Human Reliability HUMAN RELIABILITY HUMAN ERROR

Slides:



Advertisements
Similar presentations
Conceptual Graph Analysis Chapter 20 Lori Nuth | EDIT 730 | Fall 2005.
Advertisements

Action 1: Mission/task analysis Action 2: List Hazards Action 3: List Causes STEP 1 IDENTIFY THE HAZARD STEP 2 ASSESS THE RISK Action 1: Assess hazard.
Project management Project manager must;
NCSR “DEMOKRITOS” Institute of Nuclear Technology and Radiation Protection NATIONAL TECHNICAL UNIVERSITY OF ATHENS School of Chemical Engineering Fuzzy.
RISK INFORMED APPROACHES FOR PLANT LIFE MANAGEMENT: REGULATORY AND INDUSTRY PERSPECTIVES Björn Wahlström.
Modeling Human Reasoning About Meta-Information Presented By: Scott Langevin Jingsong Wang.
Mr. R. R. Diwanji Techniques for Safety Improvements.
IS550: Software requirements engineering Dr. Azeddine Chikh 4. Validation and management.
Title slide PIPELINE QRA SEMINAR. PIPELINE RISK ASSESSMENT INTRODUCTION TO HAZID 2.
Managing Project Risk.
Protection Against Occupational Exposure
Presented by Dorian S. Conger Conger-Elsea, Inc Riveredge Parkway, Suite 740 Atlanta, GA phone fax
Human Reliability Assessment
Safety Management System Performance Based on Organizational Factors of “Seveso” sites Papadakis Georgios A., Kokkinos Konstantinos G. & Machaira Paschalia.
IRSC 2009 Båstad Learning from failure: Research initiatives towards improving safety and reliability of the Swedish railway system Alexander Wilhelmsson.
PMI Knowledge Areas Risk Management.
Risk Management - the process of identifying and controlling hazards to protect the force.  It’s five steps represent a logical thought process from.
Guidance Notes on the Investigation of Marine Incidents
IRSN STRATEGY TO ASSESS A NEW MAINTENANCE POLICY / Nesebar, Bulgaria Presented by Naoëlle MATAHRI, IRSN.
HUMAN EROR. Is it really human error? This is the first question that tends to be posed in light of a critical situation gone wrong, and the answer tends.
1 Human Performance in Reactor Safety George E. Apostolakis Massachusetts Institute of Technology Presented at the Quality Colloquium,
Development of Indicators for Integrated System Validation Leena Norros & Maaria Nuutinen & Paula Savioja VTT Industrial Systems: Work, Organisation and.
Intent Specification Intent Specification is used in SpecTRM
David Baglee Dr. David Baglee. School of Computing & Technology E: T: Reliability Centred Maintenance.
FAULT TREE ANALYSIS (FTA). QUANTITATIVE RISK ANALYSIS Some of the commonly used quantitative risk assessment methods are; 1.Fault tree analysis (FTA)
Margin Management. PAGE 2 Margin Management Plant Shutdowns 1.Late 1990’s – numerous “surprise” long-term plant shutdowns 2.Shutdowns resulted when a.
CHAPTER 1 Understanding RESEARCH
9 th Workshop on European Collaboration for Higher Education and Research in Nuclear Engineering & Radiological Protection Salamanca, Spain 5-7 June 2013.
11th International Symposium Loss Prevention 2004 Prague Ľudovít JELEMENSKÝ Department of Chemical and Biochemical Engineering, STU BRATISLAVA, SLOVAKIA.
STRATEGIC ENVIRONMENTAL ASSESSMENT METHODOLOGY AND TECHNIQUES.
JOB EVALUATION MAGNETIC CONTACTORS.
Human Error and Biases. Human Error - Definition  An inappropriate or undesirable human decision or behavior that reduces, or has the potential for reducing,
Nov.19, 2004 Jon Stuart, Ph. D Task Analysis: A Foundation for Safety.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
A Guide for Management. Overview Benefits of entity-level controls Nature of entity-level controls Types of entity-level controls, control objectives,
Quality control & Statistics. Definition: it is the science of gathering, analyzing, interpreting and representing data. Example: introduction a new test.
April 29th, Chapter 6 Decision Making 6.1 The Nature of Management decisions 6.1 The Nature of Management decisions 6.2The decision making process.
Introduction to Project Management Chapter 9 Managing Project Risk
Elementary School Administration and Management GADS 671 Section 55 and 56.
Diablo Canyon NPP Risk-Informed In-service Inspection
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making System Analysis Workshop Information IAEA Workshop City, Country XX - XX Month,
Risk-informed On-Line Maintenance at Cofrentes NPP IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Defence in Depth Safety Culture Lecturer.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Common Cause Failure Analysis Workshop Information IAEA Workshop City, Country.
Erman Taşkın. Information security aspects of business continuity management Objective: To counteract interruptions to business activities and to protect.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Temelin NPP Risk Panel A PSA and Safety Monitor Application Workshop Information.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Probabilistic Risk Assessment Program Workshop Information.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Overview of Risk Informed Inspection Workshop Information IAEA Workshop City,
Software Engineering, COMP201 Slide 1 Software Requirements BY M D ACHARYA Dept of Computer Science.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Proposed Fire Risk Meter Workshop Information IAEA Workshop.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making PSA Quantification. Analysis of Results Workshop Information IAEA Workshop.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification.
Low Power and Shutdown PSA IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop City, Country.
Initiating Event Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop City, Country.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Maintenance Rule Program Workshop Information IAEA Workshop.
M. Khalaquzzaman Nuclear I&C and Information Engineering Lab NQE, KAIST Characteristics of Test and Maintenance Human Errors Leading to Unplanned Reactor.
Organizations of all types and sizes face a range of risks that can affect the achievement of their objectives. Organization's activities Strategic initiatives.
LECTURE 5 Nangwonvuma M/ Byansi D. Components, interfaces and integration Infrastructure, Middleware and Platforms Techniques – Data warehouses, extending.
Failure Modes, Effects and Criticality Analysis
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making “Overview of Level 2 PSA” Workshop Information IAEA Workshop City, Country.
Human Performance Enhancement System Park Young Ho Dept. of Nuclear & Quantum Engineering Korea Advanced Institute of Science and Technology December 23.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Risk Monitoring tools: Requirements of Risk Monitors, relation with the Living.
BASIC PROFESSIONAL TRAINING COURSE Module V Safety classification of structures, systems and components Case Studies Version 1.0, May 2015.
IRSC 2009 Båstad Learning from failure: Research initiatives towards improving safety and reliability of the Swedish railway system Alexander Wilhelmsson.
HUMAN RESOURCE GOVERNANCE, RISK MANAGEMENT AND COMPLIANCE
Methodologies For Systems Analysis.
This teaching material has been made freely available by the KEMRI-Wellcome Trust (Kilifi, Kenya). You can freely download,
Georg Umgiesser and Natalja Čerkasova
Production and Operations Management
HRA: Aerospace Challenges
Presentation transcript:

Human Reliability Analysis IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Human Reliability Analysis Purpose: To present and explain the Human Reliability Analysis Task Learning objectives: To get a global overview of Human Reliability Analysis Task within PSA Tasks framework, to understand Human Reliability Analysis Task objectives, to understand human action classification and SHARP framework Duration: 1[hr] Resources: screen, video projector, PC, PowerPoint 2000® Lecturer Lesson IV 3_7.1 Workshop Information IAEA Workshop City , Country XX - XX Month, Year IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Reliability HUMAN RELIABILITY HUMAN ERROR IAEA Workshop Human Reliability HUMAN RELIABILITY The probability of successful performance of only those human activities necessary to make a system reliable or available. HUMAN ERROR Human Error is simply some human output which is outside the tolerances established by the system requirements in which the person operates. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Reliability Analysis IAEA Workshop Human Reliability Analysis What can happen, i.e., what can go wrong?. How likely is it that this will happen?. If it does happen, which are the consequenses?. The Human Reliability Analysis should be able to answer properly to this three questions and quantify the probability of human error of those actions considered safety relevant IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Goal of Modeling the Human Performance for PSA IAEA Workshop Goal of Modeling the Human Performance for PSA To develop descriptive models to predict how well people will perform what they are supposed to do in normal and abnormal situations. It is not to understand human behavior and all the motivations behind it. A model of a system is an abstraction which reproduces (simulates) symbolically the way in which the system functions. The lecturer will emphasise that the main goal of the human reliability analysis for PSA is to evaluate the human error probability of some specific actions and integrate them in the PSA models IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

IAEA Workshop Human HRA Model The elements that perform a role in the possible human behaviour will be commented IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Error Categorisation IAEA Workshop Human Error Categorisation Omits entite task. Omits a step in a task. ERRORS OF OMISSION Selects wrong control. Misposition of controls. Issue wrong command on information. Selection error Errors of Sequence Timing Errors Qualitative Errors ERRORS OF COMMISSION Too Early. Too Late. There are many other human error classifications possible. The categorisation presented here is only one of the possible useful under the point of view of HRA. The lecturer can include other categorisations Too Little. Too Much. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Action Categories IAEA Workshop Human Action Categories RUTINE Human actions explicitly included in documents (Procedures, Specification, etc…). COGNOSCITIVE Human actuations that require a cognitive process of understanding and decision making, previous to do an action. The lecturer should introduce cognoscitive human errors IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Performance Shaping Factors (PSF) IAEA Workshop Performance Shaping Factors (PSF) Any factor that shapes (Influences) human performance. Less than adequate PSF - Higher human error probabilities. Categories of PSF’s External. Stressor. Internal. The lecturer should explain the difference between the categories of PSFs including examples of external, internal and stressor PSFs (use next slide) IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Some PSF’s in Man-Machine System IAEA Workshop Some PSF’s in Man-Machine System IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Behaviour Types Skill based behaviour. Rule based behaviour. IAEA Workshop Behaviour Types Skill based behaviour. Rule based behaviour. Knowledge based behaviour. Rasmussen classification. Other classifications are possible. Definitions are included in the next slide IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Definitions of Skill-Based, Rule-Based, and Knowledge-Based Behaviour IAEA Workshop Definitions of Skill-Based, Rule-Based, and Knowledge-Based Behaviour Rasmussen, J., Human Errors. A Taxonomy for Describing Human Malfunction in Industrial Installations, Riso-M-2304, Riso National laboratory, Roskilde, Denmark, August 1981. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Logic Tree to Aid in Selection of Expected Behaviour Types IAEA Workshop Logic Tree to Aid in Selection of Expected Behaviour Types The lecturer will explain the use of the tree to define the type of behaviour preferably with some specific examples IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Action Classification IAEA Workshop Human Action Classification TYPE 1 Before an initiating event, plant personnel can affect availability and safety either by inadvertantly disabling equipment, during testing or maintenance, or they can improve the availability of systems by restoring failed equipment through testing and maintenance. TYPE 2 By committing some error, plant personnel can initiate an accident. TYPE 3 By following procedures during the course of an accident, plant personnel can operate standby equipment that will terminate the accident. TYPE 4 Plant personnel, attempting to follow procedures, can make a mistake that aggravates the situation or fails to terminate the accident. TYPE 5 By improvising, plant personnel can restore and operate initial unavailable equipment to terminate an accident. This is the most common human action classification useful for PSA analysis. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

SHARP (SYSTEMATIC HUMAN ACTION RELIABILITY PROCEDURE): IAEA Workshop Procedures SHARP (SYSTEMATIC HUMAN ACTION RELIABILITY PROCEDURE): EPRI-NP-3583 The SHARP methodology can be employed by the analyst as guidance to make assessments of human reliability, suitable for use in a PSA, Different techniques can be used within the SHARP framework, Innovation can be employed when current techniques are deemed insufficient for adequately addressing the case under study. SHARP is the procedure most commonly used in HRA within a PSA but other procedures are possible IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

SHARP Steps (1/2) 1. Definition IAEA Workshop SHARP Steps (1/2) 1. Definition To ensure that all human interactions are adequately considered in the study. 2. Screening To identify the human interactions that are significant to the operation and safety of the plant. 3. Breakdown To develop a detailed description of important human interactions by defining the key influence factors necessary to complete the modelling. The human interaction modelling consists of a representation (e.g., qualitative model), impact assessments and quantification. The lecturer should explain the 7 SHARP steps if it is possible including examples and describing the interface with other PSA tasks, for instance system analysis, event analysis, quantification, etc. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

SHARP Steps (2/2) 4. Representation IAEA Workshop SHARP Steps (2/2) 4. Representation To select and apply techniques for modelling important human interactions in logic structures. Such methods help to identify additional significant human actions that might impact the system logic trees. 5. Impact Assessment To explore the impact of significant human actions identified in the preceding Step on the system logic trees. 6. Quantification To apply appropriate data or other quantification methods to assign probabilities for the various interactions examined, determine sensitivities and establish uncertainty ranges. 7. Documentation To include all necessary information for getting a traceable, understandable, and reproducible assessment. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

IAEA Workshop SHARP Flow Diagram IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Pathways for Quantification of Human Errror Probabilities IAEA Workshop Pathways for Quantification of Human Errror Probabilities REPRESENTATION MODEL/DATA The lecturer will use this slide to introduce the human error probability quantification process explaining the different stages of the process that can be more or less sophisticate depending on the type of human action IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Action Representation IAEA Workshop Human Action Representation A Human Action Representation is a Logic Structure Used to Explain the Different Activities (Decision and/or Actuation) that the Operators Could do when they have to Respond to a Concret Situation : HRA Event Tree. Operator Action Tree, OAT. Expanded Operator Action Tree, EXOAT. Confusion Matrix. The different type of human action representation models are summarised in the following slides IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

IAEA Workshop HRA Event Tree The lecturer will describe the development of an HRA event tree with a simple example with two task in parallel or in series. An example of a simple human action included in a PSA model will be useful IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

IAEA Workshop Operator Action Tree The lecturer will describe the development of an operator action tree. An example can be added. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Expanded Operator Action Tree Representation IAEA Workshop Expanded Operator Action Tree Representation IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Example of Confusion Matrix for Misdiagnosis of an Event IAEA Workshop Example of Confusion Matrix for Misdiagnosis of an Event The lecturer can describe the development of a Confusion Matrix to analyse and quantify possible misdiagnosis errors employing this specific example IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Human Quantification Techniques IAEA Workshop Human Quantification Techniques Handbook of human reliability analysis (THERP) NUREG/CR-1278. Post event human decision errors, operator action tree/time reliability correlation. NUREG/CR-3010. Application of SLIM-MAUD. Human congnitive reliability model for PRA analysis EPRI Project RP 2170-3. Many other quantification techniques exist. Here are collected some of the techniques most commonly employed in HRA for PSA but additional techniques may be included and explained IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Comparison of Quantification Techniques IAEA Workshop Comparison of Quantification Techniques This slide summarises the main characteristics of the quantification techniques. It can be employed to describe briefly the techniques and their differences. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

IAEA Workshop Error of Commission It is the consequence of a human action that is carried out inappropriately and causes that the situation will be worse than if the human action were not carried out. INTENT “A Method for estimating human error probabilities for decision based errors”. ATHEANA “Technical basis and implementation guidelines for a technique for human event analysis”. CREAM “Cognitive reliability and error analysis method”. HITLINE “Human interaction time line”. This slide lists several methodologies that nowadays are been developing to analyse error of commission but that are nor yet used in HRA for conventional PRAs IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making

Conclusions Human actions are always important in the final results. IAEA Workshop Conclusions Human actions are always important in the final results. Studying human behaviour and assign error probabilities is not easy but it is possible. There always will be human failures and errors but their amount and consequences may be limited by a good job. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making