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Category:Report
MONTHYEARML23122A3062023-05-0303 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 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 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 ML21155A1332021-05-24024 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 ML21145A0882021-05-24024 May 2021 Fellowship Executive Summaries ML21145A0872021-05-24024 May 2021 Faculty Development Executive Summaries ML21155A1342021-05-24024 May 2021 Scholarship Executive Summaries ML21155A1352021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary 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 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 ML21088A0132021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-05 - Status of Anlwr Research Activities - Materials Chemistry and Component Integrity ML21084A0392021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-03, Technical Assessment of Materials Compatibility in Molten Salt Reactors ML21084A0412021-03-31031 March 2021 Tlr RES DE CIB-CMB-2021-04, Corrosion in Gas-Cooled Reactors 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 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 NUREG-2233, EPRI 3002016054 Comments Resolution2020-03-31031 March 2020 NUREG-2233 EPRI 3002016054 Comments Resolution 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 2023-05-03
[Table view]Some use of "" in your query was not closed by a matching "". Category:Technical
MONTHYEARML23122A3062023-05-0303 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 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 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 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 ML21088A0132021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-05 - Status of Anlwr Research Activities - Materials Chemistry and Component Integrity ML21084A0392021-03-31031 March 2021 TLR-RES/DE/CIB-CMB-2021-03, Technical Assessment of Materials Compatibility in Molten Salt Reactors 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 ML20227A3902020-09-11011 September 2020 Enclosure 3 - Risk Explanation FY2020 Risk-Informed Activity Website ML20227A3882020-09-11011 September 2020 Enclosure 1 - Table FY2019 Risk-Informed Activitity Website Links 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 ML20030A1742020-01-31031 January 2020 Approach for Code Development in Support of Nrc'S Regulatory Oversight of Non-Light Water Reactors - Introduction 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 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 ML0227603052002-09-30030 September 2002 Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Signature Page ML0609406041998-07-22022 July 1998 Confirmatory Action Letter 97-7-001 Technical Evaluation ML19204A1611998-03-31031 March 1998 Technical Evaluation Report on the Submittal Only Review of the Individual Plant Examination of External Events at Brunswick Nuclear Plant, Units 1 and 2 - Final Report ML19227A3271988-09-30030 September 1988 Fission Product Behavior During Severe LWR Accidents: Modeling Recommendations for the Melcor Code System, Volume I: Fission Product Release from Fuel. 2023-05-03
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Annual Request for Risk-Informed Activity Information Risk Explanations The purpose of the Risk-Informed activities website is to provide and inform the public how the agency uses risk-information, risk assessment and Probabilistic Risk Assessment (PRA) in its regulatory decision making. Each of the activities submitted must include an explanation as to why the activity is classified as Risk-Informed and examples of what decisions were made that were based upon risk information. Understand that if purely deterministic considerations are involved, the activity should not be on this public website. This explanation should be at the very beginning of the activity summary description section and again referenced at the beginning of the current years update.
Risk Explanation Content:
- a. Use PRA information. Explain how the Licensee PRA information or NRC risk models were used, or
- b. If PRA results or methods were not used, explain how results, findings and insights from a risk assessment were used. A risk assessment can consider relevant safety margins, defense-in-depth attributes, success criteria, equipment functionality, reliability and availability. A risk assessment can involve the following:
- Consider the Risk triplet: What can go wrong? How likely is it? What are the consequences? Explain which of these three questions were asked and answered for the activity.
- Provide reference to the frequency of something associated with the activity and how decisions were made associated with those things that are more likely to occur.
Identify the available evidence and the processing of that evidence to quantify the probability and the uncertainties involved. Lacking evidence explain the predictive approach for considering frequency.
- Assess the probable range of outcomes or consequences that are end states of the activity analyses.
- Explain how the activity risk-informed decisions integrated the five key principles:
- 1) Current Regulations Met, 2) Defense-in-Depth Consistency, 3) Maintenance of Safety Margins, 4) Risk-Informed Analysis, and 5) Performance Monitoring.
- Consider a broader set of potential challenges to safety. Provide a logical means for prioritizing these challenges based on risk significance, operating experience, and/or engineering judgement. Consider a broader set of resources to defend against the challenges and quantify sources of uncertainty in the analysis, while testing the sensitivity of the results to key assumptions.
Enclosure 3