• Development of Applications Guidance Document for MAAP4 Accident Analysis Code
  Barbara J. Schlenger-Faber, ERIN Engineering and Research, Inc.
• Development of PRA Level 2 Guidelines
  Ricky Summitt, Ricky Summitt Consulting, Inc.
• Interface Between MAAP and MACCS2 Required to Develop a Level 3 PRA
  Stanley H. Levinson, et al.,, AREVA NP Inc.
  

• L2 PSA: A Dynamic Event Tree Approach to Validate PWR Severe Accident Management Guidelines
  E. Raimond IRSN, France
• Technical Issues in Demonstrating Compliance with Quantitative LERF/LRF Targets
  Mark T Leonard, dycoda, LLC
• Level 2 PSA for the Mochovce NPP
  Zoltan Kovacs, et al., RELKO Ltd, Engineering and Consulting Services, Slovak Republic
  

• Level 3 PSA Use and Development in the United Kingdom
  Antony P Bexon, Health Protection Agency (UK)
• Modeling Post-Core Damage Operator Actions in the PRA
  Robert J Lutz, et al., Westinghouse
• Evaluation of Technical Issues during the Development of Shutdown Severe Accident Management Guidelines for a BWR/4 Mark I
  Mark T Leonard, et al., dycoda, LLC
• Implementation of a Concept for a Risk-Informed Diagnosis and Prognosis of Plant States Through the RISARD System
  Kwang-Il Ahn, et al., ,Korea Atomic Energy Research Institute
  

• Analytical Calculation of the Mean Value of a Top Event
  Tsong-Lun Chu, et al., BNL
• Optimization Study of Filtered Vent and Drywell Flooding for a BWR/4 Mark I
  Mark T Leonard, et al., dycoda, LLC
• LEVEL 2 Probabilistic Risk Assessment for WWER-1000 of the small series Results of the Trilateral –United States-Federal Republic of Germany-Ukraine Program
  Rolf Janke, et al., Gesellschaft für Anlagen- und Reaktorsicherheit mbH
  

• A Methodology for the Conceptual Design of Advanced Nuclear Systems Using Risk-Informed Decision Making
  Michael A Elliott, et al., Massachusetts Institute of Technology
• Integration of the Advanced Transparency Framework to Advanced Nuclear Systems Enhancing Safety, Operations, Security, and Safeguards (SOSS)
  Virginia D Cleary, et al., Sandia National Laboratories
• Application of PSA in support to the design of CEA 2400 MWth Gas-cooled Fast Reactor
  Christophe Bassi, CEA (Atomic Energy Commission), France
• Metal Fires and Their Implications for Advanced Reactors
  Tara J Olivier, et al., Sandia National Laboratories
  

• Practical Issues in Component Aging Analysis
  Dana L Kelly, Idaho National Laboratory
• Investigation of Time-Dependent Trends in Failure Data of Active Component
  Jens-Uwe Kluegel, NPP Goesgen, Switzerland
• PSA as a Tool for Evaluation of Ageing Effects on The Safety of NPPs
  Andrei Rodionov, EC JRC Institute for Energy, Netherlands
  

• Methodology for Selecting SSC gor Time-Dependent Reliability Modelling in PSA
  Alexander V Trifanov, Canadian Nuclear Safety Commission
• Component selection for Ageing PSA of Armenian NPP Unit 2
  Shahen V Poghosyan, et al., Nuclear and Radiation Safety Center (NRSC)
  

• Point Lepreau Refurbishment Project Level 2 PSA results for internal and external events
  Liliana Comanescu, Atomic Energy Canada Limited
• A Proposed Method for Plant Availability and Initiating Event Frequency Modeling
  Ernie J Kee ,STP Nuclear Operating Company
• Switchyard Work Effect on Risk
  Steven E Farkas, et al., Westinghouse Electric Co.
  

Common Cause Failures II
Thursday, 8:30 AM, Sequoyah 3
Session Chair: Ricky Summitt

• Common-Cause Failure Analysis in Event Assessment
  Dana L Kelly, Idaho National Laboratory
• Some Component Insights from Analyzing NRC's Common-Cause Failure Database
  Dale M. Rasmuson, US Nuclear Regulatory Commission
• Investigation of Inter-System Common Cause Failures
  Paula Calle Vives, et al., EDF R&D, France
• Treatment of Common Cause Failure in Support System Initiator Models
  Rupert Weston, Westinghouse Electric Company LLC
  

• The Development and Use of CCF Data at European and US Boiling Water Reactors
  Leo B. Shanley, ERIN Engineering and Research, Inc.
• Modeling And Parameter Estimation of Asymmetrical Common Cause Failure Events
  Dae Il Kang, Korea Atomic Energy Research Institute(KAERI)
• Quantitative Expert Judgement and Model Assumption Violations
  Tim Bedford, et al., University of Strathclyde, UK
• The Effects of Using Unscreened Independent Events on Plant Specific Common Cause Failure Probabilities
  Young G. Jo, Southern Nuclear Operating Company
  

• Adjoint Markov Chains for Sensitivity Analysis of Dynamic Reliability Models
  Dan G Cacuci, Commissariat a l’Energie Atomique, France
• A Method for Estimation of Cutset Truncation Error in PSA based on Cutset Growth Trend
  Manuel González-Cuesta, Universidad Nacional Autónoma de México
• Advanced PRA Modeling and Quantification
  Jeff Riley, et al., EPRI
  

• An Approach to Deal with Truncation Error and Logical Loops
  Jongsoo Choi, Korea Institute of Nuclear Safety
• The Open PSA Initiative for Next Generation Probabilistic Safety Assessment
  Steven A Epstein, et al., ABS Consulting, Japan
• FTREX Features for an Efficient PSA
  Woo Sik Jung, et al., Korea Atomic Energy Research Institute
  

• Configuration Risk Management of External Event Risk Using PARAGON™
  Edward F. Parsley, ERIN Engineering and Research, Inc.
• Modeling the Impact of Switchyard Line Failures and Outages in the SONGS Safety Monitor
  Parviz Moieni, et al., Southern California Edison
• Nuclear Industry Configuration Risk Management: Insights from Current Research
  Thomas A Morgan, et al., Maracor Software & Engineering, Inc.
  

• Addressing Selected Digital I&C Technical & Licensing Issues using Risk Informed Methods
  David P Blanchard, Applied Reliability Engineering, Inc.
• Development of Guidance for the Review of New Reactor Digital Instrumentation and Control Probabilistic Risk Assessments
  Steven A Arndt, et al., U.S. Nuclear Regulatory Commission
• An Automated Tool for Supporting FMEAs of Digital Systems
  Tsong-Lun Chu, et al., Brookhaven National Laboratory
  

• Insights Gained from the Beznau Seismic PSA Including Level 2 Considerations
  Martin Richner, et al., NOK, Beznau NPP, Switzerland
• Study on Seismic PSA method for Multi-Unit Site Cycle Operatioon
  Tadakuni Hakata, TH Consulting
• OECD/NEA Task on PSA of Other Off-site External Events than Earthquake
  Jorma V Sandberg, et al., STUK-Radiation and Nuclear Safety Authority, Finland
  

• Safety Goals for Seismic Safety: Lessons Learned from The Chûetsuoki Earthquake
  Genn Saji, Ex-Secretariat of Nuclear Safety Commission of Japan
• Lessons Learned at Kashiwazaki-Kariwa NPP Attacked by the Strong Earthquake on July 16, 2007
  Harukuni Tanaka, TEPCO
• Comparative Study of Seismic PSA Methods and Sensitivity of Correlation
  Tadakuni Hakata, et al., TH Consulting
  

• Lessons Learned Developing a Fire PRA for an NFPA-80 Pilot Application
  David Miskiewicz Progress Energy, Inc.
• Applications of Fire PRA in NFPA 805 Frequently-Asked-Questions Program
  J.S. Hyslop, et al., Nuclear Regulatory Commission
• Use Of EPRI/NRC-RESs Fire Pra Methodology (EPRI 1011989, NUREG/CR-6850) for Fire Pra at Nuclear Power Facilities other than Current U.S. LWRS
  Bijan Najafi, SAIC
• Iterative Process to Fire PRA Development
  Kiang L. Zee, ERIN Engineering and Research, Inc.
  

• Risk-Informed Analysis of Fire-Induced Multiple Spurious Operation
  Dennis W Henneke, GE Hitachi
• Actual Developments in the Advanced German Fire PSA Methodology
  Marina L. Roewekamp, GRS mbH
• Modifications to a PRA Model to Address Multiple Spurious Operations (MSOs)
  Richard C. Anoba, et al., Anoba Consulting Services, LLC
• Fire Scenario Sensitivity Case Studies for Risk-Managed Technical Specifications Implementation
  James K Liming, et al., ABSG Consulting Inc.
  

• Scoping Fire Modeling for Defining the Zone of Influence for Fire PRA Analysis
  Usama Farradj, ERIN Engineering and Research, Inc.
• Insights from Evaluations of Control Room Abandonment Fire PRA Analyses
  Usama Farradj, ERIN Engineering and Research, Inc.
• Development and Pilot Application of the ANS Fire PRA Standard
  Dennis W Henneke, GE Hitachi
• Data Management for Fire Frequency and Fire Modeling Tasks in a Fire PRA
  Francisco Joglar, Mark Graham, SAIC
  

• Use of FRANC and XINITS - Practical Aspects, Lessons Learned, and Performance Insights
  Gregory T. Zucal ,ERIN Engineering and Research, Inc.
• FRANX Code for Fire PRA Analysis
  Jeff Riley, et al., EPRI
• Insights from ESBWR Fire PRA Model Development for Design Certification
  Yunlong Li, GE Hitachi Nuclear Energy
  

• Documentation of the Fire PRA using EPRI's DocAssist
  Edward A. Simbles, ERIN Engineering and Research, Inc.
• Focusing The Circuit Analysis Effort in Transitioning to NFPA 805 Using Top Event Prevention (TEP)
  David P Blanchard, Applied Reliability Engineering, Inc.
• Fire Risk Analysis of NPP "KOZLODUY" Units 3&4
  Vesselina Vladimirova, et al., Risk Engineering
  

• Addressing Uncertainty in Detailed Fire Modeling of Nuclear Power Plant Single Compartment Fire Scenarios Using Latin Hypercube Sampling
  Tom Elicson, Polestar Applied Technology
• Considerations for Improving Fire PRA Treatment of High Energy Arcing Faults
  J.S. Hyslop, et al., Nuclear Regulatory Commission
• The Cable Response to Live Fire (CAROLFIRE) Project: Advancing the Cable Fire Response Knowledge Base
  Steven P Nowlen, et al., Sandia National Laboratories
• A Phenomena Identification and Ranking Table (PIRT) Exercise for Nuclear Power Plant Fire Model Applications
  Steven P Nowlen, et al., Sandia National Laboratories
  

• Probabilistic/Statistical Examination of Cable Hot Short Durations Due to Nuclear Plant Fires
  Raymond H Gallucci, U.S. Nuclear Regulatory Commission
• Development of an Automated Fast Fire PSA Method
  Woo Sik Jung, et al., Korea Atomic Energy Research Institute
• Multi-Point Fire Analysis and Simplified Fire Modeling for Fire Risk Quantification
  Clarence L Worrell, et al., Westinghouse Electric Company
  

Human Reliability Analysis II
Monday, 2:00 PM, Salon A/B
Session Chair: Kevin Coyne

• Simplified HRA Process for Internal Fire Analyses
  Don E. Macleod, ERIN Engineering and Research, Inc.
• Modeling Nuclear Plant Operator Knowledge and Actions – The ADS-IDAC Simulation Approach
  Kevin Coyne, et al., University of Maryland
• EPRI/NRC Fire Human Reliability Analysis Guidelines
  Susan E. Cooper, et al., US Nuclear Regulatory Commission
  

• A Feasibility Study for Development of Human Error Pattern Analysis Methodology for Operational Experience Feedback
  I.S. Kim, et al., ISSA Technology, Inc.
• Benchmarking ASEP and THERP Against Simulated Scenarios
  Y. James Chang, et al., US Nuclear Regulatory Commission
• Severe Accident Mitigation Alternative Analysis Insights Using the MACCS2 Code
  Kevin R O'Kula, Washington Safety Management Solutions
  

• Human Reliability Analysis for EPR NPP PSA Level 2
  Estelle Sauvage, AREVA-NP
• Data-Driven Modeling of Dependencies Among Influencing Factors In Human-Machine Interactions
  Katrina M Groth, et al., University of Maryland
• Modeling and Estimation of Common Cause Failure Like Pre-Initiator Human Failure Events Using Experience Data
  Young G. Jo, Southern Nuclear Operating Company
  

• ATHEANA HRA Analysis in the 2007 International HRA Empirical Study (WT)
  Dennis C. Bley, Buttonwood Consulting, Inc.
• Human Reliability Analysis Within Probabilistic Safety Assessment for Other Modes Than Power Operation
  Marko Cepin, Josef Stefan Institute, Slovenia
• R.E. GINNA Nuclear Power Plant Pre-Initiator Human Reliability Analysis Upgrade to Meet ASME Standard Requirements
  Eric Jorgenson, Stephen Kimbrough Maracor Software and Engineering
• Automated Human Reliability Dependency Analysis Using the EPRI HRA Calculator®
  Jan Grobbelaar, et al., Scientech, Inc.
  

• HRA methods: Pros and Cons
  Anthony J Spurgin, Consultant
• Human Reliability – WGRisk Findings and Outlook for Data Collection and Exchange
  Vinh N Dang (Presenter Nathan Siu), et al., Paul Scherrer Institut (PSI), Switzerland
• Use of HERA to Inform Human Reliability Analysis
  Y. James Chang, et al., US Nuclear Regulatory Commission
  

Human Reliability Analysis VII
Wednesday, 10:15 AM, Sequoyah 3
Session Chair: Andreas Bye

• The International Empirical HRA Study Using Simulator Human Performance Data
  Erasmia Lois (presenter Gareth Parry), et al., US Nuclear Regulatory Commission
• Overall Design of the International Empirical HRA Method Study
  Jeff Julius, et al., US Nuclear Regulatory Commission
• Experimental Design Needs for Empirical Studies of HRA Methods
  Andreas Bye, et al., US Nuclear Regulatory Commission
• How Well Do HRA Methods Predict Crew Performance? Results from a Pilot Study
  Gareth Parry, et al., US Nuclear Regulatory Commission
  

Lessons Learned I
Wednesday, 4:00 PM, Salon C
Session Chair: Doug Hance

• Experiences with Piping Reliability Analysis in Support of Risk-Informed PSA Applications
  Bengt Lydell ,SCANDPOWER Risk Management, Inc.
• Managing Change - PRA Rollout at Dresden Nuclear Station
  John E. Steinmetz, ERIN Engineering and Research, Inc.
• International Review of the Use and Development of PSA
  Jeanne-Marie Lanore, et al., IRSN
• Assessment of NPP Operational Events Importance for Operational Experience Feedback by Means of PSA
  Vesselina Ranguelova, et al., Institute for Energy, Joint Research Centre, European Commission
  

• Shutdown PSA for Ringhals Nuclear Power Plants 2, 3 and 4. Insights, Overview and Results
  Cilla M Persson, Ringhals AB, Sweden
• Proposed Methodology, Basic and Standard for Shutdown Qualitative Risk Assessments
  Leo B. Shanley ERIN Engineering and Research, Inc.
• Experiences and Challenges for Performing Shutdown Risk Assessment at St. Lucie Nuclear Plant
  Mahmoud Heiba, Florida Power and Light
  

• An Estimtion of the Core Damage Frequency of an OPR- 1000 During a Refueling Outage
  Jinhee Park, et al., Korea Atomic Energy Research Institute
• Accident Management and Risk Evaluation of Shutdown Modes at Beznau NPP
  Martin Richner, et al., NOK, Beznau NPP, Switzerland
  

• Feasibility Study Regarding the Technical Acceptability of PRAs for Future Reactors
  Mary T Drouin US NRC
• Evaluation of Equipment Reliability During Loss of Room Cooling (LRC) for Probabilistic Risk Assessment (PRA) Purposes
  Kent E. Sutton, et al., Nebraska Public Power District (Presenter Stephen Nelson)
• The NRC's SPAR Models: Current Status, Future Development, and Modeling Issues
  Peter L Appignani, et al., US Nuclear Regulatory Commission
  

• Mitigating Systems Performance Index Impacts on PSA and Utility Operations
  Bradley W. Dolan ERIN Engineering and Research, Inc.
• MSPI Margin Improvements Arising from the use of Option 2 and System Segmentation
  Robert P Boyer, et al., Duke Energy
• Risk Assessment Standardization Project (RASP) Handbook for Risk Assessment of Operational Events
  See Meng Wong, et al., U.S. Nuclear Regulatory Commission
  

• Comparison of New Light-Water Reactor Risk Profiles
  Donald A Dube, U.S. Nuclear Regulatory Commission
• Probabilistic Risk Assessment Requirements for New Light Water Reactors
  Hanh K. Phan, et al., U.S. NRC
• Risk-Informed Framework for Revising the Need for Emergency Planning around NPP: Application to IRIS
  Andrea Maioli ,Westinghouse Electric
  

• Risk Analysis of Practical Model Facility for MOX Fuel Fabrication
  Hitoshi Tamaki, et al., Japan Atomic Energy Agency
• Current Status of the Component Failure Rates Estimation Work Based on Reprocessing Plant Maintenance Data
  Michihiko Ishida, et al., Tokai Reprocessing Technology Development Center, JAEA
• Quantitative Analysis in Response to Regulatory Reaction from a Process Upset Condition
  Ron Green, BWX Technologies
• Development of PSA Procedure for a Reprocessing Plant
  Yoshinori Ueda, et al., Japan Nuclear Energy Safety Organization
  

• Parametric Sensitivity Study of Flooding Scenarios and Their Contribution to Core Damage Frequency
  Robert J. Wolfgang, ERIN Engineering and Research, Inc.
• Using PRA to Reduce Internal Flooding Risk at the Kewaunee Power Station
  Edward D Coen, Dominion Resources Services
• Insights from the Updates of Internal Flooding PRAs
  James C. Lin, ABSG Consulting Inc.
• The Impact of Data on ISLOCA Frequencies When Using Correlated Failure Rates
  Russell Sharpe, et al., Maracor Software and Engineering
  

• PRA Model for Blind Feeding a Steam Generator
  Barbara R Baron, Westinghouse Electric Company LLC
• Estimation of The Probability of Hydrogen Transfer Line Rupture at The High Flux Isotope Reactor Cold Neutron Source
  Charles T Ramsey, Oak Ridge National Laboratory
• Evaluation of Loss-of-Coolant Accident Frequency Distributions for Standardized Plant Analysis Risk Models
  S. A. Eide, Idaho National Laboratory
  

• Application of a Probability-Based ISLOCA Methodology
  Jeffrey D. Miller, Ricky Summitt Consulting, Inc.
• Development of Plant-Specific Best Estimate Piping Failure Probability
  Terry J Herrmann, et al., Structural Integrity Associates
• Detailed Study of Emergency Diesel Generator Performance Using EPIX/RADS Database
  S. A. Eide, Idaho National Laboratory
  

• A Hierarchical Bayesian Approach to Passive System Reliability Analysis
  Bobby D Middleton, Sandia National Laboratories
• Probabilistic Risk Assessment Requirements for Passive Safety Systems
  Eric A Thornsbury, et al., ERIN Engineering & Research, Inc.
• The Use of Response Surface Methodology to Perform Uncertainty Analyses of Passive Safety Systems
  Christopher J Fong, MIT
  

• Simplified Methodology Estimating Impact on Risk Due to Sources of Uncertainty
  Robert J. Wolfgang, ERIN Engineering and Research, Inc.
• Treatment of Parameter and Model Uncertainty for Internal Events PRAs
  Ken Canavan, ERIN Engineering and Research, Inc.
• Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making
  Mary T Drouin, US NRC
• Use of the SM-UNCERT Program for Uncertainty Analysis at San Onofre
  Thomas A Morgan, et al., Maracor Software & Engineering, Inc.
  

• EPRI Education of Risk Professionals
  Douglas C Hance, EPRI
• PRA Documentation Assistant
  Jeff Riley, et al., EPRI
• PRA Computer-based Training Tools
  Pamela F Nelson, et al., Universidad Nacional Autónoma de México
  

• Implementation of a Risk-Informed Surveillance Frequency Control Program - A PRA Perspective
  Philip Tarpinian, Exelon Nuclear
• Fostering a Risk-Informed Environment in Nuclear Reactor Regulation
  Theresa Valentine Clark, et.al, U.S. Nuclear Regulatory Commission
• Development and Application of RI-ISI Methodology at Olkiluoto BWR
  Risto Himanen (presented by Pekka T Pyy), et al., Teollisuuden Voima Oy, Finland
• Use of Level 2 Results to Refine LERF for SONGS ILRT Extension
  Ricky Summitt, Ricky Summitt Consulting, Inc.
  

• Degradation Monitoring for Living PSA Applications
  Bulent Alpay, University of Michigan
• Risk-Informed Technical Spefications at the South Texas Project
  Ernie J Kee, STP Nuclear Operating Company
• EPR Risk-Informed Activities at IRSN
  Gabriel Georgescu, et al., IRSN, France
• Risk-Informed Optimization of Allowed Outage Times at Loviisa NPP
  S.P. Sirén, Fortum Nuclear Services Ltd., Finland
  

• Development and use of Level 1 PSA at IRSN
  François Corenwinder, IRSN, France
• An Approach for Integrated Safety Performance Assessment (ISPA) for Graded Regulation
  Dae-Wook Chung, Korea Institute of Nuclear Safety
• Method on Selection of Frequency-Consequence Criteria in Risk Assessment
  Kju-Myeng Oh, et al., Korea Institute of Nucelar Safety
• Risk-Informed Methodology for Establishment of Surveillance Frequencies for Nuclear Power Plants
  Srinivasa Visweswaran, et al., GE Hitachi Nuclear Energy
  

• Allocation of Scarce Resources in the Current Nuclear Safety Paradigm
  Wayne L Andrews, Perot Systems, Government Services
• Probabilistic Benefits of Water Managements Strategies for GSI 191
  Heather L Detar, Westinghouse
• Feasibility Study Regarding Probabilistic Approach for Licensing of Advanced Reactors
  Mary T Drouin, US NRC
• Risk-Informed, Technology-Neutral Design & Licensing Framework for New Nuclear Plants
  Jim Chapman, et al., Scientech
  

• PSA Information System for Regulatory Use
  Matjaz Podjavorsek, Slovenian Nuclear Safety Administration
• Evaluation of Olkiluoto BWR TechSpecs by Using Plant Specific PSA
  Risto Himanen (presented by Pekka T Pyy), et al., Teollisuuden Voima Oy, Finland
• Use of PSA Insights to Optimise STI Of EPR Safety Functions
  Vincent Sorel, et al., EDF-DIN-SEPTEN
  

Roundtable Discussion:  Lessons Learned in Training Plant Staff to be Risk-Informed, Not Risk-Misinformed
Wednesday, 8:30 AM, Sequoyah 3
Leader: Barry Sloane

• Theoretical Foundations for Building Organizational Safety Models for PRA Applications
  Zahra Mohaghegh, et al., University of Maryland
• Nuclear Power: Too Much Safety to Provide Security?
  William Mullins, Better Choice Consulting
  

• Duke Energy Experience Upgrading PRAs to Meet the Standards
  Robert Boyer, Duncan Brewer Duke Energy
• Results & Insights from the Dominion Fleet-wide R.G. 1.200 PRA Self-Assessments
  Allen C. Moldenhauer, et al., Dominion Resources
• PRA Peer Review Experiences in Korea
  Hak Kyu Lim, Korea Power Engineering Company
• An Approach for Determining the Technical Adequacy of PRA Results for Risk-Informed Activities - Revision 2 to RG 1.200
  Mary T Drouin, US NRC
• Duke Energy Experience Using the PSA Standards to Support Applications
  Stephen L. Nader, Duncan Brewer Duke Energy
  

• Probabilistic Treatment of Expert Judgment on Aleatory and Epsitemic Uncertanties Associated with On-Board Vehicle Hydrogen Storage Systems
  Yehia F. Khalil, et al., United Technologies Research Center (UTRC)
• Structuring a Probabilistic Model for Reliability Evaluation of Pipings Subject to Corrosion-Fatigue Degradation
  Mohamed Chookah, et al., University of Maryland - College Park
• Non-Proliferation Impact Assessment for GNEP: Transportation Issues
  Ross F Radel, et al., Sandia National LaboratoriesLaunch Accident Safety Analysis Code for Radioisotope Power Systems
  Tracy E Radel, et al., Sandia National Laboratories
  

Transportation and Hydrogen II
Thursday, 10:15 AM, Salon CSalon C
Session Chair: Nathan Siu

• Probabilistic Safety Assessment of Submarine Reactor
  Robert Bryant, Rolls-Royce plc, UK
• Launch Accident Safety Analysis Code for Radioisotope Power Systems
  Tracy E Radel, et al., Sandia National Laboratories
  

Use of PSA in Design
Wednesday, 10:15 AM, Salon D/E
Session Chair: Jim Chapman

• ABWR PRA Update for South Texas Project Units 3 & 4 COLA
  Dennis W Henneke, GE Hitachi
• Applicability of ASME Standard Requirements to a Design Certification PRA
  Yunlong Li, GE Hitachi Nuclear Energy
• Back to Basics – Use of Safety and Reliability Engineering Principles for Risk-Informed Decisions to Enhance Safety of First-Of-A-Kind Reactor Designs
  Kamal El-Sheikh, Reliability & Safety Assurance Consulting Services (RSACS)
• RFA Effects on Special Treatment Selection
  Donald J Spellman, et al., (Presenter J.K. August) Oak Ridge National Laboratory
  
  
  Revised August 24, 2008

PSA 2008 Topical Meeting - September 7-11, 2008 - Hilton Knoxville, TN