Daily Program

T01-10 Uncertainty and Sensitivity
A-051

A More Realistic Uncertainty Analysis Approach for the LOCA Safety Criterion

Martina KLOOS (Gesellschaft Fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany) Winfried POINTNER
A-053

Raven Facing the Problem of Assembling Multiple Models to Speed up the Uncertainty Quantification and Probabilistic Risk Assessment Analyses

Andrea ALFONSI (Idaho National Laboratory, United States) Cristian RABITI, Diego MANDELLI
A-077

Interval Characterization of Selected Epistemic Uncertainties

Chris EVERETT (Information Systems Laboratories, United States) Homayoon DEZFULI, Bob YOUNGBLOOD, Tony HALL
A-563

Optimal Sampling Placement Based on Value of Information Considering Seismic Hazard

Yosuke TASAKI (Tokyo City University, Japan) Ikumasa YOSHIDA
A-465

Online Risk Monitoring of Nuclear Power Plants: System and Its Components Ordering based on Cost Importance

Vivek AGARWAL (Idaho National Laboratory, United States) Payel CHATTERJEE, Andrei GRIBOK, Curtis SMITH
T06-01 Risk-Informed Regulation I
A-467

Risk-informed Optimization of Surveillance Test Intervals

Sami SIREN (Fortum Power and Heat, Finland) Kalle JANKALA
A-488

Development of Advanced Surveillance Requirements of Nuclear Power Plants Using Risk Information

Jose Felipe VILLANUEVA (Universitat Politecnica De Valencia, Spain) Sebastian MARTORELL, Isabel MARTON, Pablo MARTORELL, Sofia CARLOS, Ana SANCHEZ, Ruben MULLOR
A-474

Study on Risk-informed in-Service Inspection for PWR

Tamio KORIYAMA (Nuclear Regulation Authority, Japan) Haruo FUJIMOTO
A-442

Regulatory Activity Analysis for RIDM Framework Development

Dongju JANG (Korea Institute of Nuclear Safety, Korea, Republic of) Yong Suk LEE, Yongjin LEE
A-398

Recent Experiences in Risk Informed Regulation in Finland

Marko MARJAMAKI (Radiation and Nuclear Safety Authority, Finland) Matti LEHTO, Jorma SANDBERG
T07-08 Human and Organizational Factors Ⅰ (Safety/Organizational Culture)
A-528

The Organizational Value Framework – The Two Missing Legs of Future Organizational Regulatory Frameworks

Christopher JACKSON (University of California, United States)
A-389

A Management Approach for Assessing Nuclear Safety Culture Health Performance Utilizing Multiple-criteria Decision Analysis

Adrian GHEORGHE (Old Dominion University, United States) James WARREN
A-245

An Innovative Integrated Model for Safety Practitioner Practice in Organizational Context

Nicolaas VAN LOGGERENBERG (University of South Africa (Unisa), South Africa) Elrisa ESTERHUYZEN
A-244

The Role of Safety Professionals in Managing PTSD in the Workplace

Nicolaas VAN LOGGERENBERG (University of South Africa (Unisa), South Africa) Leoni LOUW
A-298

Identification and Evaluation of Zugzwang and Zeitnot Human Failure Events Based on Fukushima Daiichi Accident Context Quantification

Gueorgui PETKOV (European Commission Joint Research Centre Institute for Energy and Transport, Netherlands) Ivan PETKOV
T05-07 PSA Applications Ⅴ
A-459

Review and Update of I&C Component Reliability

Steven EIDE (Curtiss-Wright, United States)
A-382

Quantification of Application Software Failures of Digital I&C in Probabilistic Safety Analyses

Mariana JOCKENHOEVEL-BARTTFELD (AREVA GmbH, Germany) Andre TAURINES, Christian HESSLER
A-247

Identification of the Risk Induced by Cyber-Attack on the Non-safety NPP I&C System

Hee Eun KIM (Korea Advanced Institute of Science and Technology, Korea, Republic of) Han Seong SON, Jonghyun KIM, Hyun Gook KANG
T01-11 PSA Practice and Experience I
A-113

APR1400 NRC DC PRA Summary

Young Ho IN (ENERCON Services, Inc., United States) Han-gon KIM, Myung Ro KIM
A-169

Adapt the Level of Detail of the Reliability Studies for Mastering Constraints of a Nuclear Project

Herve BRUNELIERE (AREVA NP, France) Monica RATH, Cecile LE MONTAGNER, Pierre LACAILLE
A-182

Insights from the Comparison of Recent Internal Event PSA Results for Westinghouse PWRs in Korea

Gunhyo JUNG (Future & Challenge Technology Co., Ltd., Korea, Republic of) Yong Suk LEE, Kang-min PARK, Seokwon HWANG, Hojun JEON
A-577

The Insight of PRA Sensitivity Analyses for AAA Designs

Kisu KIM (KEPCO Engineering & Construction Company Inc., Korea, Republic of) Jaehoon YANG, Eunsil SONG
A-581

Insight from the Internal Flooding PRA For APR 1400 Plants

Myung Ro KIM (KEPCO Engineering & Construction Company Inc., Korea, Republic of) Dongwook KIM
A-151

Probabilistic Safety Assessment for Shutdown States of Reactors, Spent Fuel Pool and Recent R&D Results

Manorma KUMAR (Lloyd's Register Consulting, Sweden) Anders OLSSON, Horst LOEFFLER, Emmanuel RAIMOND
A-049

Thoughts on Risk Essence from PRA Practice

Hongbing JIANG (Lookout STE LLC, United States)
T06-02 Risk-Informed Regulation II
A-241

Understanding PRA from Perspectives of History, Technology, and Culture

Xiangcheng KONG (Nuclear Power Institute of China, China) Chunrui DENG
A-197

Standardized Probabilistic Safety Assessment Models: First Results and Conclusions of a Feasibility Study

Cesar QUERAL (Technical University of Madrid, Spain) Enrique MELENDEZ, Miguel SANCHEZ, Carlos PARIS, Julio MULA, Andres HERNANDEZ
A-523

Approaches of Risk Measures Minimization and Application to Inspection

Robertas ALZBUTAS (Lithuanian Energy Institute, Lithuania)
A-433

Strategy of AESJ for PRA Standards Development and Maintenance

Yoshiyuki NARUMIYA (Kansai Electric Power Company, Inc., Japan) Akira YAMAGUCHI, Haruhiro NOMURA
A-080

Technical Specification Surveillance Requirement Frequency Improvements in Nuclear Power Plants via Risk-informed Initiative-5b Approach

Luyen NGUYEN (Westinghouse Electric Corporation, United States) John KITZMILLER
T07-09 Human Reliability Ⅷ (New HRA Method)
A-531

A Task Library for Petroleum Applications in Human Reliability Analysis

Ronald BORING (Idaho National Laboratory, United States) Ronald FARRIS, Kateryna SAVCHENKO
A-296

Petro-HRA, a New Method for Human Reliability Analysis in the Petroleum Industry

Andreas BYE (OECD Halden Reactor Project - Institute For Energy Technology, Norway) Karin LAUMANN, Claire TAYLOR, Martin RASMUSSEN, Sondre OIE, Koen VAN DE MERWE, Knut OIEN, Ronald BORING, Nicola PALTRINIERI, Irene WAEROE, Salvatore MASSAIU, Kristian GOULD
A-240

Human Reliability Analysis of an Oil Refinery Operation Using the Phoenix HRA Methodology: A Hydrogen Generation Unit Case Study

Marilia RAMOS (Federal University of Pernambuco, Brazil) Enrique DROGUETT, Ali MOSLEH
A-362

Preliminary Insights regarding Human Reliability Analysis of New Research Reactors from the PSA Study Performed in the Framework of IAEA-led Competence Building Project

Ali ABU SHQAIR (Jordan Atomic Energy Commission, Jordan) Alaaddin ALNAJJAR, Firas AHMED, Khalifeh ABU SALEEM
T05-08 PSA Applications- Advanced/Research Reactor
A-600

PRA on Mixing with Foreign Substances into Core of Japanese Prototype FBR

Masahiro NISHIMURA (Japan Atomic Energy Agency, Japan) Yoshitaka FUKANO, Kenichi KURISAKA, Kenich NARUTO
A-379

Development of Level 1 Probabilistic Safety Assessment for Jordan Research and Training Reactor (JRTR) in the Framework of IAEA-led Competence Building Project

Alaaddin ALNAJJAR (Jordan Atomic Energy Commission, Jordan) Ali ABUSHQAIR, Firas AHMED, Alaa ALDAHYYAT, Khalifeh ABU SALEEM
A-102

Risk-informed Comparative Study of I&C Architectures for Research Reactors

Kyungho JIN (Kyung Hee University, Korea, Republic of) Rahman KHALIL UR, Gyunyoung HEO
A-220

Impact of Internal Inspection Data Uncertainties on Risk Analysis for Design Life Extension of Subsea Pipeline – A Case Study

Andrea MANCINI (Auriga Consulting S.P.A, Italy) Stefania BENUCCI
T01-12 Advanced Nuclear System
A-337

Evaluation of Safety Improvement by Hybrid Heat Pipe/Control Rod using Level 1 PSA

Seok Bin SEO (Ulsan National Institute of Science and Technology, Korea, Republic of) In Cheol BANG
A-344
Advanced Reactor Passive System Reliability Demonstration Analysis for an External EventMatthew BUCKNOR (Argonne National Laboratory, United States) David GRABASKAS, Acacia BRUNETT, Austin GRELLE
A-601

A Study on the Off-Site Consequence Analysis for a VHTR

Joeun LEE (Hanyang University, Korea, Republic of) Moosung JAE, Jintae KIM
A-374

A Methodology for Spent Fuel Pool Internal Events Level 1 and Level 2 PRA for APR1400

Taehee HWANG (KEPCO Engineering & Construction Company Inc., Korea, Republic of) Inn Seock KIM, Jaegab KIM
T06-03 Risk-Informed Regulation III
A-098

Are Floodings Preventable Under Moral Hazard and Limited Liability?

Oscar NIETO-CEREZO (The University of Liverpool, United Kingdom) Edoardo PATELLI, Jan WENZELBURGER, Michael BEER
A-605

Development of ASP Methodology and Its Application to the Significant Accident Precursors

Sunghyun PARK (Hanyang University, Korea, Republic of) Seunghyun JANG, Moosung JAE
A-553

Review of PRA in Regulated Power Reactor Applications

David JOHNSON (ABS Consulting, Inc., United States) Ernie KEE
A-300

Exploring the Development and Use of Municipal Risk and Vulnerability Assessments in Sweden-Challenges and Opportunities

Lexin LIN (Lund University, Sweden) Kerstin ERIKSSON
T07-10 Human and Organizational Factors Ⅱ (Procedure and Education)
A-592

User Interface and Interaction for Procedure Execution to Reduce Human Error

Yeonsub JUNG (Korea Hydro & Nuclear Power Co. Ltd., Central Research Institute, Korea, Republic of)
A-208

Operators' Autonomous Decisions during Emergency: Do They Promote or Reduce Safety?

Salvatore MASSAIU (OECD Halden Reactor Project - Institute for Energy Technology, Norway)
A-261

Use of Operational Data for Reducing Consequential Events at Nuclear Power Plants

Pamela NELSON (Universidad Nacional Autonoma de Mexico, Mexico) Teresa RUIZ-SANCHEZ, Michael BOLDRICK, Adrian MEZA, Cecila MARTIN-DEL-CAMPO
A-619

Simulation-based Learning: Comparative Review between Maritime Simulation and Other Domains

Eirik HOMLONG (Norwegian University of Science and Technology, Norway) Lillian VEDERHUS, Yushan PAN, Hans Petter HILDRE
A-490

The Grassroots of Strategically Preparing Specialists for Subsea Operations: Using a Simulator as a Tool

Eirik HOMLONG (Norwegian University of Science and Technology, Norway) Yushan PAN, Lillian VEDERHUS, Hans Petter HILDRE
T05-09 PSA Applications - Level 2
A-035

A Probabilistic Approach for Source Term Prediction in Case of Severe Accidents

Michael HAGE (Gesellschaft Fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany) Horst LOEFFLER
A-168
Internal Flooding Level 2 PSA in BelgiumShizhen YU (Tractebel ENGIE, Belgium) Philippe DEJARDIN
A-306

Estimating Loss-of-coolant Accident (LOCA) Frequencies via Spatio-temporal Methodology

Nicholas O'SHEA (University of Illinois at Urbana-Champaign, United States) Zahra MOHAGHEGH, Seyed A. REIHANI, Ernie KEE