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Revision as of 09:28, 30 April 2019
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Category:Letter
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U.S. Geological Survey - Change of Facility Project Manager
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U.S. Geological Survey NRC Non-Routine Inspection Report 05000274/2021201
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2024-04-04
[Table view] |
Text
SUSGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 September 26, 2011 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010
Subject:
Response to Question 20 of the Referenced RAI Mr. Wertz: Question 20: NUREG-1537, Part 1, Appendix 14.1, Section 2.1, "Safety Limits," states that the NRC finds 530 'C an acceptable fuel and cladding temperature limit not to be exceeded under any conditions of operation." GSTR TS 14.2.1 states that "The temperature in an aluminum-clad TRIGA fuel element shall not exceed 995 'F (535 'C) under any mode of operation." Please provide a justification for using 995 'F (535 'C) as a safety limit.Response:
The referenced statement that "the NRC finds 530 'C an acceptable fuel and cladding temperature limit not to be exceeded under any conditions of operation," actually refers to aluminum-clad, aluminum matrix plate-type fuels and is therefore not valid for the GSTR TRIGA reactor.Further down in NUREG-1537, Part 1, Appendix 14.1, Section 2.1, "Safety Limits," it states that "For aluminum-clad UZrH 1.0 LEU 8 w/o TRIGA fuel, NRC has accepted that the peak fuel temperature should not exceed 500 'C." The GSTR will accept the guidance and change GSTR TS 14.2.1 to read, "The-temperature in an aluminum-clad TRIGA fuel element shall not exceed 932 'F (500 'C) under any mode of operation." Sincerely, Tim DeBey USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct.Executed on 9/26/11 Copy to: Betty Adrian, Reactor Administrator, MS 975 USGS Reactor Operations Committee O 0 (e