ML19254E920
| ML19254E920 | |
| Person / Time | |
|---|---|
| Site: | 07109001 |
| Issue date: | 10/31/1979 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| References | |
| 14406, NEDO-10084-2, NUDOCS 7911050064 | |
| Download: ML19254E920 (2) | |
Text
NED0-10084-2 October 1979 l.
INTRODUCTION This Consolidated Safety Analysis Report (CSAR) for the General Electric IF-300 shipping cask compiles into one document the information contained in General Electric Company's application dated February 22, March 6 and March 12, 1973 (NED0-10082-1) plus the supplements dated: August 13 and 27, September 4, and December 14 and 26,1973; January 18 and 28, March 14 and 20, June 7, July 5 and 12, September 3, and December 12, 1974; May 9, September 3, 9, and 23 and November 19, 1975; September 1 and November 16 (DMD-92) and 16 (DMD-93),
1976; February 1 and May 19, 1977; and January 20 and August 10, 1978.
In some instances certain supplements were withdrawn af ter submittal and in other instances supplements were superceded.
This CSAR presents the technical basis fcr the latest revision, Revision 8, to Certificate of Compliance Number 9001 for the IF-300 shipping cask. This cask is suitable for the shipment of all types of light-water-moderated reac' tor fuels.
As such, permissible cask contents are based on limiting fuel parameters rather than individual fuel types. For purposes of identification, these design basis fuels are divided into two generic classes, BWR and PWR. The design basis fuel parameters in each class meet or exceed existing fuel parameters.
The IF-300 cask is designed to meet or exceed all Nuglear Regulatory Commission (NRC) and Department of Transportation (DOT) regulations governing the shipment of fissile radioactive material. Primary transportation mode will be the rail-road, although the shipping package is designed to facilitate truck shipment on a special overweight basis for short distances. This feature allows the servicing of those reactor sites which lack direct railroad access.
The IF-300 cask body is a depleted uranium shielding and stainless steel clad, an-nular cylinder, closed at one end.
Fuel is loaded through the top end and closure is accomplished using a bolted and sealed head. The head shielding is similar to the cask body.
7 911050 b l-1 14406 1268.287
NED0-10084-2 October 1979 Fuel is held within the cask cavity by a removable stainless steel basket.
There are several basket configurations which may be used, depending on the specific fuel being shipped. There are also two heads which permit a variation in cask cavity length.
For high heat load operation, the cask cavity is water-filled. Heat transmission from the fuel to the cavity walls is accomplished by natural circulation of the water. The cavity is protected from overpressure by a high temperature pressure relief valve. Under low heat loads the cask cavity may be air-filled.
The cask outer surface has large circumferential fins designed for impact protection. Masking the fuel active zone is a water-filled corrugated contain-ment which acts as a neutron shield. The upper and lower ends of the cask are also equipped with sacrificial fins for impact protection. Tne cask is cooled by an, air impingement technique. This cooling mode maintains the cask at tem-peratures which permit easier handling. The cooling system is not required to preserve cask integrity or retain coolant. Four longitudinal ducts direct air froa two diesel-driven blowers onto the corrugated surface. The cask, cask supports, and cooling system are all mounted on a steel skid.
Exclusion from the cask and cooling system is provided by a wire mesh c'-losure which is retractable for cask removal and locks in place during transport. The skid mounted equipment forms a completely self-contained irradiated fuel shipping pac kage.
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