|
|
(2 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 09/26/2011 | | | issue date = 09/26/2011 |
| | title = Response to Request for Additional Information to Question 20 of Dated September 29, 2010 | | | title = Response to Request for Additional Information to Question 20 of Dated September 29, 2010 |
| | author name = DeBey T | | | author name = Debey T |
| | author affiliation = US Dept of Interior, Geological Survey (USGS) | | | author affiliation = US Dept of Interior, Geological Survey (USGS) |
| | addressee name = | | | addressee name = |
Line 12: |
Line 12: |
| | document type = Letter | | | document type = Letter |
| | page count = 1 | | | page count = 1 |
| | | project = |
| | | stage = Response to RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: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 | | {{#Wiki_filter: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:== | | ==Reference:== |
| | | U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010 |
| U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-1 13 Request for Additional Information (RAI) dated September 29, 2010 | |
|
| |
|
| ==Subject:== | | ==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: | | Response to Question 20 of the Referenced RAI Mr. Wertz: |
| 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}} | | 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 UZrH1 .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}} |
|
---|
Category:Letter
MONTHYEARIR 05000274/20232022023-11-13013 November 2023 U.S. Geological - U.S. Nuclear Regulatory Commission Safety Inpsection Report No. 05000274/2023202 IR 05000274/20232032023-11-0909 November 2023 United States Geological Survey - U.S. Nuclear Regulatory Commission Security Inspection Report No. 05000274/2023203 (Public) IR 05000274/20232012023-02-27027 February 2023 United States Geological Survey - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000274/2023201 ML22026A4852022-03-0707 March 2022 Examination Confirmation Letter No. 50-274/OL-22-01, United States Department of Interior Geological Survey ML22053A1872022-02-22022 February 2022 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, Reactor Administrator Succession IR 05000274/20212022021-10-0101 October 2021 U.S. Geological U.S. Nuclear Regulatory Commission Safety Inspection Report No. 05000274/2021202 IR 05000274/20212032021-09-30030 September 2021 United States Geological Survey - Nuclear Regulatory Commission Security Inspection Report No. 05000274/2021203 IR 05000274/20202012021-04-21021 April 2021 United States Geological Survey, U.S. Nuclear Regulatory Commission Routine Inspection Report05000274/2020201 - Cover Letter and Enclosure ML21090A1912021-03-29029 March 2021 U.S. Geological Survey Triga Reactor, Annual Report Submittal in Accordance with Technical Specification 6.7.1 Rev. 00 ML21082A2822021-03-23023 March 2021 Letter to R. Horton, USGS Denver Federal Center, from B. Smith, NRC, NRC Office of Investigations Report No. 4-2019-014 - Release of OI Synopsis IR 05000274/20212012021-03-12012 March 2021 U.S. Geological Survey NRC Non-Routine Inspection Report 05000274/2021201 ML20314A2922020-12-0303 December 2020 USGS Issuance of Amendment No. 14 to Renewed Facility Operating License No. R-113 for the USGS Triga Research Reactor Increasing the Special Nuclear Material Possession Limit ML20336A0202020-12-0101 December 2020 U.S. Geological Survey Triga Reactor - License Amendment Request LAR 14, Supplemental Information Letter 04 Provided in Response to Phone Call with NRC Project Manager at 0854 Mst on 2020-11-30 ML20295A4242020-11-16016 November 2020 Notification of Mailing Address Change Regarding Submittal of Fingerprint Cards ML20310A3352020-11-0505 November 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, Updated Physical Security Plan, Rev. Xxi ML20310A2962020-11-0505 November 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request LAR 14, Supplemental Information Letter 03 Provided in Resolution of Comments Presented by the State of Colorado During the Public M ML20296A4902020-10-22022 October 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request LAR 14, Supplemental Information Letter 02 Provided in Response to Audit Visit on 2020-10-15 ML20318A0882020-10-22022 October 2020 U.S. Geological Survey Trig a Reactor, License Amendment Request LAR 14, Supplemental Information Letter 01 Provided in Response to Audit Visit on 2020-10-15 Purpose ML20295A5102020-10-21021 October 2020 U.S. Geological Survey - Regulatory Audit Report Proposed License Amended No. 14 to Increase the Special Nuclear Material Possession Limit ML20233A9962020-10-0909 October 2020 Us Geological Survey - Issuance of Amendment No. 13 to Renewed Facility Operating License No. R-113 to Amend Technical Specifications 3.1.3 and 4.1 for the Us Geological Survey Triga Research Reactor ML20279A5912020-10-0606 October 2020 U.S. Geological Survey - Regulatory Audit Proposed License Amendment No. 14 Tt Increase the Special Nuclear Material Possession Limit ML20279A3052020-10-0505 October 2020 U.S. Geological Survey - Acceptance of the Application for Proposed License Amendment No. 14 Increase in the Special Nuclear Nuclear Material Possession Limit ML20275A2672020-10-0101 October 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request 2020-02, LAR 14, Rev. 00 ML20199M1672020-07-20020 July 2020 NRC Letter and SER Authorizing USGS to Use an Alternate A2 Value ML20183A1622020-07-0202 July 2020 U.S. Geological Survey - Acceptance of the Application for a License Amendment Exception to TS 3.1.3 and 4.1 to Allow Fewer than 110 Fuel Elements When Either Shutdown or Operating at a Power Level Not Greater than 5 Kilowatts ML20177A6102020-06-25025 June 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request 2020-01, Supplemental Information Provided in Response to ML20176A465 ML20161A1272020-06-0404 June 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request 2020-01, Revision 01 ML20134J1082020-05-13013 May 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, License Amendment Request 2020-01 ML20157A0752020-05-0707 May 2020 U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, Reactor Supervisor Appointment ML20136A3362020-04-21021 April 2020 Us Dept. of Interior, Geological Survey (Usgs), Submittal of Corrected 2019 Annual Report ML20134J1162020-04-10010 April 2020 7 of the Emergency Plan for the U.S. Geological Survey Triga Reactor (Gstr) Facility (License R-113, Docket 50-274) ML20087H0192020-03-0202 March 2020 Us Dept of Interior, Geological Survey (USGS) - Submittal of 2019 Annual Report ML19206A0622019-07-11011 July 2019 Us Dept of the Interior, Us Geological Survey Follow-Up on August 9, 2018 Letter Request for Approval for Use of Alternative A2 Value for Isotope Br-80m Under Appendix a to 10 CFR 71 ML19066A0542019-02-25025 February 2019 U.S. Dept of the Interior, Geological Survey, Reply to a Notice of Violation: EA-18-031 and EA-18-111 ML19044A3732019-01-31031 January 2019 Us Dept. of Interior, Geological Survey - Submittal of 2018 Annual Report ML18354B1702018-12-31031 December 2018 U.S Geological Survey-Notice of Violation and Proposed Imposition of Civil Penalty ML18324A5752018-11-16016 November 2018 United States Geological Survey (Usgs), Transfer of Reactor Supervisor Responsibilities. Position of Reactor Supervisor for Triga Facility Has Been Transferred from Mr. Brycen Roy to Mr. Christopher Farwell, Effective October 26, on Interim ML18324A5742018-11-16016 November 2018 United States Department of the Interior - Transfer of Reactor Administrative Responsibilities ML18325A1462018-11-0707 November 2018 U.S. Dept. of Interior, Geological Survey - Response to Apparent Violations Associated with NRC Investigation Reports 4-2017-027 and 4-2018-005; IA-18-038 IR 05000274/20182022018-08-15015 August 2018 United States Geological Survey - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 50-274/2018-202 ML18236A5512018-08-0909 August 2018 Request for Approval for Use of Alternative A2 Value for Isotope Br-80m Under Appendix a to 10 CFR 71 IR 05000274/20182032018-07-17017 July 2018 United States Geological Survey - U.S. Nuclear Regulatory Commission Security Inspection Report 05000274/2018203 ML18016A0512018-01-11011 January 2018 2017 Annual Report for the U.S. Geological Survey Triga Non-Power Reactor Facility ML17355A1472017-12-18018 December 2017 Establishing a Quality Assurance Program at the U.S. Geological Survey Triga Reactor Facility (License R-113, Docket 50-274) IR 05000274/20172012017-05-17017 May 2017 United States Geological Survey NRC Routine Inspection Report No. 50-274/2017-201 ML17074A6472017-04-19019 April 2017 United States Geological Survey TRIGA Reactor Closure of Confirmatory Action Letter No. NRR-03-005 on Site-Specific Compensatory Measures Implementation Plan ML17067A3942017-03-22022 March 2017 U.S. Geological Survey - Non-Power Reactor Closeout of Generic Letter 2016-01, "Monitoring of Neutron Absorbing Materials in Spent Fuel Pools," for the U.S. Geological Survey Training Reactor And Isotopes Production, General Atomics Research Reactor ML17046A3632017-02-17017 February 2017 Examination Report No. 50-274/OL-17-01, United States Geological Survey ML17030A0362017-01-0909 January 2017 Us Dept. of the Interior, Geological Survey - Submittal of 2016 Annual Report ML16326A1462016-12-0101 December 2016 Us Geological Survey - Amendment No. 11 to Indemnity Agreement Amendment No. D-10 2023-02-27
[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 UZrH1 .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