Letter Sequence Request |
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MONTHYEARML21274A0222021-09-20020 September 2021
Root Cause Response, Revision 1
Project stage: Request
ML21274A0242021-09-21021 September 2021
Memorandum on Recovery Items
Project stage: Request
ML21274A0232021-09-21021 September 2021
Latch Improvement Safety Analysis
Project stage: Request
ML21274A0252021-09-30030 September 2021
Corrective Action Plan Corrective Actions Required Prior to Reactor Startup
Project stage: Request
ML21340A0102021-12-0303 December 2021
Ncnr Response to November 17, 2021 Request for Supplemental Information
Project stage: Request
ML21340A0072021-12-0303 December 2021
Analysis of Cooling Flow Through 29 Fuel Elements with Fuel Element 1175 Dislodged
Project stage: Request
ML21361A2462021-12-23023 December 2021
Nbsr License Amendment Request
Project stage: Request
ML21361A2472021-12-23023 December 2021
Nbsr License Amendment Request
Project stage: Request
ML22012A0902022-01-11011 January 2022
Nbsr License Amendment Request, Revised No Significant Hazard Consideration Determination
Project stage: Request
ML22011A0732022-01-20020 January 2022
NIST Acceptance of the Application for a License Amendment Re Fuel Element Latch Verification Technical Specification Revision
Project stage: Acceptance Review
ML22160A2852022-06-0808 June 2022
Nbsr License Amendment Request Supplement
Project stage: Supplement
ML22181A1282022-07-21021 July 2022
National Institute of Standards and Technology - Issuance of Amendment No. 13 to Renewed Facility Operating License No. TR-5
Project stage: Approval
2021-09-30
[Table View] |
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Category:Report
MONTHYEARML24023A6212023-12-0606 December 2023
Us Dept. of Commerce, National Institute of Standards & Technology - Problem Identification and Resolution (Pi&R) Performance Area Assessment Report
ML24023A6192023-10-23023 October 2023
NIST Center for Neutron Research Reactor Operations and Engineering (NCNR-ROE) Assessment of NCNR-ROE Procedures Program
ML24023A6222023-09-0505 September 2023
Final Report - Safety Evaluation Committee (Sec)/Safety Assessment Committee (Sac)
ML24023A6232023-09-0101 September 2023
Independent Nuclear Safety Consultant Assessment of Training at the NIST Center for Neutron Research (Ncnr) - Final
ML24023A6202023-07-11011 July 2023
Independent Nuclear Safety Consultant Assessment of the Root Cause Analysis Performed by Ncnr Into the February 3, 2021 Event at the NIST Center for Neutron Research, Revision 1
ML23207A0412023-06-0202 June 2023
Us Dept. of Commerce, National Institute of Standards & Technology, Independent Third-Party Nuclear Safety Culture Assessment of the NIST Center for Neutron Research
ML23040A3402023-03-0909 March 2023
NIST Restart Authorization Technical Evaluation Report
ML22293B8082022-10-19019 October 2022
National Institute of Standards & Technology (NIST) - License Amendment Request
ML22350A0692022-08-19019 August 2022
Us Dept. of Commerce, National Institute of Standards & Technology (Nist), Response to Request for Additional Information on License Amendment Request - Gamma Spectrum Analysis Report
ML22227A1502022-08-15015 August 2022
Us Dept of Commerce, National Institute of Standards & Technology (Nist), Request NRC Permission to Restart the Reactor Upon Completion of Listed Corrective Actions and Recovery Efforts
ML22223A1462022-08-11011 August 2022
Docket Number 50-184 and the Nbsr Requalification Plan
ML21340A0072021-12-0303 December 2021
Analysis of Cooling Flow Through 29 Fuel Elements with Fuel Element 1175 Dislodged
ML21294A3722021-10-21021 October 2021
National Institute of Standards and Technology - Supplement to October 1, 2021 Report and Restart Request
ML21288A5532021-10-15015 October 2021
NIST Center for Neutron Research - Problem Identification and Resolution
ML21274A0252021-09-30030 September 2021
Corrective Action Plan Corrective Actions Required Prior to Reactor Startup
ML21274A0262021-09-30030 September 2021
Corrective Action Plan Corrective Actions Required Post-startup
ML21274A0232021-09-21021 September 2021
Latch Improvement Safety Analysis
ML21274A0222021-09-20020 September 2021
Root Cause Response, Revision 1
ML21274A0192021-09-13013 September 2021
Ncnr Twg Report Root Cause Investigation of February 2021 Fuel Failure, Revision 2
ML21274A0212021-08-12012 August 2021
Final Report Sec Subcommittee Report: Review of the Ncnr Event Response and Technical Working Root Cause Analysis and Corrective Action Plan
ML21274A0202021-06-0303 June 2021
Ncnr Twg Report Addendum to Root Cause Investigation of February 2021 Fuel Failure
ML21153A3972021-06-0202 June 2021
Requalification Program for the Nbsr
ML21340A0082021-05-17017 May 2021
Heat Transfer in a Disc Wedged Between Two Fuel Element Plates
ML18157A1382018-05-31031 May 2018
Technical Evaluation of the Preliminary Safety Evaluation Report Supporting the Conversion to Low-Enriched Uranium Fuel for the National Bureau of Standards Reactors
ML0907001322009-03-0303 March 2009
Us Dept. of Commerce, NIST, Response to Request for Additional Information on Operator Requalification Program
2023-09-05
[Table view]
Category:Technical
MONTHYEARML24023A6212023-12-0606 December 2023
Us Dept. of Commerce, National Institute of Standards & Technology - Problem Identification and Resolution (Pi&R) Performance Area Assessment Report
ML24023A6192023-10-23023 October 2023
NIST Center for Neutron Research Reactor Operations and Engineering (NCNR-ROE) Assessment of NCNR-ROE Procedures Program
ML24023A6222023-09-0505 September 2023
Final Report - Safety Evaluation Committee (Sec)/Safety Assessment Committee (Sac)
ML24023A6232023-09-0101 September 2023
Independent Nuclear Safety Consultant Assessment of Training at the NIST Center for Neutron Research (Ncnr) - Final
ML24023A6202023-07-11011 July 2023
Independent Nuclear Safety Consultant Assessment of the Root Cause Analysis Performed by Ncnr Into the February 3, 2021 Event at the NIST Center for Neutron Research, Revision 1
ML23207A0412023-06-0202 June 2023
Us Dept. of Commerce, National Institute of Standards & Technology, Independent Third-Party Nuclear Safety Culture Assessment of the NIST Center for Neutron Research
ML23040A3402023-03-0909 March 2023
NIST Restart Authorization Technical Evaluation Report
ML22293B8082022-10-19019 October 2022
National Institute of Standards & Technology (NIST) - License Amendment Request
ML22350A0692022-08-19019 August 2022
Us Dept. of Commerce, National Institute of Standards & Technology (Nist), Response to Request for Additional Information on License Amendment Request - Gamma Spectrum Analysis Report
ML22223A1462022-08-11011 August 2022
Docket Number 50-184 and the Nbsr Requalification Plan
ML21340A0072021-12-0303 December 2021
Analysis of Cooling Flow Through 29 Fuel Elements with Fuel Element 1175 Dislodged
ML21288A5532021-10-15015 October 2021
NIST Center for Neutron Research - Problem Identification and Resolution
ML21274A0252021-09-30030 September 2021
Corrective Action Plan Corrective Actions Required Prior to Reactor Startup
ML21274A0262021-09-30030 September 2021
Corrective Action Plan Corrective Actions Required Post-startup
ML21274A0232021-09-21021 September 2021
Latch Improvement Safety Analysis
ML21274A0222021-09-20020 September 2021
Root Cause Response, Revision 1
ML21274A0192021-09-13013 September 2021
Ncnr Twg Report Root Cause Investigation of February 2021 Fuel Failure, Revision 2
ML21274A0212021-08-12012 August 2021
Final Report Sec Subcommittee Report: Review of the Ncnr Event Response and Technical Working Root Cause Analysis and Corrective Action Plan
ML21274A0202021-06-0303 June 2021
Ncnr Twg Report Addendum to Root Cause Investigation of February 2021 Fuel Failure
ML21153A3972021-06-0202 June 2021
Requalification Program for the Nbsr
ML21340A0082021-05-17017 May 2021
Heat Transfer in a Disc Wedged Between Two Fuel Element Plates
ML18157A1382018-05-31031 May 2018
Technical Evaluation of the Preliminary Safety Evaluation Report Supporting the Conversion to Low-Enriched Uranium Fuel for the National Bureau of Standards Reactors
2023-09-05
[Table view] |
Text
Corrective Action Plan September 30, 2021 Corrective Actions Required Prior to Reactor Startup SEC report reference Corrective action Comments/timing (2021)
QT-CA-1, IE-CA-6 Required training for all Operations 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, starting Proficiency Training Personnel October, ending December MS-CA-5, QT-CA-2, QT- Fuel handling training program, September - November CA-3 Fuel movement qualification clearly spelled out; training and proficiency in fuel movements and qualifications latching demonstrated and documented for operators and supervisors PR-CA-1: Fuel Rewrite OI 6.1 and OI 6.2 to capture OI revisions in movement procedure details of fuel movements and latching progress.
details PR-CA-2: Latch checks Rewrite OI 2.1 and OI 1.1A CL to OI revisions in prior to final pump include a requirement that latch checks progress.
restart be done prior to the final pump restart.
PR-CA-3, IE-CA-1: Visual check system completed and Design complete, Institute method of operational; OI 6.1 modified to include testing in progress.
visual checks. visual check. October implementation.
PR-CA-4: Independent OI 6.1 modified to require a second OI revisions in latch check individual do an independent rotational progress.
latch check prior to final visual check.
MS-CA-6, PR-CA-5: Provide required training on procedure Complete.
Procedure adherence adherence for all ROE, oversight for training supervisors.
QT-CA-5, MS-SPI-6, PR- Establish standard for operator and September - November SPI-1 Qualification supervisor qualification consistency PR-CA-6: Revise Identify procedures necessary prior to All hands effort, start procedures to be reactor restart; provide training on September. Training consistent with INPO procedure protocols; revise identified complete.11-003. procedures.
IE-CA-2 Document Analysis and justification of Complete. See Latch defense of improved improvement in latching and latch Improvement Safety latching and latch checks. Analysis.
check processes.
IE-CA-3 Modify index Corrections to positioning and fiduciary Evaluation in progress.
plate marks May have temporary corrections if manufacturing is longer term solution.
IE-CA-4 Height check Determine advisability of continuing Complete. Current determination height checks equipment does not support height checks with sufficient resolution, so latch checks are no longer prescribed.
IE-CA-5 No tool contact Modify OI 6.1 and OI 1.1A CL to assure OI revisions in following latch no tool contact will be made with the progress.
verification fuel head after the final visual latch verification.