated February 1,1982, General Electric Company requested renewal of Certificate of Compliance No. 9044.
It was required that all supplemental information referenced by the Certificate of Compliance be incorporated into a consolidated application.
It was also requested that the packaging drawings be consolidated by showing only those features pertinent to safety such as overall dimensions, material thicknesses, shielding thickness, size and location of welds, fasteners, and materials
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af construction.
A review of the consolidated applicetion confirmed that all appropriate supplement information has been incorporated.
The packaging drawings were reviewed and a determination made that all information important to safety such as, material thickness, material specifications, etc., is shown on the drawings. The application introduced a revision to the method used to package neutron source material for shipment.
The neutron sources have previously been packaged as wet shipments and the applicant requested an amendment to substitute a polyethylene liner as neutron shielding in pl6ce of the water.
The polyethylene used to fabricate the neutron source shield is a 5% boron-polyethylene composite rated by the manufacturer for exposures up to 180'F.
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The staff has reviewed the data presented by the applicant and concludes that the polyethylene neutron source shield will retain its effectiveness under the normal conditions of transport. Thermal analysis of the package indicates that the cavity temperature does not exceed 400*F under the accident conditions. Therefore, the polyethylene shield can be expected to melt, but it is still substantially below the temperature of depolymurization (about 550*F) where volatile constituents would be released. As a precaution, a fuseable core plug with a melting temperature of 200'F is used to close the cavity drain line whenever a polyethylene liner is used for supplemental neutron shielding.
Shielding analysis indicates that the dose rate three feet from the external surface of the package will not exceed the regulatory limit of 1 R/hr assuming the polyethylene is no longer effective.
As a result of the change in neutron shield material (water to polyethylene) it is necessary to change condition 11 of the Certificate of Compliance.
Condition 11 establishes a dose rate limit that assures the package will meet the requirement of post accident conditions. Condition 11 is changed to read as follows:
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For packaging of neutron sources, 50 times the measured neutron dose rate at 3 feet from the surface of the cask must be less than 1,000 mrem /hr.
No other changes have been requested or made to the package since approval of latest supplement dated December 1,1981.
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Charles E. MacDonald, C ief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:
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