a.ADS (University of California at Los Angeles)

b.ADAPT (Sandia National Laboratories)

a. RAVEN (Idaho National Laboratory)

b. PyCATSHOO (Electricite de France)

8:00-9:00am (spouse/guest)

Spouse/Guest Breakfast (8:00-9:00am)

a. Welcome Greeting – General Chair Kevin R. O’Kula

b. Welcome from Mayor Pro Tem, Peter Shahid, City of Charleston, South Carolina

c. Welcome from Professor Mohammad Modarres, Technical Program Chair

d. Keynote Presentation, Safe Enough? WASH-1400 and Its Legacy, Mr. Thomas Wellock, U.S. Nuclear Regulatory Commission Historian

e. Presentation from Professor Mohammad Modarres to WASH-1400 Authors

f. Remarks from WASH-1400 Authors: Richard Denning, Joseph Murphy, and Ian Wall

27102 PRA Knowledge Management: Preserving Data and Information

Professor Mohammad Modarres, Moderator

Panel: George Apostolakis (NRRC), Robert Budnitz (LBNL (ret.), Michael Cheok (NRC), Ali Mosleh (UCLA), and Marina Röwekamp (GRS)

PSA 2019 Luncheon – Daniel Churchman, Fleet Engineering Director for SNC

Sponsored by Westinghouse

27149 Development of Multi-Unit PSA Model for the Case Study of the IAEA Project

26718 Seismic Correlation Modeling in Multi-Module PRAs

26900 An Approach to Developing an Integrated Site Probabilistic Risk Assessment (PRA) Model

26641 Simplified Structural Steel Analysis to Support Assumption of Loss of One Column for Building Structural Integrity

27035 An Approach for Apportioning Fire Scenario Frequencies to Induced Initiating Events

27151 Characterization of Interruptible and Growth Fires for Nuclear Power Plant Applications

27105 Summary of the results of 4th Mandate of PSA Working Group Established by Co-operation Forum for VVER Regulators

27409 BWROG Insights based on PRA Peer Review F&O Closure Workshops

26949 PWROG SAMG Implementation Lessons Learned

27036 Quantitative Risk Analysis Support to Decision-Making for New Systems

27121 Applying Risk-Informed Decision-Making to the Acceptance Criteria for Evaluating Leak-Before-Break Analyses in Piping Which is Susceptible to Primary Water Stress Corrosion Cracking Degradation

27038 Identifying Key Factors Affecting the Performance of Decision-Making Tasks Included in SAMGs

26876 Decision Making for Active and Passive Safety Systems Alternative: Preliminary Assessment

27027 Interfacing Passive System Performance Degradation Initiated by Nuclear Power Plant Operator Action

27100 Bathtub Shaped Hazard Rate functions Change Points Determination; Hazard Graph’s Properties

27127 A Method for Considering Numerous Combinations of Plant Operational States in Multi-Unit PSA Models

27411 Simplified Methodology for Multi-Unit PSA Model

27162 Methodological Approach for a Hydrological Hazards PSA for a Multi-Unit Multi-Source Site

27152 Modeling of Personnel Suppression in Nuclear Power Plant Applications

27158 Radiative Heat Flux Zone of Influence for Open Fires and Electrical Enclosure Fires

27188 The Effect of Pressurizer Heaters on Spurious Pressurizer Main Spray Initiation, MSO 36, Scenario in a Reference Plant Fire PRA

27015 Condition-Based Probabilistic Safety Assessment for an Induced Steam Generator Tube Rupture

27097 Use of Risk Insights in the Practical Implementation of Integrated Risk-Informed Decision-Making Framework

26956 Development of 3+ Level Probabilistic Safety Assessment Methodology and Application for Akkuyu Nuclear Power Plant

26402 Discussion of Risk Aggregation in Three Dimensions for Various Risk Hazards

27063 Insights from Risk-Related Implementation of Reactor Pressure Vessel Water Inventory Control (RPV WIC)

27207 PSA Evaluation of the New Independent Feedwater System at Ringhals NPP in Sweden

26947 Power Supply and Mitigation System Considerations for Extended Loss of All AC Power Events

28205 Modeling Fire-Induced Main Control Room Abandonment in PRA Fault Trees

27043 Defining Realistic Conservatism in Nuclear Criticality Safety Analysis

27133 Criticality Safety Insights for a Nuclear Waste Process Using Hazard Analysis

27167 Estimating the Probability of Multiple Misloads in Spent Fuel Casks for Light Water Reactor Systems

8:00-9:00 am (Spouse Guests)

Spouse/Guest Breakfast (8:00-9:00am)

PSA methodologies for external hazards at nuclear power plants: Current status and future developments – Plenary (II)

Robert J. Budnitz, Lawrence National Berkeley Laboratory, (retired)

27138 Severe Accident Source Terms for Small Modular SFRs

27388 Development of a Methodology for Early Integration of Safety Analysis into Advanced Reactor Design

27198 Probabilistic Risk Assessment of a Single-Failure-Proof Crane for Small Modular Reactor Refueling Operations

26969 Once upon a time, there was a total loss of ultimate heat sink…

27023 A Study on Probabilistic Risk Assessment Methodology of External Hazard Combinations, – Identification of Hazard Combination Impacts on Air Cooling Decay Heat Removal System

26670 Risk-Reduction Credit for Very Early Warning Fire Detection: From FAQ to Fiction

27110 Incorporation of Spatial Variability of Ground Motions in a Seismic Multi-Unit Probabilistic Risk Assessment

27209 Accident Sequence Probability in PSA

27020 Modeling Hydrogen Explosion in Level 1 PSA

27009 Practical Application of the Loss of Offsite Power Recovery Analysis using the Convolution Methodology

27229 Simplified/harmonized PSA: a generic modeling framework applied to precursor analysis

27154 Model Based Reliability Analysis of Digital I&C of the Hoisting Equipment in Nuclear Facilities

26999 Development of Cyber-Attack Complexity Evaluation Model for Cyber Security of Nuclear Power Plants

27126 Use of Risk Insights in the Practical Implementation of Integrated Risk-Informed Decision-Making Framework

27056 Internal Flooding PRA Refinement by Partitioning of Pipe Rupture Frequencies

27021 Evaluation of Common Cause Failure by an Initiating Event for Multi-unit using Bayesian Belief Network

27224 Development of Inter Unit CCF Methods for Multi-Unit PSA

27120 Integrating External and Internal Event Hazard Models at Nuclear Power Plants

27192 A Preparatory Study on Systematically Considering Combinations of External Events in the Design Basis and the Probabilistic Safety Assessment of NPP Paks

27058 Lessons Learned from Recent Seismic Risk Evaluations Including Probabilistic Risk Assessments to Support Regulatory Actions

27146 A new method to allocate combination probabilities of correlated seismic failures into CCF probabilities

26664 Assessment for SRV line break

27088 General Screening Criteria for Loss of Room Cooling in PRA Modeling

27074 On Assessing the Risk Related to Consequential Steam Generator Tube Rupture Events in Nuclear Power Plants

27181 Office for Nuclear Regulation Risk Informed Regulatory Decision Making

27285 Assessing the Impact of TSTF 505 Initiative 4B Risk-Informed Completion Times on Baseline Risk

27059 Insights from Review of Seismic Probabilistic Risk Assessments in the Context of 10 CFR 50.69

26662 Risk-Deformed Regulation: What Went Wrong with NFPA 805

27044 Power restoration timescales and probabilities: new data and a general theory

27029 Low Power Shutdown PRA Modelling Challenges and Recommendations

26124 NuScale’s Emergency Planning Zone Methodology

27065  FLEX Equipment Reliability Data

8:00-9:00 am (Spouse/guest)

Spouse/guest breakfast (8:00-9:00am)

27145 State-of-the-Art Reactor Consequenece Analyses Project: Uncertainty Analyses for Station Blackout Scenarios

27164 State-of-the-Art Reactor Consequenece Analyses Project: Insights on Accident Progression and Source Term

27165 State-of-the-Art Reactor Consequenece Analyses Project: Insights on Offsite Consequences

27166 State-of-the-Art Reactor Consequenece Analyses Project: Insighs on Methodologies

Opal 1

27106 Comparative Application of Digital I&C Modeling Approaches for PSA

27241 Insights from a WGRISK Activity on the Status of Site-Level PSA Developments

27034 TMRE Implementation Experience at Duke Energy and Southern Nuclear Company Pilot Plants

27049 Incorporation of Surveillance Frequency Control Program Risk Evaluations in PRA Models

27144 A Simplified Probabalistic Model for Flywheel Integrity Using “R”

8:00-9:00 am (spouse/guest)

Spouse/Guest Breakfast (8:00-9:00am)

PSA Research and Education at Universities: History, Impact, Challenges, and Future Outlook – Plenary (V)

Professor Ali Mosleh, Moderator, (Garrick Institute for the Risk Sciences, UCLA)

Panel:

George Apostolakis (MIT Emeritus Prof.)

Mohammad Modarres (Prof. UMD)

Ali Mosleh (Prof. UCLA)

Akira Yamaguchi (Prof. Univ. of Tokyo)

Katrina Groth (Assistant Prof. UMD)

Tunc Aldemir, The Ohio State University

Wolfgang Kröger, ETH Zürich

Dr. Robert A. Bari, Chair, Brookhaven National Laboratory, Senior Physicist Emeritus, (retired)

Dr. Robert J. Budnitz, Lawrence Berkeley National Laboratory, (retired)

Dr. Robert E. Henry, Fauske and Associates, Inc. (retired)

Dr. Roger J. Mattson, Consultant

27099 Simulation Based Dynamic Event Tree Analysis

27117 Mutual Integration of Classical and Dynamic PRA

29590 Dynamic Probabilistic Risk Assessment with PyCATSHOO: The Case of the Emergency Power Supply of a Nuclear Power Plant

27260 Models for Human Performance Improvement

27062 Human Reliability Analysis Quantification Guidance for Main Control Room Abandonment Scenarios in Fire PRAs: What’s New and When Can Existing Methods Be Used?

27128 The Use of Expert Judgment to Support Human Reliability Analysis of Implementing FLEX Equipment

27081 Human Action Dependency Development in the Age of Automation

27032 Level 3 PSA Application for Akkuyu Nuclear Power Plant

27217 Ingestion Dose Evaluation in A Food Chain Model for Consequence Analysis

27129 Development and Status of the ASME/ANS RA-S-1.3 Level 3 PRA Standard

25805 A Focused Sensitivity Study on the Key Input Parameters Important to Long-Term Level 3 PSA Metrics

27037 Re-Evaluating the Current Safety Goal Policy

27125 Technical Evaluation of the Margins Between Established Risk Goals and Health Objectives for Nuclear Power Plants

27213 Application of Qualitative Importance Measures

27150 Overview of the Society of Fire Protection Engineers (SFPE) latest Engineering Guide to Fire Risk Assessments, 2nd Edition

27018 ANALYSIS OF LOSS-OF-OFFSITE-POWER EVENTS 1987-2017

27095 Pilot Application of SACADA Database for Feed and Bleed Operator Action

27013 A complex network analysis for balanced design verification

27184 A Guidance for the Scoping and the Frequency of a PRA Data Update

27109 Complex Modeling for Surveillance Test Interval Extensions

27057 Application of Electrical Power Recovery in the South Texas Project (STP) PRA Model

27077 Whole-site Risk Characterization Approaches in Canada: Regulatory and Technical Challenges

27014 Reliability analysis of a dynamic system using Petri net and comparison with Smart Component Methodology

27173 ATF: A Dynamic PRA Comparison

27169 Preliminary Methodology and Scenarios for Integrated Safety/Security Dynamic Probabilistic Risk Assessments

27016 A Dynamic Safety Margins Estimation with a Limited Number of PWR Large Break LOCA Simulations

27104 Communicating PRA Concepts to Non-Practitioners

26981 RISKAUDIT and CNEN Cooperation on Probabilistic Safety Analysis

27096 Release Category Characterization; Towards a More Realistic Method

27418 The GRS Source Term Prognosis Software FaSTPro for PWR and BWR Spent Fuel Pools

29625 SAPHIRE’s Current “State-of-Practice” to Meet PRA Demands

27156 New Functions and Features Associated with EPRI HRA Calculator Version 5.2(R)

27143 Human Reliability Dependency Analysis and Configuration Risk Management

27130 Sodium Pump Performance in the NaSCoRD Database

27191 Development of a Reliability Data Toolkit for Component Analysis in Liquid Waste Nuclear Facilities

27124 ESO-based online reliability estimation method for nuclear reactors

27079 Alternative Approach for Defining Truncation Limits

27375 Quantification of the Uncertainty Due to State-of-Knowledge Using ROAAM + Framework for Nordic BWRs

27214 An Approach to Fire Probabilistic Risk Assessment Modeling, Uncertainty Quantification and Sensitivity Analysis

27107 Understanding and Effectively Managing Conservatisms and Safety Margin

8:00-9:00am (Spouse/Guest)

Spouse/Guest Breakfast (8:00-9:00am)

27069 Organizational Factors in PRA: Twisting Knobs and Beyond

27028 HRA and Dependency Analysis Insights from a Dominion Energy Model Update Project

27228 Human Performance Modeling and Experimentation for Control Rooms

27448 An Illustrative, Interview-based Risk Framework for Treatment of High-Stress Human Actions in Multiunit Nuclear Power Plant Accidents

29876 Review of Airborne Release Fraction Used for Toxicological Free-Fall Liquid Spills Based on DOE-HDBK-3010 Requirements

30161 Estimation of the Conservatism in the Free-Fall Spill Source Term Correlation for High-Level Waste

27089 Fire-Induced Pressure Response and Failure Characterization of PCV / SCV / 3013 Containers