ML19347B749
| ML19347B749 | |
| Person / Time | |
|---|---|
| Site: | 07106346 |
| Issue date: | 09/25/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19347B747 | List: |
| References | |
| NUDOCS 8010150610 | |
| Download: ML19347B749 (3) | |
Text
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Form NRC-618 U.S. NUCLEAR REGULATORY CoMMISSloN i
,g CFR ?)
CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.fal Certificate Number 1.(b) Revsion No.
1.(c) Package fdentification No.
1.(d) Pages No. 1.(e) Total No. Pages 6346 4
USA /6346/B( )F 1
3
- 2. PRE AM8LE 2.tal This certificate is issked to satisfy Sections 173.093a.173.394.173.395. and 173.336 of the Department of Transportation Hazardous Materials Regulations 149 CFR 170189 and 14 CFR 103) and Sections 146-19-loa and 146-19-100 of tne oepartment of Transoortation aangerous Cargoes Regulations (46 CFR 146-149), as arnended.
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2.10)
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, " Packaging of Radioactive Materials for Transport and Transportanon of Radioactive Material Under Certsin Conditeens."
2.fc)
This certificate does not relieve the consignor from comoliance with any recuirement of the regulations of the U.S. oepartment of Transoortation or otner applicable regulatory agencies, including the government of any country through or into which the pacmage will be transported.
- 5. This certificate is issued on the basis of a safety analysis reoort of tne pacnage design or aposication-j 3.(a)
Prepared *:y (Name and addressi:
3.(b)
Title and identification of report or aoosication:
General Atomic Company General Atomic Company application dated P. O. Box 81608 August 28, 1980.
l San Diego, CA 92136 3.(c) oocket No. 71-6346 4 CoNDITroNS This certificate is conditional ur.un the fulfilling of the requirements of Subpart o of 10 CFR 71. as apolicaute. and the conditions coscified in item 5 colow.
- 5. Oescription of Packsiing and Autnorized Contents. Mooet Numoer, Fissde Class. Other Conditions, and References; (a) Packagir.g (1) Model No.:
FSV-1 (2) Description The cask is cylindrical, 208" long and 28" diameter for most of its lengt.:
except for the top flange which is 11-3/8" thick and 31" in diameter.
The cask utilizes stainless steel encased depleted uranium as primary shielding.
The cask's inner container, for fueled contents, has a cavity of 16-5/8" diameter and 187-5/8" long.
The fuel contents are hexagonal cross section elements and are loaded into the cask's inner container, six in one column.
The cask may utilize either of two closure configurations.
One closure system utilizes an outer cover cor.sisting of 3-3/4" stainless steel together depleted uranium, 2-1/4" thick, and an inner lid of 2-1/4" thick stainless steel.
The primary seal is provided by two 0-rings, one metallic and the other silicone.
The alternate closure system utilizes 4.75" thick alloy steel and 4.14" of depleted uranium.
The alternate closure i
system requires the use of an impact limiter at the top during transport.
The alternate closure is sealed by a molded dual concentric silicone elastomer l
seal ring with a test port between the seals.
A gas sample port penetrates through the lid into the container.
The gas test port is sealed with a check valve and primary plug with a silicone 0-ring.
se1015clolC)
s Page 2 - Certificate No. 6346 - Revision No. 4 - Docket No. 71-6346 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with National Lead Company Drawing Nos.:
400650, Rev. 1; 70085F, Rev. 5; 70086F, Rev. 7; 70094F, Rev. 5; and 70296F, Rev. 2.
The packaging with its alternate closure system utilizes the above drawings except that closures with impact limiter are constructed as shown on General Atomic Company Drcwing Nos. GADR 55-2-1, Issue A; GADR 55-2-2, Issue A; and GADR 55 2-3, Issue A.
(b) Contents (1) Type and form of material (i) Irradiated fuel elements consisting of graphite body, hexagonal in horizontal cross section, approximately 31.2 inches high and 14.2 inches across the flats.
Each fuel element prior to irradiation contains thorium and uranium enriched to a maximum of 93.5 w/o in the U-235 isotope; or (ii) Solid nonfissile irradiated hardware and neutron: source components.
(2) Maximum quantity of material per package Not to exceed a decay heat generation of 4.1 kw and:
(i) Item 5(b)(1)(i) above:
Six fuel elements each containing 1.4 kg of enriched uranium and 11.3 kg of thorium prior to irradiation and weighing 300 lbs; (ii) Item 5(b)(1)(ii) above:
As needed, appropriate component spacers shall be used in the cask cavity to limit movement of contents during shipment.
(c) Fissile Class III Maximum number of packages per shipment Contents 5.(b)(1)(1):
One (1) 6.
The alternate closure system shall be leak tested prior to (1) first use and periodically in accordance with Section I.G.2 and (2) each use in accordance with Section I.G.1, to Addendum I, Revision 1, General Atomic Company Safety Analysis
~ Report GADR-55.
Page 3 - Certificate No. 6346 - Revision No. 4 - Docket No. 71-6346 7.
ae spent fuel container main flange seal (s) and the alternate closure system fuel container primary plug silicone 0-ring shall be replaced at least every 12 months.
8.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
9.
Expiration date:
September 30, 1985.
REFERENCE General Atomic Company application dated August 28, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION"
+
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety SEP 2 51980 Date:
._.