Letter Sequence RAI |
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MONTHYEARML0434101362004-12-0707 December 2004
United States Geological Survey - RAI, Use of Aluminum Clad Fuel
Project stage: RAI
ML0505303002005-02-0808 February 2005
Letter from the U.S. Geological Survey in Response to Request for Additional Information Dated 12/7/2004
Project stage: Response to RAI
ML0506602022005-03-10010 March 2005
United States Geological Survey -- Request for Additional Information Use of Aluminum Clad Fuel
Project stage: RAI
ML0510502592005-04-11011 April 2005
the U.S. Geological Survey Is Herein Responding to Request for Additional Information Dated March 10, 2005. Concerns USGS Amendment Request to Research Reactor Facility License (No. R-113, Docket 50-274) to Allow Use of Aluminum Clad Triga
Project stage: Request
ML0525103832005-08-25025 August 2005
U. S. Geological Survey Providing Clarification and Additional Supporting Information in Response to Request for Additional Information
Project stage: Response to RAI
ML0529402272006-01-30030 January 2006
United States Geological Survey -License Amendment 11 Use of Aluminum Clad Fuel
Project stage: Approval
2005-03-10
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Category:Letter
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United States Geological Survey - U.S. Nuclear Regulatory Commission Routine Inspection Report No. 05000274/2023201
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Examination Confirmation Letter No. 50-274/OL-22-01, United States Department of Interior Geological Survey
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U.S. Geological Survey Triga Reactor, Docket Number 50-274, License Number R-113, Reactor Administrator Succession
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United States Geological Survey, U.S. Nuclear Regulatory Commission Routine Inspection Report05000274/2020201 - Cover Letter and Enclosure
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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
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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
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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
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U.S. Geological Survey - Regulatory Audit Report Proposed License Amended No. 14 to Increase the Special Nuclear Material Possession Limit
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ML20279A5912020-10-0606 October 2020
U.S. Geological Survey - Regulatory Audit Proposed License Amendment No. 14 Tt Increase the Special Nuclear Material Possession Limit
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U.S. Geological Survey - Acceptance of the Application for Proposed License Amendment No. 14 Increase in the Special Nuclear Nuclear Material Possession Limit
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ML20199M1672020-07-20020 July 2020
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ML20183A1622020-07-0202 July 2020
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7 of the Emergency Plan for the U.S. Geological Survey Triga Reactor (Gstr) Facility (License R-113, Docket 50-274)
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United States Geological Survey NRC Routine Inspection Report No. 50-274/2017-201
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2024-04-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML16147A6422016-06-28028 June 2016
U.S. Geological Survey - Request for Additional Information Regarding the Review of the License Renewal of the U.S. Geological Survey Triga Research Reactor (TAC No. ME1593)
ML16112A0032016-04-25025 April 2016
U.S. Geological Survey - Request for Additional Information for the Review of the Physical Security Plan Regarding the License Renewal of the U.S. Geological Survey Triga Research Reactor
ML16027A1342016-02-0808 February 2016
Us Geological Survey - Request for Additional Information Regarding the Review of the License Renewal of the Us Geological Survey Triga Research Reactor Draft 1.27.16
ML15259A7312015-09-21021 September 2015
Request for Additional Information License Amendment Request to Modify the Source, Byproduct and Special Nuclear Material Possession Limits for Facility Operating License No. R-113 for the U.S. Geological Survey Triga Reactor
ML15226A2772015-08-18018 August 2015
Us Geological Survey - Request for Additional Information License Amendment Request to Modify the Source, Byproduct and Special Nuclear Material Possession Limits for Facility Operating License No. R-113 for the U.S. Geological Survey Triga
ML14211A5862014-08-25025 August 2014
U.S. Geological Survey - Request for Additional Information and Clarification to Previous Responses to the U.S. Nuclear Regulatory Commission Request for Additional Information
ML14141A6322014-06-12012 June 2014
U.S. Geological Survey - Request for Additional Information Amendment Request to Modify the Source, Byproduct and Special Nuclear Material Possession Limits for Facility Operating License No. R-113 for the U.S. Geological Survey Triga Resea
ML14023A7952014-01-28028 January 2014
U.S. Geological Survey - Request for Additional Information Review of the Emergency Plan for the License Renewal for the Geological Survey Triga Reactor
ML14014A1232014-01-22022 January 2014
U.S. Geological Survey - Request for Additional Information Review of the Operator Requalification Program for the License Renewal for the Geological Triga Reactor
ML13190A0522013-07-15015 July 2013
United States Geological Survey - Additional Clarification Requested Responses to the U.S. Nuclear Regulatory Commission Request for Additional Information Dated September 29, 2010
ML13162A6622013-05-17017 May 2013
Redacted USGS RAI Clarification Information Needed to Support the USGS License Renewal SAR
ML12075A0012012-03-21021 March 2012
United States Geological Survey - NRC Request for Additional Information Ar-41 Dose Calculations Relating to the License Renewal (Tac No. ME1593)
ML0527203682005-10-0707 October 2005
RAI Letter - Security Measures - Debey
ML0506602022005-03-10010 March 2005
United States Geological Survey -- Request for Additional Information Use of Aluminum Clad Fuel
ML0504200272005-02-16016 February 2005
U.S. Geological Survey - Request for Additional Information Amendment Request for Construction Permit Recapture
ML0434101362004-12-0707 December 2004
United States Geological Survey - RAI, Use of Aluminum Clad Fuel
2016-06-28
[Table view] |
Text
March 10, 2005 Mr. Warren Day, Reactor Administrator United States Department of the Interior Geological Survey Box 25046, MS 974 Denver Federal Center Denver, CO 80225-0046
SUBJECT:
UNITED STATES GEOLOGICAL SURVEY REQUEST FOR ADDITIONAL INFORMATION RE: USE OF ALUMINUM CLAD FUEL (TAC NO. MC5120)
Dear Mr. Day:
We are continuing our review of changes to the technical specifications (TSs) for the United States Geological Survey TRIGA Research Reactor which you submitted on November 16, 2004, as supplemented on December 3, 2004, and February 8, 2005. During our review of your TSs changes, questions have arisen for which we require additional information and clarification. Please provide responses to the enclosed request for additional information within 60 days of the date of this letter. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your TSs changes.
If you have any questions regarding this review, please contact me at (301) 415-1127.
Sincerely,
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-274
Enclosure:
As stated cc w/enclosure: See next page
U.S. Geological Survey Docket No. 50-274 cc:
Mayor City Hall Denver, CO 80202 Mr. Eugene W. Potter State of Colorado Radiation Management Program HMWM-RM-B2 4300 Cherry Creek Drive South Denver, CO 80246 Mr. Timothy DeBey Reactor Director U.S. Geological Survey Box 25046 - Mail Stop 424 Denver Federal Center Denver, CO 80225 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
March 10, 2005 Mr. Warren Day, Reactor Administrator United States Department of the Interior Geological Survey Box 25046, MS 974 Denver Federal Center Denver, CO 80225-0046
SUBJECT:
UNITED STATES GEOLOGICAL SURVEY REQUEST FOR ADDITIONAL INFORMATION RE: USE OF ALUMINUM CLAD FUEL (TAC NO. MC5120)
Dear Mr. Day:
We are continuing our review of changes to the technical specifications (TSs) for the United States Geological Survey TRIGA Research Reactor which you submitted on November 16, 2004, as supplemented on December 3, 2004, and February 8, 2005. During our review of your TSs changes, questions have arisen for which we require additional information and clarification. Please provide responses to the enclosed request for additional information within 60 days of the date of this letter. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your TSs changes.
If you have any questions regarding this review, please contact me at (301) 415-1127.
Sincerely,
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-274
Enclosure:
As stated cc w/enclosure: See next page DISTRIBUTION:
PUBLIC RNRP/R&TR r/f TDragoun MMendonca AAdams WBeckner OGC EHylton FGillespie CBassett DMatthews WEresian SHolmes Isaac GHill (2) PDoyle DHughes PMadden KWitt PYoung ADAMS ACCESSION NO.: ML050660202 TEMPLATE No.: NRR-088 OFFICE RNRP:PM RNRP:LA RNRP:SC NAME AAdams EHylton PMadden DATE 3/ 8 /05 3/ 7/05 3/ 8 /05 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION UNITED STATES GEOLOGICAL SURVEY DOCKET NO. 50-264
- 1. Your answer to question 3 of our request for additional information (RAI) dated December 7, 2004, discussed fuel temperatures in the F and G rings when limiting the measured temperature of a stainless steel clad fuel element to 800EC in the B ring.
Technical Specification (TS) D.3. also allows the instrumented fuel element to be placed in the C ring, where fuel temperatures could be lower than in the B ring. Limiting the measured fuel temperature to 800EC in the C ring could result in higher temperatures in the F and G rings than would result from limiting measured temperature to 800EC in the B ring. Please provide maximum fuel temperatures in the F and G rings if the measured temperature of 800EC is taken from an instrumented fuel element in the C ring. (Note that your answer to question 9 below may change the 800EC temperature in this question.)
- 2. The instrumented fuel element contains multiple thermocouples at different locations in the fuel element. Because of this, the temperature reading from the element may not be the true maximum temperature of the fuel in the element. Discuss the accuracy of your measured temperatures as compared to true temperature and the impact this has on the various temperatures given in your RAI request responses.
- 3. What was the wt% of the fuel in the instrumented fuel element used to measure the fuel temperatures given in your responses to our RAI? If the fuel wt% of the instrumented fuel element is different than the fuel wt% of the aluminum clad fuel, explain what effect the difference in fuel wt% has on the conclusions presented in your RAI response.
- 4. Your answer to question 3 of our RAI contains fuel temperature data based on a coolant temperature of 50 EC. However, your TSs allow a bulk pool temperature up to 60 EC.
Please present the data on fuel temperature assuming a coolant temperature of 60 EC.
- 5. Your original application contained a table with a set of temperature measurements. For the 1 MW steady state measurement taken in March of 2002, where was the instrumented fuel element located in the core?
- 6. Discuss maximum fuel temperatures in the aluminum clad fuel at the reactor high power set point of 1.1 MW.
- 7. Your answer to our RAI question 10 was based on a coolant temperature of 50 EC.
However, your TSs allow a bulk pool temperature up to 60 EC. Please present the data on fuel temperature assuming a coolant temperature of 60 EC.
- 8. You have proposed changes to TS D.7. It appears that your proposed wording would remove the flexibility to have a core with less than 100 fuel elements operate with a power level greater than 100 kW. Please provide a justification for your proposed change to the TS.
- 9. TS D.3. contains a fuel temperature limit of 800EC for fuel temperature. However, General Atomics in report E-117-833, The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel, discusses a steady-state operational fuel temperature design limit of 750EC based on consideration of irradiation- and fission-product-induced fuel growth and deformation. Please discuss.