ML19254D490
| ML19254D490 | |
| Person / Time | |
|---|---|
| Site: | 07106346 |
| Issue date: | 10/23/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19254D486 | List: |
| References | |
| NUDOCS 7910260040 | |
| Download: ML19254D490 (3) | |
Text
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-a Form NRC 618 U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.la) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 6346 3
USA /6346/B( )F 1
3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sc. ms 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170A and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Re;ulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents detvibad in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, **Fac taging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.*
2.lc)
This certificate does not relieve the consignor from compliance witt 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 package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.la)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
General Atomic Company Gulf General Atomic, Inc. app'.ication dated P. O. Box 81608 May 20, 1969, as supplemented.
San Diego, CA 92136 3.(c)
Docket No. 71-6346 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. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model No.:
FSV-1 (2) Description The cask is cylindrical, 208" long and 28" diameter for most of its length 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 contigurations. One closure system utilizes an outer cover consisting 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.;4" of depleted uranium. The alternate closure 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 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.
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Page 2 - Certificate No. 6346 - Revision No. 3 - Docket No. 71-6346 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with National Lead Company Drawings Nos.: 400650, Rev.1; 70085F, Rev. 5; 70086F, Rev. 7; 70094F, Rev. 5; 401550, Rev.1; 70105F, Rev. 5; 70104F, Rev. 5; and 70296F, Rev. 2.
The packaging.dith its alternate closure system utilizes the above drawings except that closures with impact limiter are constructed as shown on General Atomic Company Drawings 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.
(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 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, General Atomic Company Safety Analysis Report GADR-55.
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Page 3 - Certificate No. 6346 - Revision No. 3 - Docket No. 71-6346 7.
The 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: October 31, 1980.
REFERENCES Gulf General Atomic, Inc. ppplication dated May 20, 1969.
Supplements dated:
December 2, 1969; June 17 and July 27, 1970; August 3,1971; June 15,1977; August 15, 1978; and February 27, April 6, September 6, and October 12, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
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