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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 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 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 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 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 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 ML21342A1222021-12-0808 December 2021 Second Digital Twins Workshop Day 1 ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21342A1242021-09-16016 September 2021 Second Digital Twins Workshop Day 3 ML21342A1232021-09-15015 September 2021 Second Digital Twins Workshop Day 2 ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview 2024-09-17
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Lecture 8-31 Browns Ferry fireFire PRA historyRisk-informed fire protectionCurrent controversies2 Resources3Overview 10 CFR 50.48, June 16, 2004, last amended Aug. 28, 2007.-Based Standard for Fire NFPA 805, 2001 Edition, Quincy, MA, 2001. (Available through the NFPA Online Catalog at www.nfpa.org) Electric Power Research Institute and U.S. Nuclear Regulatory Commission Office -RES Fire PRA Methodology for EPRI 1011989 and NUREG/CR-6850, Electric Power Research Institute (EPRI), Palo Alto, CA and U.S. Nuclear Regulatory Commission, Washington, DC, 2005.Electric Power Research Institute and U.S. Nuclear Regulatory Commission Office Enhancements: Supplement 1 to NUREG/CR-EPRI 1019259 and NUREG/CR-6850 Supplement 1, Electric Power Research Institute (EPRI), Palo Alto, CA and U.S. Nuclear Regulatory Commission, Washington, DC, 2009.4 Other References (cont.)5Overview 6
7Browns Ferry Fire Browns Ferry (March 22, 1975)Browns Ferry Fire Browns Ferry Fire Professor George Apostolakis, UCLA(UCLA School of Engineering)Early cable spreading room analysesWASH-1400HTGR PRANRC-sponsored, post-Browns Ferry R&D at UCLA => fire PRA methodologyPhysical model for fire-induced damageIncorporation in PRA via competing processes model (growth vs. suppression)Used and refined in Zion and Indian Point PRAsFramework and tools for subsequent analyses (NUREG-1150, IPEEEs)
Fire PRA/RIDM History Empirical Support for ResultsEventSummary Description*Browns Ferry(BWR, 1975)Multi-unit cable fire; multiple systems lost, spurious component and system operations; makeup from CRD pumpGreifswald(VVER, 1975)Electrical cable fire;station blackout (SBO), loss of all normal core cooling for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, loss of coolant through valve; recovered through low pressure pumps and cross-tie with Unit 2Beloyarsk(LWGR, 1978)Turbine lube oil fire ,collapsed turbine building roof, propagated into control building, main control room (MCR) damage, secondary fires;extinguished in 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />; damage to multiple safety systems and instrumentation.Armenia(VVER, 1982)Electrical cable fire (multiple locations), smoke spread to Unit 1 MCR,secondary explosionsand fire; SBO (hose streams),loss of instrumentation and reactor control; temporary cable from emergency diesel generator to high pressure pump Chernobyl(RBMK, 1991)Turbine failure and fire, turbine building roof collapsed;loss of generators, loss of feedwater(direct and indirect causes); makeup from seal water supplyNarora(PHWR, 1993)Turbine failure, explosion and fire, smoke forced abandonment of shared MCR; SBO, loss of instrumentation; shutdown cooling pumpenergized 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> later*See NUREG/CR-6738 (2001), IAEA-TECDOC-1421 (2004)
Risk-Fire PRA/RIDM HistoryStandard and regulatory approach development Consensus processMultiple stakeholders, diverse views (incl. strong PRA critics)problem Fire PRA R&D14 15 Fire PRAs More Recent ResultsFire PRA/RIDM History From: K. VoelsingInformation Conference, March 15, 2018.Fire PRA/RIDM History 181980199520002005Browns Ferry fire(WASH-1400 analysis)IndustryFull-Scope PRAsNUREG-1150/RMIEPNFPA 805, 10 CFR 50.48(c),RG 1.205, NEI 04-02,EPRI 1011989/NUREG/CR-Current ChallengesRG 1.174, Revision 3 Excessive conservatism or optimism canInappropriately focus decision maker attentionMask opportunities for other improvementsDamage stakeholder confidence?
High Energy Arcing Faults (HEAF) in cabinetsOperational events, e.g.,Maanshan(2001)Robinson (2010)Onagawa(2011)Potentially important contributor to fire riskMulti-national experimental program21 Where are we now?22 Heterogeneity sources in a practical PRA:Multiple technical disciplinesDifferent states of knowledgeDifferent views on what needs to be and what can be reasonably modeledDifferent views on acceptable modeling approachesDifferent views on treatment of uncertaintyLimited project resourcesNumerical results need to be provided in context23 Comments24