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Category:Meeting Briefing Package/Handouts
MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML22340A5892022-12-13013 December 2022 Boas HPS_Drop-in_12-13-2022 ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21183A2012021-07-0707 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21183A2022021-07-0606 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21113A0822021-05-0606 May 2021 Appendix B - Workshop Slides ML21098A1292021-04-0606 April 2021 1E - Sierra Modeling ML21098A1312021-04-0606 April 2021 1G - Fragility ML21098A1282021-04-0606 April 2021 1D - Modeling Overview ML21098A1262021-04-0606 April 2021 1B - Overview ML21069A0202021-03-0303 March 2021 Phenomena Identification and Ranking Tables: U.S. NRC Perspective ML21057A1672021-03-0101 March 2021 Public Meeting - HELB - NRC Presentations on Alternative Acceptance Criteria for Postulating Pipe Break Locations - March 2021 ML20336A0042020-12-0707 December 2020 Opening Session - NRC Public Workshop on Advanced Manufacturing Technologies for Nuclear Applications ML20304A5012020-11-0505 November 2020 Rev 3 - ACRS Fc Briefing for the Advisory Committee on Reactor Safeguards Full Committee - Final ML20283A6162020-10-15015 October 2020 Presentation: Nrc'S Preparations for Advanced Reactor Licensing, ORNL Molten Salt Workshop, October 14-15, 2020 ML20289A6582020-10-0808 October 2020 Enclosure 3 - NRC Presentation on Nrc'S Crediting FLEX Effort 2024-09-17
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MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24213A0642024-07-31031 July 2024 Presentation - NRC Work on Thermal Aging Embrittlement of Austenitic Stainless Steel Weld Metal Implications for Section XI Flaw Evaluation Procedures ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24029A2372024-03-12012 March 2024 03/12-14/2024 Regulatory Information Conference (RIC) ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23166A1122023-06-14014 June 2023 Presentation on Artificial Intelligence and Machine Learning Support for Probabilistic Fracture Mechanics Analysis ML23193B0422023-06-11011 June 2023 Applications of the Extremely Low Probability of Rupture (Xlpr) Code ML23150A0242023-05-17017 May 2023 0a -Welcome (NRC) ML23150A0262023-05-17017 May 2023 0c - Working Group ML23121A2552023-05-0202 May 2023 Public Meeting to Discuss Revision of Regulatory Guide 1.200 and Updates to Technical Guidance Related to Risk-Informed Activities ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML23058A2132023-02-27027 February 2023 HTGR Workshop 2023 Slides - Final ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22179A3342022-06-28028 June 2022 NRC Public Meeting - Advanced Manufacturing Technologies, June 28, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22080A0472022-03-22022 March 2022 Anticipated Impacts of Nuclear Accidents, Presentation for 2022 Society for Benefit-Cost Analysis Annual Conference, 3-22-2022 ML22083A2042022-03-15015 March 2022 Presentation on NRC Regulatory Research - Enabling Regulatory Readiness for Accident Tolerant Fuel, March 22, 2022 ML22140A3092022-03-0808 March 2022 bush-goddards-hv-w12 ML22140A3112022-03-0808 March 2022 coffins-hv-t7 ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML22040A1802022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Thaggard M - Safety Marker Study ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit 2024-09-17
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Text
Enhancement of PRA Technology for Applications:
A Regulatory Research Perspective*
Nathan Siu and Mehdi Reisi Fard Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission IAEA Technical Meeting on the Enhancement of Methods, Approaches and Tools for Development and Application of Probabilistic Safety Assessments September 29-October 2, 2020
- The views expressed in this presentation are not necessarily those of the U.S. Nuclear Regulatory Commission
Outline
- Role of regulatory research at NRC
- Comments on potential PSA technology* TM Organizer Questions enhancements
- Why it is important to consider the
- Dynamic PSA subject from a PSA research
- Combinations of hazards perspective?
- Portable equipment
- Development of SAMGs national/international status of
- Level 3 PSA practice/experience?
- Software reliability and modelling
- What are the current challenges
- Incorporation of ageing aspects and open issues?
- Treatment of uncertainties**
- In this presentation Technology = {methods, models, tools, data}
2 **Added to organizer list
ROLE OF REGULATORY R&D 3
Role of Regulatory R&D Ultimate NRC Regulatory R&D: Purpose Purpose and Considerations Adapted from NUREG-2150 NRC/RES TSOs Multiple Multiple Applications Universities Actors Stakeholders Analyses (incl. reviews)
Industry (A)
R&D needs, wants, Other Agencies priorities International Methods, Models, Tools, Databases, Technology Multiple (capabilities)
Resources Uses Standards, Technical analyses
- People Guidance, (T)
Technology development
- Funds Tests/experiments
- Infrastructure
- Information Surveys/reviews Foundational Knowledge (K) Context Multiple Products 4
Role of Regulatory R&D NRC Regulatory R&D: More Considerations Multiple regulatory functions (and decision types)
Risk-informed decision making Time Scale Near Term Long Term (User Need) (Future-Focused)
Current Trends Not just reactors 5
Role of Regulatory R&D Some Trends
- Increased number of applications
- Increased credit for capabilities (e.g., FLEX)
- Greater role in design (e.g., LMP)
- Novel designs, technologies, and operational concepts Photo courtesy of NEA Halden Reactor Project
- Improving analysis capabilities
- Computational resources
- Smart technologies (e.g., content analytics) Challenge :
Be Ready!
- Changing workforce (KSAs, preferences) 6
A:
Analyses Analyses (for application)
- Why it is important to consider the subject from a T: Technology Technology (provides capability)
PSA research perspective?
- What is the current status of practice/experience? K: Knowledge Knowledge (provides context)
- What are the challenges and open issues?
COMMENTS ON POTENTIAL PRA TECHNOLOGY ENHANCEMENTS 7
Dynamic PSA
- Analyses (anticipated, potential) Long history (starting with fast rx)
- Advanced reactor design approvals
- Operating reactor risk-informed applications (e.g., FLEX, security)
- External hazards scenarios (e.g., flooding)
- Technology Not always complicated
- Improved realism (fewer modelling approximations)
- Reduced completeness uncertainties (e.g., EOCs, passive systems)
- Improved synergy (other fields, educational trends) Computational capabilities + investments (e.g.,
A. Amendola and G. Reina, Event Sequences and J.M. Lanore, et al, Progress in Methodology for Probabilistic Assessment of Accidents: Timing of
- DOE, TSOs, universities) => time to reap benefits?
Accident Sequences," ANS/ENS Intl Mtg Probabilistic Knowledge Consequence Spectrum: A Methodology for Probabilistic Transient Analysis," Nuclear Technology, 77, 297-315(1981). Risk Assessment, Port Chester, NY, 1981.
- Technology development TAF
- International: some applications T. J. McIntyre and N. Siu, "Electric Power Recovery at TMI-1, A Simulation Model," ANS/ENS Intl Topical Mtg Thermal Reactor Safety, San Diego, California, February 2-6, 1986.
- Communication and perception
- Investment requirements, cost/benefit
- Cultural resistance See also draft white paper (ML19066A390) and presentation from 2019 IAEA workshop 8
(ML19248C656)
Combination of Hazards
Treatment of consecutive events
- Current risk-informed applications (specific (and pre-conditioning)?
combinations)
- Improved realism (correlation of hazards)
- Reduced completeness uncertainties
- Improved synergy with natural hazards community
- Some methods developed and used, included in PRA Role of stochastic simulation?
standards and guidance
- Participation in international activities
- Efficient identification and prioritization
- Data augmentation (simulation?)
- Communication (discipline-specific frameworks -
what is a hazard? Area of responsibility when Hurricane tracks adapted from University of Wisconsin-Milwaukee performing analyses?) (https://web.uwm.edu/hurricane-models/models/archive/)
Emergency response based on data from National Hurricane Center:
(https://www.nhc.noaa.gov/1992andrew.html) 9
Portable Equipment
- Importance (Benefits) Task-Based Simulation: Old Idea, Recent Applications
- Other non-safety related equipment
- Improved HRA for ex-MCR activities (possibly including task-based simulation)
- Improvements (practice, methods?) in constructing informed priors (potential)
- Improved insights M.T. Lawless, K.R. Laughery, and J.J. Persensky, Using Micro Saint to Predict Performance in a
Nuclear Power Plant Control Room: A Test of Validity and Feasibility, NUREG/CR-6159, 1995.
- Strong interest, many applications (e.g., NOED, CRM, SDP, licensing actions, NTTF 2.1 seismic PRA)
- Further applications being developed
- HRA (e.g., granularity/aggregation, quantification)
S. Fogarty, Approaches and Tools to Quantifying Facility Security Risk, INMM Workshop on Risk-Informed Security , Stone Mountain, GA, February 11-12, 2014.
See also presentation from 2019 IAEA workshop (ML19248C655) 10
Development of SAMGs
- Importance (Benefits) SOARCA Assessment of B.5.b Measures
- Improved HRA for post-core damage
- Severe-accident induced cascading failures
- Additional/improved insights (e.g., to prioritize severe accident R&D)
- Some changes identified during FLEX implementation
- Multi-source dependencies
- Appropriate realism (scope, avoiding Game Over)
D. Collins, et al., Modeling Potential Reactor Accident Consequences, NUREG/BR-0359 Rev. 1, 2012. (ML12347A049) 11
Level 3 PSA
- Demonstration of LMP for operating plants Level 3 PRA Project Scope
- Regulatory analysis guidance revisions (potential)
- Developments in selected areas (e.g., multi-source PRA)
- Improved insights regarding safety margins
- Improved insights for performing analyses (risk, feasibility of and benefits from future Level 3 studies)
- Improved staff capabilities for performing and reviewing PRAs
- Reference plant state-of-practice study ongoing
- Broad scope Integration across all sources, hazards Resources 12
Software Reliability and Modeling
- Analyses WGRISK Benchmarking Study
- Licensing digital upgrades
- Improved hazard identification
- Reduced completeness uncertainties
- Improved synergy with I&C community
- Technology development (e.g., integration of STAMP/STPA with conventional PRA)
- Activities include WGRISK benchmarking study
- Challenges M. Porthin, et al., Comparative application of digital I&C modeling approaches for PSA,
- Software CCF International Topical Meeting on Probabilistic Safety Assessment (PSA 2019), Charleston, SC, April 28-May 3, 2019.
Incorporation of Ageing Aspects
- Importance (Benefits) Analysis technology exists
- Capabilities should regulatory need arise As good as new
- Knowledge Blending mechanistic and statistical perspectives
- Improved insights changes PRA approach?
- Long history of R&D, no recent work
- Challenges Importance of burn-in?
- Physics of failure modeling
- Incorporation in PRA Standards 14
Treatment of Uncertainties Model uncertainties can be characterized; consensus
- Importance (Benefits) approach for quantification?
- All risk-informed applications (operating reactors and new designs)
- Improved characterization methods
- Improved synergy with other technical communities From static (handoff) to dynamic (interaction)?
- Established methods and guidance
- Improvements being considered in R&D planning Adapted from NUREG-2156
- Quantitative assessment (model and completeness uncertainties), particularly for new designs