ML19318B291
| ML19318B291 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 03/24/1980 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19318B292 | List: |
| References | |
| 15877, NUDOCS 8006250208 | |
| Download: ML19318B291 (2) | |
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m PDR 9 0 - 72'I Babcock &Wilcox aeseeren ena oeveicoment oivisica P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 March 24,'1980 Mr. W. T. Crow, Section Leader Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety U. S. Nuclear Regulatory Commission Washington, D. C. 20555 License: SNM-778, docket 70-824
Dear Mr. Crow:
'1he renewal application for our license has been under consideration for some time during which several revisions have been made.
I am attaching yet another revision.
This addresses a lica.nse condition that exists in the current license and was carried over to the renewal.
It specifies that irradiated fuel assemblies received at the Lynchburg Research Center for examination must be received in the shipping container specified in certificate of compliance 6698.
The basis for this condition was provided in " Report of Operational and Structural Aspects of the Nuclear Fuel Transport Cask Handling System, Building B", Wiley and Wilson, Inc., July 29, 1975. The report demonstrated that under the postulated accident condition, whereby the loaded cask is dropped from a height of 23.33 feet above the hot cell storage pool floor, the pool would maintain its water-tight integrity. This report was forwarded to you under my cover dated August 1, 1975. The cask data used in the above referenced demonstration was obtained from the " Safety Analysis Report for NFS Cask (/4", Nuclear Fuel Services, Inc., 1972.
Recent revisions to the. safety analysis report has caused the Lynchburg Research Center to review. its calculations in this regard. The review indicated that water-I tight integrity of the pool would be lost under the accident conditions, utilizing the most recent SAR data.
It is therefor necessary to add impact absorbing material to the pool floor to insure that the limiting criterion for the most probable failure unde, i.e. 402 psi punching shear, is not exceeded.
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- The attached revised license condition is an improvement over the previous one in two important respects; 1) it established the safety criterion for each type of fuel assembly shipping container on the most limiting criterion for the most probable pool failure mode, rather than on a cask identified in a particular certificate of compliance and 2) it specifies that the safety demonstration must be performed by an engineer capable of performing, or verifying the correctness of, the calculations demonstrating the safety.
In, addition, the revised condition will permit the use of other shipping con-tainers.
I feel that this action is an improvement in safety. If you have questions in this regard please call me.
Yours very truly, BABCOCK & WILCOX COMPANY LYNCHBURG RESEARCH CENTER Arne F. Olsen License Administrator AFO:ccf Attachment (s) l i
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