1. IAEA International Atomic Energy Agency New IAEA Safety Guide (information) Human Factor Engineering for NPP (DS492) Alexander Duchac SAS,NSNI

2. IAEA DPP Justification  Why HFE safety guide? A cross-cutting activity that affects I&C design, plant procedures, training, and many other things and that addresses the interfaces between these things Advances in I&C technology (digital) Implementation of EOPs, SAMGs Enhancement of human-machine interface New plants (soft controls, large screens, etc.) Modification of existing plants (CRs,TSC, etc.) Some MS require a specific chapter on HFE in SAR  A systematic consideration of HFE is needed  Currently no specific IAEA safety guide available

3. IAEA HFE in IAEA safety standards SSR 2/1 Requirement 32 Systematic consideration of human factors, including the human– machine interface, shall be included at an early stage in the design process for a nuclear power plant and shall be continued throughout the entire design process SSG-39 Design of I&C Systems Chapter 8 Addresses SSR 2/1 Requirement 65, 66 related to MCR, ECR Focus on providing the information to operate the plant in all operational states and accident conditions HFE not discussed in detail (this was not the objective of SSG-39)

4. IAEA Objectives & Scope To provide specific recommendations to meet SSR 2/1 Req. 32, 65, 66 related to HSI: Operation and maintenance of plant systems Accident conditions Design of controls and displays navigations e.g. Soft controls VDUs Large screen displays Equipment layout Control room, Supplementary control room, Emergency response center, Local controls, etc. Guidance for new plants & modification of existing

5. IAEA Some topics (although important) outside the scope Intentional acts as well as aspects of human performance relating to ‘trustworthiness and background checks’ The plant organizational factors such as: Multiple challenges to human performance, including challenges to situation assessment, planning, decision making, communication, coordination, and task execution Lack of relevant procedural guidance Interaction of human organization and technical factors across all stakeholder organizations Risk management Analysis of human, organizational and technical factors with regard to behavioural aspects

6. IAEA Fukushima Implications Relevant Fukushima accident lessons to be considered: Availability of the information and displays giving to plant operators and other critical personnel during accidents Optimal layout of displays and controls reducing possibility of erroneous operation HSI in the field (accessibility during accident states, equipment status, local controls and measurement devices, etc.

7. IAEA Account for related IAEA standards SSR-2/1Safety of Nuclear Power Plants: Design SSR-2/2Safety of Nuclear Power Plants: Commissioning and Operation SSG-25 Periodic safety review SSG 39Design of I&C Systems GS-R-3Management System for Facilities and Activities (DS456) GSR Part 4 Safety Assessment for Facilities and Activities

8. IAEA Account for related IAEA standards NS-G-2.6Maintenance and Surveillance NS-G-2.8Recruitment, Qualification and Training of Personnel NS-G-2.14Conduct of Operations at Nuclear Power Plants NP-T-3.10Integration of Analog and Digital Instrumentation and Control Systems in Hybrid Control Rooms Now discussion is limited to HFE specific issues to consider when applying these guides

9. IAEA This document will interface with the following relevant international guidance IEC 60960:1988, Edition 1.0 (1988-08-30): Functional design criteria for a safety parameter display system for nuclear power stations IEC 60964-2009, Nuclear Power Plants–Control Room– Design”. IEC 60965:2009, Edition 2.0 (2009-07-16): Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room IEC 61227:2008, Edition 2.0 (2008-04-29): Nuclear power plants - Control rooms - Operator controls IEC 61771:1995, Edition 1.0 (1995-12-13): Nuclear power plants - Main control-room - Verification and validation of design IEC 61772:2009, Edition 2.0 (2009-04-29): Nuclear power plants - Control rooms - Application of visual display units (VDUs) IEC 61839:2000, Edition 1.0 (2000-07-21): Nuclear power plants - Design of control rooms - Functional analysis and assignment IEC 62241:2004, Edition 1.0 (2004-11-02): Nuclear power plants - Main control room - Alarm functions and presentation

10. IAEA NUREG 0700-2002, “Human-System Interface Design Review Guidelines” NUREG 711, Rev. 3 Human Factors Engineering Program Review Model NUREG-0696-1980 Functional Criteria for Emergency Response Facilities NUREG-6400/CR-6400-1997 Human Factors Engineering (HFE) Insights for Advanced Reactors Based Upon Operating Experience IEEE 1289-1998, “Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating Stations” IEEE1023-2004, Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities” This document will interface with the following relevant international guidance

11. IAEA Provisional TOC rev. 1 1. Introduction 2. HFE program management 3. Analysis Review of operating experience Functional requirements analysis and function allocation Tasks analysis Staffing and qualification Treatment of important human actions 4. Human system interface design Main CR Supplementary CR Accessibility and work environment Procedure development Training programme development 5. Human factors verification and validation 6. Design implementation 7. Human performance monitoring

12. IAEA Provisional TOC rev. 1 8. Special topics Consideration of human and organizational factors Decommissioning Severe accidents Commercial of the shelf products Mobile devices Computerized procedures / automatic sequences Alarm management Annexes Examples of human factors assessment methods Bibliography of international I&C standards

13. IAEA Schedule April-November 2014 Internal approvals, NUSSC April 2015 CSS endorsement May 2015 – 1 st CS meeting (structure, scope) November 2015 – 2 nd CS meeting (advanced draft) May 2016 – 3rd CS meeting (final draft) July 2016 – NSNI internal review November 2016 – NUSSC April 2017 MS Comments resolution July 2017 – NUSSC November 2017 – CSS