|
|
| (3 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 05/31/2012 | | | issue date = 05/31/2012 |
| | title = U.S. Geological Survey - Response to Request for Additional Information (RAI) Question 14 | | | title = U.S. Geological Survey - Response to Request for Additional Information (RAI) Question 14 |
| | 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 = 2 | | | page count = 2 |
| | | project = |
| | | stage = Response to RAI |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:S-USGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 May 31, 2012 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
| | |
| | ==Reference:== |
| | U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-113, Request for Additional Information (RAI) dated September 29, 2010 |
| | |
| | ==Subject:== |
| | Responses to Question 14 of the Referenced RAI Mr. Wertz: |
| | Here is the response to Question 14, parts 14.1 and 14.2: |
| | 14.1 In GSTR SAR Section 13.1, the GSTR SAR states that fuel temperature limits of 1,100 0C for stainless steel clad fuel and 535 °C for aluminum clad fuel were set to preclude the loss of clad integrity. GSTR SAR Technical Specification (TS) |
| | Section 14.2.1 lists safety limits for stainless steel clad fuel and aluminum fuel of 1,000 °C and 535 °C, respectively. The NRC has accepted (NUREG-1537 Appendix 14.1) that no fuel damage or cladding failure is expected ifthe fuel temperature for aluminum clad fuel is maintained at a temperature of less than 500 °C and the stainless steel clad fuel temperature is not to exceed 1,150 0C when the cladding temperature is less than 500 °C and is not to exceed 950 °C if the cladding temperature is greater than 500 *C. Please provide justification for the use of fuel temperature safety limits that are different from the stated limits in NUREG-1 537. |
| | The GSTR will accept the stated limits in NUREG-1 537 and change GSTR SAR Section 13.1 to read, "Fuel temperature limits of 1,150 'C (if cladding temperature is at or less than 500 °C) or 950 °C (if cladding temperature is greater than 500 °C) for stainless steel clad fuel and 500 'C for aluminum clad fuel have been set to preclude the loss of clad integrity." |
| | |
| | 14.2 Within Chapter 13, the assumed power level or trip setpoint for accident analysis is set at 1.0 MW (Maximum Hypothetical Accident, Loss of Coolant Accident) and 1.06 MW (uncontrolled rod withdrawal). However, the Limiting Safety System Setting (LSSS) and SCRAM setpoints are set at 1.1 MW. Please describe how these setpoints ensure that the safety basis is maintained. |
| | The reanalysis of the power level /trip setpoint change for the uncontrolled rod withdrawal accident will be answered at a later date after the neutronic analysis results are available; however, we will change our accident analysis assumptions to be at an assumed power of 1.1 MW in our new neutronic and thermal-hydraulic analyses. |
| | Sincerely, Tim DeBey USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on 5/31/12 Copy to: |
| | Betty Adrian, Reactor Administrator, MS 975 USGS Reactor Operations Committee}} |
Latest revision as of 02:36, 12 November 2019
|
|---|
Category:Letter
MONTHYEARML24092A1542024-04-0404 April 2024
U.S. Geological Survey - Change of Facility Project Manager
ML24092A0422024-03-28028 March 2024
U.S. Geological Survey Triga Reactor Annual Report Submittal in Accordance with Technical Specification 6.7.1 Rev. 00 for 2023
IR 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
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
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
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
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
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
2024-04-04
[Table view] |
Text
S-USGS science for a changing world Department of the Interior US Geological Survey PO Box 25046 MS 974 Denver, CO 80225-0046 May 31, 2012 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
U.S. Geological Survey TRIGA Reactor (GSTR), Docket 50-274, License R-113, Request for Additional Information (RAI) dated September 29, 2010
Subject:
Responses to Question 14 of the Referenced RAI Mr. Wertz:
Here is the response to Question 14, parts 14.1 and 14.2:
14.1 In GSTR SAR Section 13.1, the GSTR SAR states that fuel temperature limits of 1,100 0C for stainless steel clad fuel and 535 °C for aluminum clad fuel were set to preclude the loss of clad integrity. GSTR SAR Technical Specification (TS)
Section 14.2.1 lists safety limits for stainless steel clad fuel and aluminum fuel of 1,000 °C and 535 °C, respectively. The NRC has accepted (NUREG-1537 Appendix 14.1) that no fuel damage or cladding failure is expected ifthe fuel temperature for aluminum clad fuel is maintained at a temperature of less than 500 °C and the stainless steel clad fuel temperature is not to exceed 1,150 0C when the cladding temperature is less than 500 °C and is not to exceed 950 °C if the cladding temperature is greater than 500 *C. Please provide justification for the use of fuel temperature safety limits that are different from the stated limits in NUREG-1 537.
The GSTR will accept the stated limits in NUREG-1 537 and change GSTR SAR Section 13.1 to read, "Fuel temperature limits of 1,150 'C (if cladding temperature is at or less than 500 °C) or 950 °C (if cladding temperature is greater than 500 °C) for stainless steel clad fuel and 500 'C for aluminum clad fuel have been set to preclude the loss of clad integrity."
14.2 Within Chapter 13, the assumed power level or trip setpoint for accident analysis is set at 1.0 MW (Maximum Hypothetical Accident, Loss of Coolant Accident) and 1.06 MW (uncontrolled rod withdrawal). However, the Limiting Safety System Setting (LSSS) and SCRAM setpoints are set at 1.1 MW. Please describe how these setpoints ensure that the safety basis is maintained.
The reanalysis of the power level /trip setpoint change for the uncontrolled rod withdrawal accident will be answered at a later date after the neutronic analysis results are available; however, we will change our accident analysis assumptions to be at an assumed power of 1.1 MW in our new neutronic and thermal-hydraulic analyses.
Sincerely, Tim DeBey USGS Reactor Supervisor I declare under penalty of perjury that the foregoing is true and correct.
Executed on 5/31/12 Copy to:
Betty Adrian, Reactor Administrator, MS 975 USGS Reactor Operations Committee