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| | number = ML19046A393 | | | number = ML19046A393 |
| | issue date = 01/23/2019 | | | issue date = 01/23/2019 |
| | title = 01/23/2019 Draft Wg Charter | | | title = Draft Wg Charter |
| | author name = | | | author name = |
| | author affiliation = NRC/RES | | | author affiliation = NRC/RES |
Latest revision as of 05:20, 30 November 2019
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Category:Charter
MONTHYEARML19046A3932019-01-23023 January 2019 Draft Wg Charter ML17355A5322018-06-30030 June 2018 of the Charter for the Committee to Review Generic Requirements ML0309001172003-03-28028 March 2003 Charter for Operating Experience Task Force 2019-01-23
[Table view]Some use of "" in your query was not closed by a matching "". Category:Meeting Briefing Package/Handouts
MONTHYEARML24274A3232024-10-0404 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 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 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 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 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 ML21183A2012021-07-0707 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21183A2022021-07-0606 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21113A0822021-05-0606 May 2021 Appendix B - Workshop Slides ML21098A1262021-04-0606 April 2021 1B - Overview ML21098A1282021-04-0606 April 2021 1D - Modeling Overview ML21098A1312021-04-0606 April 2021 1G - Fragility ML21098A1292021-04-0606 April 2021 1E - Sierra Modeling 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 ML20267A4422020-09-29029 September 2020 Enhancement of PRA Technology for Applications: a Regulatory Research Perspective 2024-09-17
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Text
CHARTER NRC - EPRI Collaborative Research Working Group on High Energy Arcing Fault (HEAF)
Mission Statement To advance the state of knowledge and improve understanding of risk from electrical arcing fault hazards in nuclear power plants (NPPs).
Goal Statements Characterize the primary factors that influence the occurrence and severity of arcing fault events (arc flash, arc blast, or HEAF).
Develop a risk model for arcing fault events based on experimental data, operating experience, and engineering judgement.
Analyze the plant impact of and quantify the change in risk from arcing fault events involving copper and aluminum.
Team Members Ken Fleischer (Fleischer Consultants) JS Hyslop (NRC)
Dane Lovelace (Jensen Hughes) Nicholas Melly (NRC)
Shannon Lovvern (TVA) Kenn Miller (NRC)
Tom Short (EPRI) Gabriel Taylor (NRC)
Marko Randelovic/Ashley Lindeman (EPRI)
Project Managers Kelli Voelsing (EPRI)
Mark Henry Salley (NRC)
Project Sponsor Tina Taylor (EPRI)
Michael Cheok (NRC) 1 DRAFT Version 0
CHARTER NRC - EPRI Collaborative Research Working Group on High Energy Arcing Fault (HEAF)
Deliverables
- 1. Representative probabilistic risk assessment (PRA) frequencies and binning for electrical arc faults, including factors such as:
o Arc flash, arc blast, or HEAF scenario definitions o Damage to external targets vs. confined to electrical component of origin o Component type and application
- 2. A technical model for the spectrum of arcing fault events based on experimental data, operating experience, and engineering judgement that:
o includes the technical bases for representative damage models o accurately predicts the risk o is properly correlated with event frequencies and consequences o accounts for influential plant features
- 3. Representative pilot plant risk analysis. The pilot plant analysis should:
o Represent the hazard across the fleet. The contribution of arcing fault events to plant risk is expected to vary, and may require plant engagement to understand which plants have aluminum in SSCs of interest (location, configuration, amount, etc.).
o Seek industry stakeholder participation to evaluate the risk impact of the updated arcing fault model for aluminum and associated frequency.
- 4. Updated guidance to parse and more accurately characterize the risk of arcing fault events in fire PRAs. The updated methodologies and guidance should be published per the standard industry or NRC practices.
- 5. Periodic communications to keep stakeholders apprised of Working Group activities and progress.
2 DRAFT Version 0