NRC/RES/DRA/PRAB: Difference between revisions
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Latest revision as of 22:09, 26 November 2019
(NRC/RES/DRA/PRAB) | |
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Alan Kuritzky, Daniel Hudson, Jeffery Wood, John Nakoski, Lauren (Killian) Ning, Michelle Gonzalez, Selim Sancaktar, Suzanne Dennis, Walter Leschek
3 August 2009 - 31 July 2025 | |
| HQ Office | |
| HQ Division |
NRR
Division of Licensing Projects
Japan Lessons-Learned Division Division of Policy and Rulemaking
Division of Inspection and Regional Support
Division of Materials and License Renewal Division of Operating Reactor Licensing
No value Acquisition Management Division Division of Administrative Services Office of Nuclear Reactor Regulation
Division of Licensing Projects Japan Lessons-Learned Division No value Division of Policy and Rulemaking Division of Inspection and Regional Support Division of Materials and License Renewal Division of Operating Reactor Licensing Division of Regulatory Improvement Programs Division of Systems Safety and Analysis
No value Division of Construction Inspection and Operational Programs Office of Nuclear Material Safety and Safeguards
No value Division of Fuel Cycle Safety, Safeguards, and Environmental Review Division of Spent Fuel Management Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Regulatory Research
No value Division of Engineering Technology Office of Nuclear Security and Incident Response
No value Division of Security Operations
No value Governance & Enterprise Management Services Division
No value
No value
No value
No value
No value Office of the Chief Human Capital Officer
No value
No value
No value
No value
No value Office of Information Services
No value
No value
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Office of Public Affairs Region I Office of Public Affairs Region II The following 2 query conditions could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Advisory Committee on the Medical Uses of Isotopes]] OR [[:Atomic Safety and Licensing Board Panel]] OR [[:Document Control Desk]] OR [[:Embark Venture Studio]] OR [[:NRC/ACRS]] OR [[:NRC/ASLBP]] OR [[:NRC/Chairman]] OR [[:NRC/EDO]] OR [[:NRC/FSME]] OR [[:NRC/IS]] OR [[:NRC/OCAA]] OR [[:NRC/OCFO]] OR [[:NRC/OCIO]] OR [[:NRC/OCM]] OR [[:NRC/OE]] OR [[:NRC/OEDO]] OR [[:NRC/OGC]] OR [[:NRC/OI]] OR [[:NRC/OIG]] OR [[:NRC/OIP]] , [[Division::+]]</code>. Office of Nuclear Reactor Regulation
Division of Licensing Projects Japan Lessons-Learned Division Division of Policy and Rulemaking Division of Inspection and Regional Support Division of Materials and License Renewal Division of Operating Reactor Licensing Division of Regulatory Improvement Programs Division of Systems Safety and Analysis Office of Nuclear Material Safety and Safeguards
Division of Fuel Cycle Safety, Safeguards, and Environmental Review Division of Spent Fuel Management Division of Decommissioning, Uranium Recovery and Waste Programs
Division of Construction Inspection and Operational Programs Office of Nuclear Security and Incident Response
Division of Security Operations Office of Nuclear Regulatory Research
Division of Engineering Technology
Acquisition Management Division Division of Administrative Services Office of the Chief Human Capital Officer
Office of Information Services
Office of Public Affairs Region I Office of Public Affairs Region II
Some use of "" in your query was not closed by a matching "". |
Region 1Division
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Region 2Division
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Region 3Division
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Region 4Division
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| from | MONTHYEARML25154A0332025-07-310Issue date: 31 July 2025 Title: FRN: General Notice Level 3 Probabilistic Risk Assessment Project Documentation (Volume 8) ML25078A0762025-03-110Issue date: 11 March 2025 Title: RIC 2025 Digital Exhibit - from Data to Decisions: the Role of SPAR Models in Nuclear Safety ML25063A2662025-03-040Issue date: 4 March 2025 Title: NRC-RES Sitewide, All Hazards Level 3 PRA Project: Approach and Results for Multi-Unit Level 1 Risk ML25063A2732025-03-040Issue date: 4 March 2025 Title: NRC-RES Sitewide, All Hazards Level 3 PRA Project: Integrated Site Risk for Two-Unit Site ML24318B4962024-12-060Issue date: 6 December 2024 Title: The Role of Risk Analysis Research in Safety Decision-making ML24318B4972024-11-130Issue date: 13 November 2024 Title: The Role of Risk Analysis Research in Safety Decisionmaking ML24164A2112024-07-080Issue date: 8 July 2024 Title: FRN: General Notice. Level 3 Probabilistic Risk Assessment Project Documentation (Volume 7) ML24164A0102024-07-010Issue date: 1 July 2024 Title: Level 3 PRA Project, Volume 7: Dry Cask Storage PRA (Draft Report for Comment) ML24164A1782024-06-120Issue date: 12 June 2024 Title: 06/16-19/2024 Sec - Mu PRA Insights ML24141A1132024-05-200Issue date: 20 May 2024 Title: Insights from Multi-Unit Level 1, 2 and 3 Probabilistic Risk Assessment Results for Light-Water Reactor Designs - What Can Be Extrapolated to Advanced Reactor Designs? ML23194A0132023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4d Reactor, At-Power, Level 2 PRA for Internal Fires, Seismic Events, and High Winds; Draft Report for Release ML23194A0162023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4a Reactor, At-Power, Level 1 PRA for Internal Fires; Draft Report for Release ML23194A0172023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4b Reactor, At-Power, Level 1 PRA for Seismic Events; Draft Report for Release ML23194A0122023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4c Reactor, At-Power, Level 1 PRA for High Winds and Other Hazards; Draft Report for Release ML23194A0142023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4e Reactor, At-Power, Level 3 PRA for Internal Fires, Seismic Events, and High Winds; Draft Report for Release ML23194A0152023-08-310Issue date: 31 August 2023 Title: Level 3 PRA Project, Volume 4 Overview of Reactor, At-Power, Level 1, 2, and 3 PRAs for Internal Fires, Seismic Events, and High Winds; Draft Report for Comment ML23216A0372023-08-090Issue date: 9 August 2023 Title: FRN: General Notice Level 3 Probabilistic Risk Assessment Project Documentation (Volume 4) ML23010A1352023-02-090Issue date: 9 February 2023 Title: Response to Public Comments on Batch-1 ML22108A2252022-04-190Issue date: 19 April 2022 Title: FRN: General Notice. Level 3 Probabilistic Risk Assessment Project Documentation (Volume 3x) ML22048B5942022-04-120Issue date: 12 April 2022 Title: Attachment -2 EDG-Protection-Risk-Significance Assessment ML22067A2102022-04-050Issue date: 5 April 2022 Title: Level 3 PRA Project, Volume 3x: Overview of Reactor, At-Power, Level 1, 2, and 3 PRAs for Internal Events and Internal Floods (Draft) ML22067A2112022-04-050Issue date: 5 April 2022 Title: Level 3 PRA Project, Volume 3a: Reactor, At-Power, Level 1 PRA for Internal Events, Part 1 - Main Report (Draft) ML22067A2142022-04-050Issue date: 5 April 2022 Title: Level 3 PRA Project, Volume 3c: Reactor, At-Power, Level 2 PRA for Internal Events and Internal Floods (Draft) ML22067A2152022-04-050Issue date: 5 April 2022 Title: Level 3 PRA Project, Volume 3d: Reactor, At-Power, Level 3 PRA for Internal Events and Internal Floods (Draft) ML22067A2322022-04-050Issue date: 5 April 2022 Title: U.S. NRC Level 3 Probabilistic Risk Assessment (PRA) Project, Volume 2: Background, Site and Plant Description, and Technical Approach ML22067A2132022-04-050Issue date: 5 April 2022 Title: Level 3 PRA Project, Volume 3b: Reactor, At-Power, Level 1 PRA for Internal Floods (Draft) ML21235A0082022-03-310Issue date: 31 March 2022 Title: Trial Acceptability of Probabilistic Risk Assessment Results for Advanced Non-Light Water Reactor Risk-Informed Activities ML21235A0102022-03-160Issue date: 16 March 2022 Title: Trial Regulatory Analysis ML22067A2122022-03-080Issue date: 8 March 2022 Title: Level 3 PRA Project, Volume 3a: Reactor, At-Power, Level 1 PRA for Internal Events, Part 2 - Appendices (Draft) ML22061A1052022-02-180Issue date: 18 February 2022 Title: 4A-3_of_4-Hunter-Duane_Arnold_ASP_Analysis-SLIDES ML22003A1912022-01-110Issue date: 11 January 2022 Title: Letter to Victoria Anderson - Response to NEI Letter with Comments on Regulatory Guide 1.247 ML21308A0752021-11-080Issue date: 8 November 2021 Title: Using Operational Experience to Support Dynamic PRA Activities - PSA 21 Presentation ML21256A0172021-09-100Issue date: 10 September 2021 Title: Using Operational Experience to Support Dynamic PRA Activities ML21246A2162021-09-030Issue date: 3 September 2021 Title: Trial Use RG 1.247 - Acceptability of Probabilistic Risk Assessment Results for Advanced Non-:ight Water Reactor Risk-Informed Activities NUREG-2198, Figures Final2021-05-140Issue date: 14 May 2021 Title: NUREG-2198 - Figures Final ML19291B3652019-10-210Issue date: 21 October 2019 Title: The United States Regulatory Perspective on Multi-Unit Risk Consideration ML19008A1322019-01-090Issue date: 9 January 2019 Title: Generic PWR and BWR SPAR Model Memo ML19008A1332019-01-090Issue date: 9 January 2019 Title: Generic PWR SPAR Model White Paper ML19008A1342019-01-090Issue date: 9 January 2019 Title: Generic BWR SPAR Model White Paper ML18260A2902018-10-190Issue date: 19 October 2018 Title: Closeout of User Need Request NRR-2010-005 to Support in Developing Analytical Bases and Guidance for Future Risk Assessments of Consequential Steam Generator Tube Rupture (C-SGTR)Events ML18352B0992018-04-220Issue date: 22 April 2018 Title: Final Accident Sequence Precursor Analysis - Peach Bottom Atomic Power Station (Unit 3), Reactor Core Isolation Cooling System Pressure Switch Failure Results in Condition Prohibited by Technical Specifications (LER 278-2018-001) - Precurso ML18095B0132018-04-050Issue date: 5 April 2018 Title: Draft NUREG/CR-XXXX, Vol. 2, Phenomena Identification and Ranking Technique (PIRT) Exercise for Identification of Low-Power Shutdown Probabilistic Risk Assessment Modeling Priorities ML18095A9482018-04-050Issue date: 5 April 2018 Title: Draft NUREG/CR-XXXX, Vol. 1, Phenomena Identification and Ranking Technique (PIRT) Exercise for Identification of Low-Power Shutdown Probabilistic Risk Assessment Modeling Priorities ML18074A0252018-03-150Issue date: 15 March 2018 Title: Tools and Methods for Assessing the Risk Associated with Csgtr ML17349A9692018-02-210Issue date: 21 February 2018 Title: Enclosuasp Efficiency Review Memo Final ML17349A9712018-02-210Issue date: 21 February 2018 Title: Review of the Accident Sequence Precursor (ASP) Program ML17349A9702018-02-210Issue date: 21 February 2018 Title: Framework for Accident Sequence Precursor (ASP) Program Next Steps ML17349A9682018-02-210Issue date: 21 February 2018 Title: Accident Sequence Precursor (ASP) Program and Operating Experience (Ope) Program ML17151B0702017-05-310Issue date: 31 May 2017 Title: Public Meeting Summary of May 23, 2017, Teleconference with Nextera Energy Duane Arnold, LLC ML17139D4432017-05-190Issue date: 19 May 2017 Title: Us NRC Probabilistic Risk Assessment Confirmatory Success Criteria Analysis Using the Duane Arnold Site ML16237A3792016-08-240Issue date: 24 August 2016 Title: Draft Regulatory Guide DG-1285, an Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant Specific Changes to the Licensing Basis. (Aggregation Edits) ML16237A3822016-08-240Issue date: 24 August 2016 Title: DG-1285 Section 2-1 Revised Draft 7-26-16 Industry Comments ML16237A4272016-08-230Issue date: 23 August 2016 Title: ASP Analysis - Reject - Peach Bottom HPCI System Inoperable for 17 Hours Due to Flow Controller Failure - LER 278-2015-001 ML16211A1322016-08-110Issue date: 11 August 2016 Title: Quality Assurance Plan for the Level 3 PRA Project, Rev.0 ML16117A1982016-04-260Issue date: 26 April 2016 Title: Slide Presentation on U.S. NRC-RES Confirmatory Success Criteria Analysis (for May 3, 2016 Public Meeting) ML14295A3342014-10-210Issue date: 21 October 2014 Title: Memo_Transmittal of NUREG-XXXX, Development of a Statistical Testing Approach for Quantifying Software Reliability and Application to an Example System ML12233A6022012-08-270Issue date: 27 August 2012 Title: 8/10/2012 Summary of Second Closed Meeting to Discuss Ongoing Office of Nuclear Regulatory Research Confirmatory Level 1 Probabilistic Risk Assessment Success Criteria Analyses ML1135004952011-07-310Issue date: 31 July 2011 Title: (Redacted) Screening Analysis Report for the Proposed Generic Issue on Flooding of Nuclear Power Plant Sites Following Upstream Dam Failures ML0918908312009-08-030Issue date: 3 August 2009 Title: Enclosure 2: Thermal-Hydraulic Analysis to Support Update of Specific Success Criteria in the Standardized Plant Analysis Risk Model, Appendix a, Verson 2.0, Appendix a: Melcor Surry Plant System Models, Calculation Rev. 9 ML0918908202009-08-030Issue date: 3 August 2009 Title: Enclosure 1: Thermal-Hydraulic Analysis to Support Update of Specific Success Criteria in the Standardized Plant Analysis Risk Model, Version 2.0 ML0918908452009-08-030Issue date: 3 August 2009 Title: Enclosure 3: Thermal-Hydraulic Analysis to Support Update of Specific Success Criteria in the Standardized Plant Analysis Risk Model, Appendix B, Version 2.0, Appendix B: Melcor Peach Bottom Plannt System Models, Calculation Rev. 8 2025-07-31 |
| to | MONTHYEARML20218A7512020-08-070Issue date: 7 August 2020 Title: Summary of June 25, 2020 Teleconference with Grand Gulf Nuclear Station ML17151B0702017-05-310Issue date: 31 May 2017 Title: Public Meeting Summary of May 23, 2017, Teleconference with Nextera Energy Duane Arnold, LLC ML14078A5812014-04-010Issue date: 1 April 2014 Title: RASCAL 4.3 Dose Calculations in Support of Vogtle Level 3 Probabilistic Risk Assessment Project ML1034902332010-12-130Issue date: 13 December 2010 Title: Letter from B. Bradley to D. Helton Request for a 75-Day Extension to the Comment Period for Draft NUREG-1953, Confirmatory Thermal-Hydraulic Analysis Risk Models - Surry and Peach Bottom 2020-08-07 |