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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 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 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 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 2024-09-17
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Plant Systems ModelingWorkshop 3 1
Learning Objectives
- Introductory knowledge of typical NPP systems, structures, and components (SSCs) modeled in PRAs*Practice with thought process, elements, and mechanics of NPP PRA 2Important:
a)The workshop problems can be performed as group exercises.
b)The purpose is to exercise the modeling thought process, not to get the "right answer."
Fenwick 1 NPP
-BackgroundIn an effort to expand its footprint in a global marketplace, the Grand Duchy of Fenwick has decided to build a distillery to mass produce a brandy based on their famous Pinot Grand Fenwick wine. akaKaroEngineering, a boutique firm known in some circles for its excellence in technical editing but not yet well
-practiced in nuclear power plant design, has proposed that the Duchy use a small boiling water reactor to provide process heat to the distillery, as well as electric power for domestic use and export.The proposed plant would be located at the foot of Mount Fenwick and overlooking the scenic Fenwick River, the Duchy's lone river. (This location would provide a unique and attractive location for aprésskiing events.) Substantial capital cost reductions would be achieved through: a) the elimination of multiple components found in most nuclear power plant designs and b) the use of identical components (e.g., for valves and electrical breakers) whenever possible.
3 Fenwick 1 NPP
-Other Notable FeaturesOther notable features of the proposed, conceptual design are as follows.
- Direct use of reactor steam to provide process heat to the distillery
- A novel, submerged condenser for normal heat rejection
-cooled emergency diesel generator to provide onsite power should offsite power be lost
-drive safety injection pump to provide cooling water. The pump would normally be electric
-motor driven, but a steam
-driven turbine could be connected to the pump should all power be lost.
- A direct vent to the atmosphere for reactor steam used to drive the backup safety injection system turbine
- A containment building to contain radioactive releases, should a severe accident occur
- Major components in the Nuclear Steam Supply System (NSSS) and electrical distribution system (with key loads) are shown on the following pages. The mechanical components are designated by system (e.g., "SI" for safety injection" and type (e.g., "P" for pump). The electrical components are designated by electrical bus (e.g., "A" for the 6.9 kV emergency power bus) and type (e.g., "X" for transformer).
4 Fenwick 1 Location and Plan 5
Fenwick 1
-NSSS and Safety System (Schematic) 6DesignatorPre-hyphenFW NS SI SWPost-hyphen C F P R V TOtherNSSSDescriptionFeedwaterNSSSSafety InjectionService WaterCondenserFilterPumpReactorValveTurbineNuclear Steam Supply
©akaKaroEngineering, 2018 7©akaKaroEngineering, 2018DesignatorPre-hyphen A B CFW NI NS SI SW VI X Y ZPost-hyphen B C F G M P R S V T XOtherBat.M-CCMCRMGSNSSS VACVDCDescription6900 VAC non
-vital bus A4160 VAC non
-vital bus B250 VDC non
-vital bus CFeedwater125 VDC non
-vital I&C bus NVNSSSSafety InjectionService Water125 VDC vital I&C bus VI6900 VAC vital bus X4160 VAC vital bus Y250 VDC vital bus ZBatteryCondenserFilterEmergency Diesel Generator MGSPumpReactorSwitchgear/M
-CC/Distribution PanelValveTurbineTransformerBatteryMotor Control CenterMain Control RoomMotor Generator SetNuclear Steam Supply SystemVolts (Alternating Current)Volts (Direct Current)Fenwick 1
-Electrical DistributionNotes: 1)Small box indicates a breaker2)Large box indicates a load Exercises*
1.Initiating Event Identification a.Identify some potentially important initiating events for the plant. For each event, describe: (i) why you think it is an initiating event, and (ii) why you think it's potentially important.
b.Identify some potentially important external hazards for the plant. For each hazard, describe why you think it's potentially important.
2.Event Tree DevelopmentSelect an initiating event and develop an event tree for plant response following that initiating event.
3.Fault Tree Development a.Develop a fault tree for the SI system. Identify the minimal cut sets.
b.If time permits, (i) develop fault trees for all of the top events in your event tree and (ii) identify some minimal cut sets for core damage.
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