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Category:Report
MONTHYEARML24292A1502024-10-21021 October 2024 SSHAC Level 1 Demonstration Project ML24292A1392024-10-21021 October 2024 Applying a Graded Approach and Adapting Guidance on Site Characterization of External Hazards for Advanced Reactor and Microreactor Applications ML24292A1532024-10-21021 October 2024 Simulation of Physics-Based 0-10 Hz Synthetic Ground Motion Using High - Performance Computing Supporting Refinements to Regional Ground Motion Models for CEUS ML24213A2512024-09-23023 September 2024 A Case Study for Building Systems Theoretic Process Analysis at the Nuclear Regulatory Commission (NRC) ML24032A0102023-09-30030 September 2023 FY2023 University Nuclear Leadership Program (Unlp) Research and Development Award Executive Summaries ML23122A3062023-05-0303 May 2023 NRC Scientific Computer Code Investment Plan Public ML23030B8382023-02-0101 February 2023 Use of High Entropy Alloys (Heas) in Future Nuclear Applications ML22356A2072023-01-31031 January 2023 Volume 1 - Human Performance Test Facility ML22356A2082023-01-31031 January 2023 Volume 2 - Comparing Operator Workload and Performance Between Digitized and Analog Simulated Environments ML22356A2092023-01-31031 January 2023 Volume 3 - Supplemental Exploratory Analysis of Sensitivity of Workload Measures Ril 2022-11 ML22241A0392022-09-22022 September 2022 737 Max Digital Lessons Learned Report ML22192A0462022-09-0202 September 2022 Regulatory Considerations in Use of Digital Twin Technologies for Nuclear Reactor Application ML22235A6432022-09-0202 September 2022 Project Summary of Digital Twin Regulatory Viability in Nuclear Reactor Applications ML22143A9292022-06-0101 June 2022 NRC Technical Assessment of Electron Beam Welding ML22118A0902022-05-0505 May 2022 U.S. Nuclear Regulatory Commission Technical Assessment of Cold Spray ML22048B5932022-04-12012 April 2022 Attachment -1 Table - EDG Trips Bypass at Various Plants Based on TSs and FSARs ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML21361A2612021-12-31031 December 2021 Letter Report - TLR-RES/DE/REB-2021-17, Technical Challenges and Gaps in Digital Twin Enabling Technologies for Nuclear Reactor Applications ML21361A1762021-12-31031 December 2021 Ril 2021-18, Report on High Energy Arcing Fault Experiments, Experimental Results from Open Box Enclosures (NIST Tn 2198) (SAND2021-16075 R) ML21292A1882021-11-17017 November 2021 Technical Assessment of Additive Manufacturing-Laser Directed Energy Deposition ML21312A0862021-11-0808 November 2021 2021 Research Grant Executive Summaries ML21280A3632021-10-26026 October 2021 Watermarked for ACRS - Response to Public Comments on Proposed RG 1.244 -10-7 ML21266A0452021-09-28028 September 2021 Probabilistic Leak-Before-Break Evaluations of Pressurized-Water Reactor Piping Systems Using the Extremely Low Probability of Rupture Code ML21175A1432021-07-21021 July 2021 Office of Nuclear Regulatory Research FY2021-23 Planned Research Activities ML21174A1832021-06-25025 June 2021 RES Addendum to ANL-13/08 ML21109A1232021-05-31031 May 2021 TLR-RES/DE/CIB-2021-07, Additional Technical Information in Support of the Review of Subpart a, Graphite Materials ML21145A0882021-05-24024 May 2021 Fellowship Executive Summaries ML21145A0902021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21145A0892021-05-24024 May 2021 Scholarship Executive Summaries ML21145A0872021-05-24024 May 2021 Faculty Development Executive Summaries ML21155A1352021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21155A1342021-05-24024 May 2021 Scholarship Executive Summaries ML21155A1332021-05-24024 May 2021 Fellowship Executive Summaries ML21155A1322021-05-24024 May 2021 Faculty Development Executive Summaries ML21113A0812021-05-0606 May 2021 Ril AMT Workshop Summary ML21097A0632021-04-0707 April 2021 Fy 2020 Research and Development Grant Executive Summaries ML21084A0412021-03-31031 March 2021 Tlr RES DE CIB-CMB-2021-04, Corrosion in Gas-Cooled Reactors ML21084A0392021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-03, Technical Assessment of Materials Compatibility in Molten Salt Reactors ML21088A0132021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-05 - Status of Anlwr Research Activities - Materials Chemistry and Component Integrity ML21088A0472021-03-31031 March 2021 NRC Non-Light Water Reactor (non-LWR) Vision and Strategy, Volume 5 - Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle ML20345A0032021-01-19019 January 2021 TLR-RES/DE/CIB-2020-11, Basis for a Potential Alternative to Revision 2 of Regulatory Guide 1.99 ML20351A2042021-01-0808 January 2021 NRC Technical Assessment of Additive Manufacturing - Laser Powder Bed Fusion ML20287A1982021-01-0101 January 2021 Public Comment Dispositions on DG-1370 for Regulatory Guide (RG) 1.191, Rev 1, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20308A7442020-11-0303 November 2020 NRC Non-Light Water Reactor (Non-LWR) Vision and Strategy, Volume 5 Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle, Draft ML20311A2622020-10-19019 October 2020 Technical Letter Report - TLR-RES/DE/CIB-2020-06, Evaluation of PWSCC Subcritical Crack Growth in Complex Geometries Using Abaqus Xfem ML20245E1862020-09-30030 September 2020 RIL-2020-09, International Workshop on Advanced Non-Light Water Reactor - Materials and Component Integrity ML20227A3882020-09-11011 September 2020 Enclosure 1 - Table FY2019 Risk-Informed Activitity Website Links ML20227A3902020-09-11011 September 2020 Enclosure 3 - Risk Explanation FY2020 Risk-Informed Activity Website ML20245E4572020-09-0101 September 2020 Draft Preface ML20164A2132020-07-31031 July 2020 Response to Comments on DG-3036 for RG 3.15, Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant 2024-09-23
[Table view]Some use of "" in your query was not closed by a matching "". Category:Technical
MONTHYEARML24213A2512024-09-23023 September 2024 A Case Study for Building Systems Theoretic Process Analysis at the Nuclear Regulatory Commission (NRC) ML23122A3062023-05-0303 May 2023 NRC Scientific Computer Code Investment Plan Public ML23030B8382023-02-0101 February 2023 Use of High Entropy Alloys (Heas) in Future Nuclear Applications ML22356A2072023-01-31031 January 2023 Volume 1 - Human Performance Test Facility ML22356A2082023-01-31031 January 2023 Volume 2 - Comparing Operator Workload and Performance Between Digitized and Analog Simulated Environments ML22356A2092023-01-31031 January 2023 Volume 3 - Supplemental Exploratory Analysis of Sensitivity of Workload Measures Ril 2022-11 ML22241A0392022-09-22022 September 2022 737 Max Digital Lessons Learned Report ML22192A0462022-09-0202 September 2022 Regulatory Considerations in Use of Digital Twin Technologies for Nuclear Reactor Application ML22235A6432022-09-0202 September 2022 Project Summary of Digital Twin Regulatory Viability in Nuclear Reactor Applications ML22143A9292022-06-0101 June 2022 NRC Technical Assessment of Electron Beam Welding ML22118A0902022-05-0505 May 2022 U.S. Nuclear Regulatory Commission Technical Assessment of Cold Spray ML21361A2612021-12-31031 December 2021 Letter Report - TLR-RES/DE/REB-2021-17, Technical Challenges and Gaps in Digital Twin Enabling Technologies for Nuclear Reactor Applications ML21361A1762021-12-31031 December 2021 Ril 2021-18, Report on High Energy Arcing Fault Experiments, Experimental Results from Open Box Enclosures (NIST Tn 2198) (SAND2021-16075 R) ML21292A1882021-11-17017 November 2021 Technical Assessment of Additive Manufacturing-Laser Directed Energy Deposition ML21266A0452021-09-28028 September 2021 Probabilistic Leak-Before-Break Evaluations of Pressurized-Water Reactor Piping Systems Using the Extremely Low Probability of Rupture Code ML21174A1832021-06-25025 June 2021 RES Addendum to ANL-13/08 ML21109A1232021-05-31031 May 2021 TLR-RES/DE/CIB-2021-07, Additional Technical Information in Support of the Review of Subpart a, Graphite Materials ML21113A0812021-05-0606 May 2021 Ril AMT Workshop Summary ML21097A0632021-04-0707 April 2021 Fy 2020 Research and Development Grant Executive Summaries ML21084A0412021-03-31031 March 2021 Tlr RES DE CIB-CMB-2021-04, Corrosion in Gas-Cooled Reactors ML21084A0392021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-03, Technical Assessment of Materials Compatibility in Molten Salt Reactors ML21088A0132021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-05 - Status of Anlwr Research Activities - Materials Chemistry and Component Integrity ML21088A0472021-03-31031 March 2021 NRC Non-Light Water Reactor (non-LWR) Vision and Strategy, Volume 5 - Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle ML20345A0032021-01-19019 January 2021 TLR-RES/DE/CIB-2020-11, Basis for a Potential Alternative to Revision 2 of Regulatory Guide 1.99 ML20351A2042021-01-0808 January 2021 NRC Technical Assessment of Additive Manufacturing - Laser Powder Bed Fusion ML20308A7442020-11-0303 November 2020 NRC Non-Light Water Reactor (Non-LWR) Vision and Strategy, Volume 5 Radionuclide Characterization, Criticality, Shielding, and Transport in the Nuclear Fuel Cycle, Draft ML20311A2622020-10-19019 October 2020 Technical Letter Report - TLR-RES/DE/CIB-2020-06, Evaluation of PWSCC Subcritical Crack Growth in Complex Geometries Using Abaqus Xfem ML20245E1862020-09-30030 September 2020 RIL-2020-09, International Workshop on Advanced Non-Light Water Reactor - Materials and Component Integrity ML20227A3882020-09-11011 September 2020 Enclosure 1 - Table FY2019 Risk-Informed Activitity Website Links ML20227A3902020-09-11011 September 2020 Enclosure 3 - Risk Explanation FY2020 Risk-Informed Activity Website ML20245E4572020-09-0101 September 2020 Draft Preface Regulatory Guide 1.2362020-07-30030 July 2020 Draft for ACRS Review ML20191A0692020-07-0101 July 2020 Research Paper on NuScale Boron Dilution and Incursion ML20168A7952020-04-30030 April 2020 the Influence of Walls, Corners, and Enclosures on Fire Plumes ML20065K9062020-03-31031 March 2020 Office of Nuclear Regulatory Research Fy 2020-22 Planned Research Activities ML20045F2822020-02-29029 February 2020 RIL-2001, Part 1, - Proceedings of NRC Annual Probabilistic Flood Hazard Assessment Research Workshops I-IV ML20045F2832020-02-14014 February 2020 RIL-2001, Part 2, - Proceedings of NRC Annual Probabilistic Flood Hazard Assessment Research Workshops I-IV ML20045F2842020-02-14014 February 2020 RIL-2001, Part 3, - Proceedings of NRC Annual Probabilistic Flood Hazard Assessment Research Workshops I-IV ML20045F2852020-02-14014 February 2020 RIL-2001, Part 4, - Proceedings of NRC Annual Probabilistic Flood Hazard Assessment Research Workshops I-IV ML20030A1782020-01-31031 January 2020 NRC Non-Light Water Reactor Vision and Strategy; Volume 3 - Computer Code Development Plans for Severe Accident Progression, Source Term, and Consequence Analysis ML20030A1772020-01-31031 January 2020 NRC Non-Light Water Reactor Vision and Strategy; Volume 2 - Fuel Performance Analysis for Non-LWRs ML20030A1762020-01-31031 January 2020 NRC Non-LWR Water Reactor Vision Strategy; Volume 1 - Computer Code Suite for Non-LWR Plan Systems Analysis ML20030A1742020-01-31031 January 2020 Approach for Code Development in Support of Nrc'S Regulatory Oversight of Non-Light Water Reactors - Introduction ML19203A0892019-07-31031 July 2019 Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report ML19144A0892019-05-30030 May 2019 TLR-Criteria for Postulating Pipe Rupture Locations Background and History ML17264A6442017-09-25025 September 2017 Draft Report - Soarca Project Sequoyah Integrated Deterministic and Uncertainty Analyses ML19023A4342017-08-10010 August 2017 the Applicability of Human Factors Engineering Analyses in Retail Stores - Appendices ML19023A4352017-08-10010 August 2017 the Applicability of Human Factors Engineering Analyses in Retail Stores - Main Report ML20093F0032011-01-0101 January 2011 SAND2011-0128 - Accident Source Terms for LWR NPPs Using High-Burnup or MOX Fuel ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version 2024-09-23
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DRAFT PREFACE This body of work illustrates the NRCs effort to appropriately credit human actions within flexible coping strategies (FLEX) using a systematic, qualitative approach to produce human error probability (HEP) estimates. Volume 1 of this report, Utilization of Expert Judgment to Support Human Reliability Analysis of Flexible Coping Strategies (FLEX), was completed in 2018 as an assessment of FLEX action feasibility using data collected by the NRC staff. This information was used to inform the development of the NRCs Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA). IDHEAS-ECA is a human reliability analysis (HRA) method that can be used for FLEX and Non-FLEX actions. Upon completion of the method, in 2019, the NRC and industry further explored the feasibility of FLEX actions using IDHEAS-ECA. This work is documented in Volume 2 of this report, Flexible Coping Strategies (FLEX) HRA Using IDHEAS-ECA. The two reports demonstrate how the teams of experts were used and describe how each project was introduced into the NRCs framework for FLEX. Both projects capture the state of knowledge and uncertainties of the technical issues within FLEX and non-FLEX scenarios, however, there are several differences between each project.
In Volume 1, the staff performed an expert elicitation to obtain benchmark human error probabilities (HEPs) of FLEX actions and to understand the performance influencing factors associated with the use of portable FLEX equipment. This information was then used to benchmark IDHEAS-ECA. The expert elicitation project scope was developed to capture the variation of FLEX and non-FLEX scenarios and estimate the HEP ranges of the five FLEX actions. In particular, the project captured which performance influencing factors might drive the HEPs up or down.
Volume 2, on the other hand, describes FLEX scenario evaluation using a new HRA method built specifically to handle FLEX actions: IDHEAS-ECA. Along with the method, the staff developed a software tool to take the qualitative analysis of FLEX actions and produce quantitative results, HEP values.
The technical approaches and scenario context were slightly different among the two projects.
Volume 1 Implemented principles and processes of the NRCs Expert Elicitation Guidance, ML16287A734, and included an expert panel with experience in PRA/HRA, auditing FLEX strategies, and understanding maintenance practices in nuclear power plants. The NRC provided the expert panel with the scenario limitations and human failure events to analyze for the scenarios. Since FLEX varies from plant to plant, there were challenges to create base, generic scenarios due to limited FLEX information. Therefore, the NRC project leads first developed a skeleton of the scenarios prior to the workshop, then had the expert panel develop the details of the scenarios.
Volume 2 used a similar framework as the expert elicitation with a larger set of participants and resources to implement data collection. To the extent possible, scenarios were based on relevant previous efforts to develop HRA/PRA scenarios for FLEX (e.g., EPRIs November 2018 report and Volume 1 of this report). However, when performing this work (Volume 2), the HRA analysts evaluated scenarios and HFEs for specific nuclear power plants. The analysis approach allowed HRA analyst to attend a boiling water reactor (BWR) and a pressurized water reactor (PWR) site visit. The plant visits were the predominant sources of detailed HRA-relevant FLEX information for the HRA analyst to reference. Lastly, information from a small
group of PWR Owners Group and BWR Owners Group representatives, and FLEX experts (both NRC and industry) supplemented the plant-specific information from the two sites to provide a more generic operational understanding of FLEX strategies and equipment analyzed in the scenarios.
Because of the plant visits coupled with the input from FLEX and operational experts throughout the project, the second project team (Volume 2) developed more credible and detailed HRA/PRA scenarios than those for the expert elicitation (Volume 1). Also, because of the time gap between the two efforts, Volume 2 captures the increased reliability of operator actions due to industry improvements to their FLEX programs from 2018 to 2019.
In conclusion, both projects serve as a bases to explore the data and knowledge of FLEX within HRA. They demonstrate a cohesive effort to address the challenges identified in existing HRA methods and create solutions to bridge the gaps of understanding. Previous methods used by the NRC assumed that FLEX actions were not feasible. However, these two-projects provide evidence of feasibility. Both efforts increased the understanding of operator actions using FLEX equipment and developed estimates of their feasibility to inform and improve analysis, methodologies, and quantification tools.