Workshop Information IAEA Workshop

Size: px
Start display at page:

Download "Workshop Information IAEA Workshop"

Transcription

1 IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Assessment of General Design Aspects of NPPs (Part 2) Lecturer Lesson Lesson III III 1_2 1_2 Workshop Information IAEA Workshop City City,, Country XX XX --XX XX Month, Year Year

2 Items for Discussion Review of Single Failure Criterion System Redundancy System Independence System Diversity Concept of Fail-Safe Design System Interactions and Dependencies Conduct of Single Failure Assessments IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 2

3 Review of Single Failure Criteria.. protection system shall be designed for high functional reliability and inservice testability commensurate with safety functions performed. Redundancy and independence designed into protection system shall be sufficient to assure: 1. No single failure results in the loss of protective function.. 2. Removal from service of any component or channel does not result in loss of required minimum redundancy unless acceptable reliability of operation of protection system can be otherwise demonstrated. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 3

4 Review of Single Failure Criteria..protection system shall be designed to permit periodic testing of its functioning when reactor is in operation, including a capability to test channels independently to determine failures and losses of redundancy that may have occurred. Taken from US Title 10 Code of Federal Regulations, Part 50 Appendix A, General Design Criteria 21 IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 4

5 Example of Potential Single Failure IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 5

6

7

8

9 System Redundancy System redundancy in all critical components is first step to meet single failure criteria. System redundancy reduces system failure probability thus improving reliability. To be redundant requires individual trains have sufficient capacity (Design Margins) to meet functional requirements. 2 redundant trains alone does not meet single failure criteria. Provisions also needed for: periodic on-line testing, and ability to remove a channel from service. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 9

10 System Redundancy IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 10

11 System Redundancy To permit on-line testing and maintenance typically use minimum of 3 redundant trains or channels. To prevent spurious safety system operation (also potential safety concern) it is most common to take 2/3 Coincidence in actuation logic. Current reactor protection systems use either 2/3 or 2/4 coincidence logic. IEEE Std. 279 (1971), IEEE Std. 379 (1988) provide conservative guidance IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 11

12 Example of Too Much Redundancy IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 12

13 System Independence Single Failure Criteria for redundant systems implies redundant trains (or channels) are physically independent of each other. No common dependencies on power or environmental supports. Cross-connections are isolated to prevent fault in one train failing redundant train. IEEE Std. 384 (1984) provides conservative guidance. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 13

14 Example of Lack of Independence IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 14

15 Example of Lack of Independence IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 15

16 System Independence Independence is achieved by: Routing cabling in physically separated metal conduits according to electrical design standards, such as IEEE Std. 384 (1984). Cross-connection using qualified electrical isolation devices Use of Optical Isolators NOT resistors Fluid system cross connections isolated via check valves. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 16

17 System Diversity Reliability of redundant, independent safety system becomes limited by potential for common cause failure. Example: 2/4 train ECCS system will typically have failure probability in 10-4 to 10-5 range. It is difficult to mathematically justify common cause failure probability being significantly lower than this range. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 17

18 Common Cause Failures include Common design error or inadequate Design Margins Common manufacturing defects Common testing or system restoration errors Environmental degradation (dirt, grit, moisture) IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 18

19 System Diversity Potential significance of common cause failure warrants thorough consideration in safety assessments. Additional redundancy is NOT way to address common cause failure. Component diversity is acceptable way to address common cause failure. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 19

20 Diversity Can Be Achieved By Use of different physical operating principles (e.g. : steam and electric driven pumps) Use of different component manufacturers to eliminate common manufacturing defects. Use of different technicians to test, maintain, or restore operating equipment. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 20

21 Concept of Fail-Safe Design Fail-safe concept originated with military concerns over accidental launch of missiles or detonation of weapons. Fail-safe concept requires systematic identification of safe outcome of system failure (e.g. no missile launch!). Central issue of Fail-safe concept typically identification of de-energized state of systems and components. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 21

22 Application of Fail Safe Concept to NPPs Control Rod Clutches, electrical breakers should be designed to TRIP on loss of control power. Relay logic should TRIP on loss of power. Reactor protection system should be designed to TRIP on loss of power supply. ECCS recirculation valves should typically fail as-is. Pneumatic Valves should be assessed which is safest state for loss of air pressure. Solenoid operated valves should be assessed which is safest state for loss of power. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 22

23 Systems Dependencies & Systems Interactions Most NPP designs have redundant protection systems supported by redundant support systems (e.g. AC/DC Power, cooling water, HVAC, etc.) Failure of one train of these individual support systems can lead to very complicated transient events involving sudden loss of ½ of all systems. World operating experience has shown these events can be very severe. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 23

24 Systems Dependencies & Systems Interactions Systems Interactions caused by single failures (steam line rupture in a compartment, inadvertent automatic fire suppression operation) can cause significant components to fail simultaneously. Faults initiated by failed support systems and system interaction events should be considered in Single Failure Assessments. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 24

25 Conduct of Single Failure Assessment Excellent guidance on performing single failure assessments can be found in: IAEA 50-SP-1, IEEE Std. 352 (1987). Single Failure Assessment is deterministic in nature and documented as FMEA. Probability only considered in dispositioning of incredible faults. Purpose: document Single Failure Criteria compliance for safety systems credited in Accident Analysis. Inputs are comparable to those needed for PSA (frequently FMEA conducted in parallel with PSA) IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 25

26 Conduct of Single Failure Assessment Documentation required: All Electrical Schematics, Piping & Instrument Drawings, Isometrics (fluid systems only). Equivalent Schematics for all Support Systems. All Electrical/Mechanical Specifications. System descriptions. Operating Manuals and Operating Procedures. Test/Maintenance Procedures. Operating History Reports for similar equipment at other NPPs. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 26

27 Conduct of Single Failure Assessment Systematic identification of PIEs or Postulated Initiating Events. Identification of systems credited (timing, operation mode) in Accident Analysis. Collapse credited systems, support systems into single list of credited functions. Support system FMEA used to identify any systems interaction transients requiring further accident analysis as new PIEs. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 27

28 Conduct of Single Failure Assessment Single Failure Assessments are LARGE Independent review by Regulatory Body or other external organizations necessitates systematic, auditable documentation. Typical Format is via: Failure Modes and Effects Analysis Table Content of FMEA Table found in 50-SP-1 or IEEE Std. 352 (1987). IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 28

29 Documentation of Single Failure Assessment FMEA Table systematically documents: Specific component identification - Component function - Failure mode - Effect of the failure on the system - Methods available to detect/correct the failure - Any relevant further comments - IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 29

30 Example of Actual FMEA IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 30

31 IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 31

32 Comments from Personal Experience Single Failure assessments and PSA complement each other as tools to investigate safety. Both tools have identified design weaknesses Single Failure assessment provides a more legal proof of regulatory compliance to Regulatory Body than does a PSA because no faults are hidden from consideration. Support System FMEAs frequently used as critical input to PSA for identifying Special Initiators. IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making 32

10. SYSTEM ANALYSIS. The assessment consist of two elements: Safety Analysis Report and an independent Review of Safety Report.

10. SYSTEM ANALYSIS. The assessment consist of two elements: Safety Analysis Report and an independent Review of Safety Report. 10. SYSTEM ANALYSIS Several projects related to the safety analysis of the Ignalina NPP or its safety systems have been performed. The joint Lithuanian - Sweden Barselina project - the first probabilistic

More information

Solenoid Valves used in Safety Instrumented Systems

Solenoid Valves used in Safety Instrumented Systems I&M V9629R1 Solenoid Valves used in Safety Instrumented Systems Operating Manual in accordance with IEC 61508 ASCO Valves Page 1 of 7 Table of Contents 1 Introduction...3 1.1 Terms and Abbreviations...3

More information

Safety Analysis: Event Classification

Safety Analysis: Event Classification IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Safety Analysis: Event Classification Lecturer Lesson IV 1_2 Workshop Information IAEA Workshop City, Country XX - XX Month,

More information

MDEP Common Position No AP

MDEP Common Position No AP MDEP Validity: until net update or archiving MDEP Common Position No AP1000-01 Related to : AP1000 Working Group activities THE DESIGN AND USE OF EXPLOSIVE - ACTUATED (SQUIB) VALVES IN NUCLEAR POWER PLANTS

More information

Workshop Information IAEA Workshop

Workshop Information IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Risk Monitoring tools: Requirements of Risk Monitors, relation with the Living PSA, applications of Risk Monitors Lecturer Lesson

More information

Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design

Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects

More information

Review and Assessment of Engineering Factors

Review and Assessment of Engineering Factors Review and Assessment of Engineering Factors 2013 Learning Objectives After going through this presentation the participants are expected to be familiar with: Engineering factors as follows; Defense in

More information

IAEA Headquarters in Vienna, Austria 6 to 9 June 2017 Ref No.: CN-251. Ivica Bašić, Ivan Vrbanić APoSS d.o.o.

IAEA Headquarters in Vienna, Austria 6 to 9 June 2017 Ref No.: CN-251. Ivica Bašić, Ivan Vrbanić APoSS d.o.o. Overview And Comparison Of International Practices Concerning The Requirements On Single Failure Criterion With Emphasize On New Water-Cooled Reactor Designs Presentation on International Conference on

More information

This manual provides necessary requirements for meeting the IEC or IEC functional safety standards.

This manual provides necessary requirements for meeting the IEC or IEC functional safety standards. Instruction Manual Supplement Safety manual for Fisher Vee-Ball Series Purpose This safety manual provides information necessary to design, install, verify and maintain a Safety Instrumented Function (SIF)

More information

Safety Classification of Structures, Systems and Components in Nuclear Power Plants

Safety Classification of Structures, Systems and Components in Nuclear Power Plants DS367 Draft 5.1 IAEA SAFETY STANDARDS for protecting people and the environment Date: 04/11/2008 Status: for Member States comments Reviewed in NS-SSCS Please submit your comments by 20 March 2009 Safety

More information

IAEA SAFETY STANDARDS for protecting people and the environment

IAEA SAFETY STANDARDS for protecting people and the environment Date: 2016-08-31 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: STEP 8a For Submission to Member States DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS

More information

Section 1: Multiple Choice

Section 1: Multiple Choice CFSP Process Applications Section 1: Multiple Choice EXAMPLE Candidate Exam Number (No Name): Please write down your name in the above provided space. Only one answer is correct. Please circle only the

More information

IAEA SAFETY STANDARDS for protecting people and the environment

IAEA SAFETY STANDARDS for protecting people and the environment IAEA SAFETY STANDARDS for protecting people and the environment DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS DRAFT SAFETY GUIDE DS 482 STATUS: STEP 11 Submission to Review

More information

DeZURIK. KGC Cast Knife Gate Valve. Safety Manual

DeZURIK. KGC Cast Knife Gate Valve. Safety Manual KGC Cast Knife Gate Valve Safety Manual Manual D11036 August 29, 2014 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related Literature... 4 1.5

More information

SAFETY APPROACHES. The practical elimination approach of accident situations for water-cooled nuclear power reactors

SAFETY APPROACHES. The practical elimination approach of accident situations for water-cooled nuclear power reactors SAFETY APPROACHES The practical elimination approach of accident situations for water-cooled nuclear power reactors 2017 SUMMARY The implementation of the defence in depth principle and current regulations

More information

Safety manual for Fisher GX Control Valve and Actuator

Safety manual for Fisher GX Control Valve and Actuator Instruction Manual Supplement GX Valve and Actuator Safety manual for Fisher GX Control Valve and Actuator Purpose This safety manual provides information necessary to design, install, verify and maintain

More information

SIL explained. Understanding the use of valve actuators in SIL rated safety instrumented systems ACTUATION

SIL explained. Understanding the use of valve actuators in SIL rated safety instrumented systems ACTUATION SIL explained Understanding the use of valve actuators in SIL rated safety instrumented systems The requirement for Safety Integrity Level (SIL) equipment can be complicated and confusing. In this document,

More information

(C) Anton Setzer 2003 (except for pictures) A2. Hazard Analysis

(C) Anton Setzer 2003 (except for pictures) A2. Hazard Analysis A2. Hazard Analysis In the following: Presentation of analytical techniques for identifyin hazards. Non-formal, but systematic methods. Tool support for all those techniques exist. Techniques developed

More information

The Nitrogen Threat. The simple answer to a serious problem. 1. Why nitrogen is a risky threat to our reactors? 2. Current strategies to deal with it.

The Nitrogen Threat. The simple answer to a serious problem. 1. Why nitrogen is a risky threat to our reactors? 2. Current strategies to deal with it. International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants. The simple answer to a serious problem Vienna. 6 9 June 2017

More information

RESILIENT SEATED BUTTERFLY VALVES FUNCTIONAL SAFETY MANUAL

RESILIENT SEATED BUTTERFLY VALVES FUNCTIONAL SAFETY MANUAL Per IEC 61508 and IEC 61511 Standards BRAY.COM Table of Contents 1.0 Introduction.................................................... 1 1.1 Terms and Abbreviations...........................................

More information

Every things under control High-Integrity Pressure Protection System (HIPPS)

Every things under control High-Integrity Pressure Protection System (HIPPS) Every things under control www.adico.co info@adico.co Table Of Contents 1. Introduction... 2 2. Standards... 3 3. HIPPS vs Emergency Shut Down... 4 4. Safety Requirement Specification... 4 5. Device Integrity

More information

DeZURIK. KSV Knife Gate Valve. Safety Manual

DeZURIK. KSV Knife Gate Valve. Safety Manual KSV Knife Gate Valve Safety Manual Manual D11035 August 29, 2014 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related Literature... 4 1.5 Reference

More information

Reliability of Safety-Critical Systems Chapter 4. Testing and Maintenance

Reliability of Safety-Critical Systems Chapter 4. Testing and Maintenance Reliability of Safety-Critical Systems Chapter 4. Testing and Maintenance Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no RAMS Group Department of Production and Quality Engineering NTNU

More information

UKEPR Issue 04

UKEPR Issue 04 Title: PCSR Sub-chapter 6.8 Main steam relief train system - VDA [MSRT] Total number of pages: 16 Page No.: I / III Chapter Pilot: M. LACHAISE Name/Initials Date 25-06-2012 Approved for EDF by: A. PETIT

More information

FP15 Interface Valve. SIL Safety Manual. SIL SM.018 Rev 1. Compiled By : G. Elliott, Date: 30/10/2017. Innovative and Reliable Valve & Pump Solutions

FP15 Interface Valve. SIL Safety Manual. SIL SM.018 Rev 1. Compiled By : G. Elliott, Date: 30/10/2017. Innovative and Reliable Valve & Pump Solutions SIL SM.018 Rev 1 FP15 Interface Valve Compiled By : G. Elliott, Date: 30/10/2017 FP15/L1 FP15/H1 Contents Terminology Definitions......3 Acronyms & Abbreviations...4 1. Introduction...5 1.1 Scope.. 5 1.2

More information

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)

More information

Regulatory requirements with respect to Spent Fuel Pool Cooling

Regulatory requirements with respect to Spent Fuel Pool Cooling Regulatory requirements with respect to Spent Fuel Pool Cooling Dr. Christoph Pistner Annual Meeting on Nuclear Technology Hamburg, 12.05.2016 Important Documents Safety Requirements for Nuclear Power

More information

Eutectic Plug Valve. SIL Safety Manual. SIL SM.015 Rev 0. Compiled By : G. Elliott, Date: 19/10/2016. Innovative and Reliable Valve & Pump Solutions

Eutectic Plug Valve. SIL Safety Manual. SIL SM.015 Rev 0. Compiled By : G. Elliott, Date: 19/10/2016. Innovative and Reliable Valve & Pump Solutions SIL SM.015 Rev 0 Eutectic Plug Valve Compiled By : G. Elliott, Date: 19/10/2016 Contents Terminology Definitions......3 Acronyms & Abbreviations...4 1. Introduction..5 1.1 Scope 5 1.2 Relevant Standards

More information

TRI LOK SAFETY MANUAL TRI LOK TRIPLE OFFSET BUTTERFLY VALVE. The High Performance Company

TRI LOK SAFETY MANUAL TRI LOK TRIPLE OFFSET BUTTERFLY VALVE. The High Performance Company TRI LOK TRI LOK TRIPLE OFFSET BUTTERFLY VALVE SAFETY MANUAL The High Performance Company Table of Contents 1.0 Introduction...1 1.1 Terms and Abbreviations... 1 1.2 Acronyms... 1 1.3 Product Support...

More information

Assessing Combinations of Hazards in a Probabilistic Safety Analysis

Assessing Combinations of Hazards in a Probabilistic Safety Analysis Assessing Combinations of Hazards in a Probabilistic Safety Analysis Halbert Taekema a, and Hans Brinkman a a NRG, Arnhem, The Netherlands Abstract: Guidance on how to systematically address combination

More information

This publication is no longer valid Please see Application of the Single Failure Criterion

This publication is no longer valid Please see  Application of the Single Failure Criterion SAFETY SERIES No. 50-P-1 LU O < LU LJ_ Application of the Single Failure Criterion A PUBLICATION WITHIN THE NUSS PROGRAMME INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1990 CATEGORIES IN THE IAEA SAFETY

More information

Pneumatic QEV. SIL Safety Manual SIL SM Compiled By : G. Elliott, Date: 8/19/2015. Innovative and Reliable Valve & Pump Solutions

Pneumatic QEV. SIL Safety Manual SIL SM Compiled By : G. Elliott, Date: 8/19/2015. Innovative and Reliable Valve & Pump Solutions SIL SM.0010 1 Pneumatic QEV Compiled By : G. Elliott, Date: 8/19/2015 Contents Terminology Definitions......3 Acronyms & Abbreviations..4 1. Introduction 5 1.1 Scope 5 1.2 Relevant Standards 5 1.3 Other

More information

DeZURIK Double Block & Bleed (DBB) Knife Gate Valve Safety Manual

DeZURIK Double Block & Bleed (DBB) Knife Gate Valve Safety Manual Double Block & Bleed (DBB) Knife Gate Valve Safety Manual Manual D11044 September, 2015 Table of Contents 1 Introduction... 3 1.1 Terms... 3 1.2 Abbreviations... 4 1.3 Product Support... 4 1.4 Related

More information

IEM on Severe Accident Management in the light of the accident at the Fukushima Daïchi NPP

IEM on Severe Accident Management in the light of the accident at the Fukushima Daïchi NPP IEM on Severe Accident Management in the light of the accident at the Fukushima Daïchi NPP Progress, challenges and perspectives in the field of design features, as regards SAMG IAEA, March 2014 Introduction

More information

Assessment of Internal Hazards

Assessment of Internal Hazards Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste, 12-23 October 2015 Assessment of Internal Hazards Javier Yllera Department

More information

Bespoke Hydraulic Manifold Assembly

Bespoke Hydraulic Manifold Assembly SIL SM.0003 1 Bespoke Hydraulic Manifold Assembly Compiled By : G. Elliott, Date: 12/17/2015 Contents Terminology Definitions......3 Acronyms & Abbreviations..4 1. Introduction 5 1.1 Scope 5 1.2 Relevant

More information

Hydraulic (Subsea) Shuttle Valves

Hydraulic (Subsea) Shuttle Valves SIL SM.009 0 Hydraulic (Subsea) Shuttle Valves Compiled By : G. Elliott, Date: 11/3/2014 Contents Terminology Definitions......3 Acronyms & Abbreviations..4 1. Introduction 5 1.1 Scope 5 1.2 Relevant Standards

More information

IAEA Regional Workshop Legal and Regulatory Aspects of Decommissioning of Research Reactors June Manila, Philippines

IAEA Regional Workshop Legal and Regulatory Aspects of Decommissioning of Research Reactors June Manila, Philippines IAEA Regional Workshop Legal and Regulatory Aspects of Decommissioning of Research Reactors 26 30 June 2006 Manila, Philippines Monday, 26 June 2006 09:00 09:45 Opening (A. Dela Rosa, B. Batandjieva) Welcoming

More information

LECTURE 3 MAINTENANCE DECISION MAKING STRATEGIES (RELIABILITY CENTERED MAINTENANCE)

LECTURE 3 MAINTENANCE DECISION MAKING STRATEGIES (RELIABILITY CENTERED MAINTENANCE) LECTURE 3 MAINTENANCE DECISION MAKING STRATEGIES (RELIABILITY CENTERED MAINTENANCE) Politecnico di Milano, Italy piero.baraldi@polimi.it 1 Types of maintenance approaches Intervention Unplanned Planned

More information

Solenoid Valves For Gas Service FP02G & FP05G

Solenoid Valves For Gas Service FP02G & FP05G SIL Safety Manual SM.0002 Rev 02 Solenoid Valves For Gas Service FP02G & FP05G Compiled By : G. Elliott, Date: 31/10/2017 Reviewed By : Peter Kyrycz Date: 31/10/2017 Contents Terminology Definitions......3

More information

FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge]

FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge] PAGE : 1 / 9 5. CONTAINMENT PURGE (EBA [CSVS]) The Reactor Building purge system comprises the following: A high-capacity EBA system [CSVS] [main purge] A low-capacity EBA system [CSVS] [mini-purge] 5.1.

More information

General maintenance engineering applications

General maintenance engineering applications Unit 868 General maintenance engineering applications UAN: J/600/6007 Level: Level 2 Credit value: 12 GLH: 55 Relationship to NOS: Endorsement by a sector or regulatory body: Aim: This unit has been derived

More information

EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION

EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION EMERGENCY CORE COOLING SYSTEM SIMPLIFICATION XA9846601 R.S. HART Sheridan Park Research Community, Atomic Energy of Canada Ltd, Mississauga, Ontario D.B. RHODES Chalk River Laboratories, Atomic Energy

More information

Reliability of Safety-Critical Systems Chapter 3. Failures and Failure Analysis

Reliability of Safety-Critical Systems Chapter 3. Failures and Failure Analysis Reliability of Safety-Critical Systems Chapter 3. Failures and Failure Analysis Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no RAMS Group Department of Production and Quality Engineering

More information

Preliminary Failure Mode and Effect Analysis for CH HCSB TBM

Preliminary Failure Mode and Effect Analysis for CH HCSB TBM Preliminary Failure Mode and Effect Analysis for CH HCSB TBM Presented by: Chen Zhi Contributors by HCSB TBM Safety Group, in China June 21, 2007 E-mail: chenz@swip.ac.cn Outline Introduction FMEA Main

More information

Advanced LOPA Topics

Advanced LOPA Topics 11 Advanced LOPA Topics 11.1. Purpose The purpose of this chapter is to discuss more complex methods for using the LOPA technique. It is intended for analysts who are competent with applying the basic

More information

SPR - Pneumatic Spool Valve

SPR - Pneumatic Spool Valve SIL SM.008 Rev 7 SPR - Pneumatic Spool Valve Compiled By : G. Elliott, Date: 31/08/17 Contents Terminology Definitions:... 3 Acronyms & Abbreviations:... 4 1.0 Introduction... 5 1.1 Purpose & Scope...

More information

Section 1: Multiple Choice Explained EXAMPLE

Section 1: Multiple Choice Explained EXAMPLE CFSP Process Applications Section 1: Multiple Choice Explained EXAMPLE Candidate Exam Number (No Name): Please write down your name in the above provided space. Only one answer is correct. Please circle

More information

Ranking of safety issues for

Ranking of safety issues for IAEA-TECDOC-640 Ranking of safety issues for WWER-440 model RANKING OF SAFETY ISSUES FOR WWER-440 MODEL PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK RANKING OF SAFETY

More information

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)

More information

DISTRIBUTION LIST. Preliminary Safety Report Chapter 19 Internal Hazards UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF

DISTRIBUTION LIST. Preliminary Safety Report Chapter 19 Internal Hazards UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF Rev: 000 Page: 2 / 20 DISTRIBUTION LIST Recipients GNS Executive GNS all staff Cross Box GNS and BRB all staff CGN EDF Regulators Public Rev: 000 Page: 3 / 20 SENSITIVE INFORMATION RECORD Section Number

More information

Understanding safety life cycles

Understanding safety life cycles Understanding safety life cycles IEC/EN 61508 is the basis for the specification, design, and operation of safety instrumented systems (SIS) Fast Forward: IEC/EN 61508 standards need to be implemented

More information

Lifespan Improvements Available in the Industry

Lifespan Improvements Available in the Industry Refining Actuator Systems and Their Reliability, Lifespan Improvements Available in the Industry League City, TX, April 12-15, 2010 Philip Black, Director pbblack@earthlink.net 1 Extending the Lifespan

More information

GUIDELINES FOR VESSELS WITH DYNAMIC POSITIONING SYSTEMS ***

GUIDELINES FOR VESSELS WITH DYNAMIC POSITIONING SYSTEMS *** INTERNATIONAL MARITIME ORGANIZATION 4 ALBERT EMBANKMENT MSC/Circ.645 LONDON SE1 7SR 6 June 1994 Telephone: 020 7735 7611 Fax: 020 7587 3210 Telex: 23588 IMOLDN G Ref. T4/3.03 GUIDELINES FOR VESSELS WITH

More information

Enhancing NPP Safety through an Effective Dependability Management

Enhancing NPP Safety through an Effective Dependability Management Prepared and presented by Gheorghe VIERU, PhD Senior Scientific Nuclear Security Research Worker AREN/c.o. Institute for Nuclear Research Pitesti, ROMANIA Safety: Defence in Depth, October 2013 1 OUTLINES

More information

Neles trunnion mounted ball valve Series D Rev. 2. Safety Manual

Neles trunnion mounted ball valve Series D Rev. 2. Safety Manual Neles trunnion mounted ball valve Series D Rev. 2 Safety Manual 10SM D en 1/2017 2 Neles trunnion mounted ball valve, Series D Table of Contents 1 Introduction...3 2 Structure of the D series trunnion

More information

Nuclear Safety Regulation: Before and after Fukushima*

Nuclear Safety Regulation: Before and after Fukushima* Nuclear Safety Regulation: Before and after Fukushima* Shridhar Chande, India International Conference on Effective Nuclear Regulatory Systems: Sustaining Improvements Globally, Vienna 11-15 April 2016

More information

The Best Use of Lockout/Tagout and Control Reliable Circuits

The Best Use of Lockout/Tagout and Control Reliable Circuits Session No. 565 The Best Use of Lockout/Tagout and Control Reliable Circuits Introduction L. Tyson Ross, P.E., C.S.P. Principal LJB Inc. Dayton, Ohio Anyone involved in the design, installation, operation,

More information

General maintenance engineering applications

General maintenance engineering applications Unit 068 General maintenance engineering applications Level: 2 Credit value: 12 NDAQ number: 500/9514/6 Unit aim This unit covers the skills and knowledge needed to prove the competences required to cover

More information

Hazard Identification

Hazard Identification Hazard Identification Most important stage of Risk Assessment Process 35+ Techniques Quantitative / Qualitative Failure Modes and Effects Analysis FMEA Energy Analysis Hazard and Operability Studies HAZOP

More information

Why do I need dual channel safety? Pete Archer - Product Specialist June 2018

Why do I need dual channel safety? Pete Archer - Product Specialist June 2018 Why do I need dual channel safety? Pete Archer - Product Specialist June 2018 To answer this, we need some basic background information. First why is safety needed? Here are 4 good reasons. 1. To Protect

More information

REDUNDANT PROPULSION SHIPS RULES FOR CLASSIFICATION OF NEWBUILDINGS DET NORSKE VERITAS SPECIAL EQUIPMENT AND SYSTEMS ADDITIONAL CLASS PART 6 CHAPTER 2

REDUNDANT PROPULSION SHIPS RULES FOR CLASSIFICATION OF NEWBUILDINGS DET NORSKE VERITAS SPECIAL EQUIPMENT AND SYSTEMS ADDITIONAL CLASS PART 6 CHAPTER 2 RULES FOR CLASSIFICATION OF SHIPS NEWBUILDINGS SPECIAL EQUIPMENT AND SYSTEMS ADDITIONAL CLASS PART 6 CHAPTER 2 REDUNDANT PROPULSION JANUARY 1996 CONTENTS PAGE Sec. 1 General Requirements... 5 Sec. 2 System

More information

PROCEDURE. April 20, TOP dated 11/1/88

PROCEDURE. April 20, TOP dated 11/1/88 Subject: Effective Date: page 1 of 2 Initiated by: Failure Modes and Effects Analysis April 20, 1999 Supersedes: TOP 22.019 dated 11/1/88 Head, Engineering and Technical Infrastructure Approved: Director

More information

NUBIKI Nuclear Safety Research Institute, Budapest, Hungary

NUBIKI Nuclear Safety Research Institute, Budapest, Hungary System Reliability Analysis and Probabilistic Safety Assessment to Support the Design of a New Containment Cooling System for Severe Accident Management at NPP Paks Tamas Siklossy* a, Attila Bareith a,

More information

APPLICATION OF THE FAILURE MODES AND EFFECTS ANALYSIS TECHNIQUE TO THE EMERGENCY COOLING SYSTEM OF AN EXPERIMENTAL NUCLEAR POWER PLANT

APPLICATION OF THE FAILURE MODES AND EFFECTS ANALYSIS TECHNIQUE TO THE EMERGENCY COOLING SYSTEM OF AN EXPERIMENTAL NUCLEAR POWER PLANT 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 APPLICATION

More information

Calibration Requirements for Direct Reading Confined Space Gas Detectors

Calibration Requirements for Direct Reading Confined Space Gas Detectors : Calibration Requirements for Direct Reading Confined Space Gas Detectors However, the definition of bump test has always been a little slippery. Some manufacturers differentiate between a bump test that

More information

FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS])

FUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS]) PAGE : 1 / 16 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS]) 7.0. SAFETY REQUIREMENTS 7.0.1. Safety functions The main functions of the EVU system [CHRS] are to limit the pressure inside the containment

More information

Instrumented Safety Systems

Instrumented Safety Systems Instrumented Safety Systems Engineered Valve Systems for Control and Safety Applications HIPPS Final Elements DINO OLIVIERI Mokveld Agent AIS ISA Giornata di studio HIPPS Agenda The loop Final Elements

More information

SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 440/270 REACTOR

SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 440/270 REACTOR PROCEEDINGS OF THE YEREVAN STATE UNIVERSITY Physical and Mathematical Sciences 216, 2, p. 57 62 P h y s i c s SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 44/27

More information

SIL Safety Manual. ULTRAMAT 6 Gas Analyzer for the Determination of IR-Absorbing Gases. Supplement to instruction manual ULTRAMAT 6 and OXYMAT 6

SIL Safety Manual. ULTRAMAT 6 Gas Analyzer for the Determination of IR-Absorbing Gases. Supplement to instruction manual ULTRAMAT 6 and OXYMAT 6 ULTRAMAT 6 Gas Analyzer for the Determination of IR-Absorbing Gases SIL Safety Manual Supplement to instruction manual ULTRAMAT 6 and OXYMAT 6 ULTRAMAT 6F 7MB2111, 7MB2117, 7MB2112, 7MB2118 ULTRAMAT 6E

More information

TEPCO s Safety Assurance Philosophy on Nuclear Power Generation Plants

TEPCO s Safety Assurance Philosophy on Nuclear Power Generation Plants TEPCO s Safety Assurance Philosophy on Nuclear Power Generation Plants January 25, 2013 Tokyo Electric Power Company, Inc. This English translation has been prepared with the intention of creating an accurate

More information

Return to Session Menu DYNAMIC POSITIONING CONFERENCE QUALITY ASSURANCE SESSION. The Meaning of LIFE. Richard Purser GL Noble Denton

Return to Session Menu DYNAMIC POSITIONING CONFERENCE QUALITY ASSURANCE SESSION. The Meaning of LIFE. Richard Purser GL Noble Denton Return to Session Menu DYNAMIC POSITIONING CONFERENCE October 15-16, 2013 QUALITY ASSURANCE SESSION The Meaning of LIFE Richard Purser GL Noble Denton The Meaning of Life 15 th October 2013 What is the

More information

Complementarity between Safety and Physical Protection in the Protection against Acts of Sabotage of Nuclear Facilities

Complementarity between Safety and Physical Protection in the Protection against Acts of Sabotage of Nuclear Facilities Complementarity between Safety and Physical Protection in the Protection against Acts of Sabotage of Nuclear Facilities Robert Venot Institut de Radioprotection et de Sûreté Nucléaire 77-83, avenue du

More information

Lecture 04 ( ) Hazard Analysis. Systeme hoher Qualität und Sicherheit Universität Bremen WS 2015/2016

Lecture 04 ( ) Hazard Analysis. Systeme hoher Qualität und Sicherheit Universität Bremen WS 2015/2016 Systeme hoher Qualität und Sicherheit Universität Bremen WS 2015/2016 Lecture 04 (02.11.2015) Hazard Analysis Christoph Lüth Jan Peleska Dieter Hutter Where are we? 01: Concepts of Quality 02: Legal Requirements:

More information

Delayed Coker Automation & Interlocks

Delayed Coker Automation & Interlocks Delayed Coker Automation & Interlocks a Presented by Mitch Moloney of ExxonMobil @ coking.com April-2005 MJ Moloney - ExxonMobil April-2005 coking.com 0 Automation & Interlocks @ ExxonMobil - Background

More information

Safe management of industrial steam and hot water boilers A guide for owners, managers and supervisors of boilers, boiler houses and boiler plant

Safe management of industrial steam and hot water boilers A guide for owners, managers and supervisors of boilers, boiler houses and boiler plant Health and Safety Executive Safe management of industrial steam and hot water boilers A guide for owners, managers and supervisors of boilers, boiler houses and boiler plant Background Accidents involving

More information

SEMEMI SQA Unit Code H2AX 04 Carrying out scheduled maintenance tasks on fluid power equipment

SEMEMI SQA Unit Code H2AX 04 Carrying out scheduled maintenance tasks on fluid power equipment Carrying out scheduled maintenance tasks on fluid power equipment Overview This unit identifies the competences you need to carry out scheduled maintenance tasks on fluid power equipment on mobile or static

More information

Suitable for anyone who is required to maintain industrial pneumatic systems. No prior knowledge of pneumatic or electrical principles is necessary.

Suitable for anyone who is required to maintain industrial pneumatic systems. No prior knowledge of pneumatic or electrical principles is necessary. PNEUMATICS COURSE 660: 4 DAYS: Max 8 Candidates This course provides maintenance personnel and production operators etc with the skills and knowledge necessary to carry out maintenance tasks on pneumatic

More information

PI MODERN RELIABILITY TECHNIQUES OBJECTIVES. 5.1 Describe each of the following reliability assessment techniques by:

PI MODERN RELIABILITY TECHNIQUES OBJECTIVES. 5.1 Describe each of the following reliability assessment techniques by: PI 21. 05 PI 21. 05 MODERN RELIABILITY TECHNIQUES OBJECTIVES 5.1 Describe each of the following reliability assessment techniques by: ~) Stating its purpose. i1) Giving an e ample of where it is used.

More information

PREDICTING HEALTH OF FINAL CONTROL ELEMENT OF SAFETY INSTRUMENTED SYSTEM BY DIGITAL VALVE CONTROLLER

PREDICTING HEALTH OF FINAL CONTROL ELEMENT OF SAFETY INSTRUMENTED SYSTEM BY DIGITAL VALVE CONTROLLER PREDICTING HEALTH OF FINAL CONTROL ELEMENT OF SAFETY INSTRUMENTED SYSTEM BY DIGITAL VALVE CONTROLLER Riyaz Ali FIELDVUE Business Development Manager Fisher Controls Int'l., LLC. Marshalltown, IA 50158

More information

Safety Engineering - Hazard Identification Techniques - M. Jahoda

Safety Engineering - Hazard Identification Techniques - M. Jahoda Safety Engineering - Hazard Identification Techniques - M. Jahoda Hazard identification The risk management of a plant 2 Identification of the hazards involved in the operation of the plant, due to the

More information

VALVES OPERATION, MAINTENANCE & TROUBLESHOOTING

VALVES OPERATION, MAINTENANCE & TROUBLESHOOTING Training Title VALVES OPERATION, MAINTENANCE & TROUBLESHOOTING Training Duration 5 days Training Venue and Dates Valves operation, Maintenance & Troubleshooting 5 02-06 Dec $3,750 Dubai, UAE In any of

More information

How to reinforce the defence-indepth in NPP by taking into account natural hazards?

How to reinforce the defence-indepth in NPP by taking into account natural hazards? How to reinforce the defence-indepth in NPP by taking into account natural hazards? Caroline LAVARENNE Karine HERVIOU Patricia DUPUY Céline PICOT IAEA 21-24 October 2013, Vienna Introduction The DiD has

More information

Containment Isolation system analysis and its contribution to level 2 PSA results in Doel 3 unit

Containment Isolation system analysis and its contribution to level 2 PSA results in Doel 3 unit Containment Isolation system analysis and its contribution to level 2 PSA results in Doel 3 unit Marius LONTOS a*, Stanislas MITAILLÉ a, and Shizhen YU a, Jérémy BULLE a TRACTEBEL ENGIE, Brussels, Belgium

More information

Understanding the How, Why, and What of a Safety Integrity Level (SIL)

Understanding the How, Why, and What of a Safety Integrity Level (SIL) Understanding the How, Why, and What of a Safety Integrity Level (SIL) Audio is provided via internet. Please enable your speaker (in all places) and mute your microphone. Understanding the How, Why, and

More information

The «practical elimination» approach for pressurized water reactors

The «practical elimination» approach for pressurized water reactors The «practical elimination» approach for pressurized water reactors V. TIBERI K.HERVIOU International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water

More information

Risks Associated with Caissons on Ageing Offshore Facilities

Risks Associated with Caissons on Ageing Offshore Facilities Risks Associated with Caissons on Ageing Offshore Facilities D. Michael Johnson, DNV GL, Peter Joyce, BG Group, Sumeet Pabby, BG Group, Innes Lawtie, BG Group. Neil Arthur, BG Group, Paul Murray, DNV GL.

More information

Maintaining mechanical devices and equipment. Outcome one

Maintaining mechanical devices and equipment. Outcome one 006 UNIT 019 Maintaining mechanical devices and equipment Learning outcomes 1 Maintain mechanical devices and equipment 2 Know how to maintain mechanical devices and equipment Performance evidence must

More information

Reliability of Safety-Critical Systems Chapter 10. Common-Cause Failures - part 1

Reliability of Safety-Critical Systems Chapter 10. Common-Cause Failures - part 1 Reliability of Safety-Critical Systems Chapter 10. Common-Cause Failures - part 1 Mary Ann Lundteigen and Marvin Rausand mary.a.lundteigen@ntnu.no &marvin.rausand@ntnu.no RAMS Group Department of Production

More information

4. Hazard Analysis. Limitations of Formal Methods. Need for Hazard Analysis. Limitations of Formal Methods

4. Hazard Analysis. Limitations of Formal Methods. Need for Hazard Analysis. Limitations of Formal Methods 4. Hazard Analysis We have seen limitations of formal verification of computer systems. Formal methods don t take into consideration hardware aspects. E.g. that the wires in a railway signalling system

More information

ONR GUIDE. Internal Hazards. Nuclear Safety Technical Assessment Guide. NS-TAST-GD-014 Revision 4

ONR GUIDE. Internal Hazards. Nuclear Safety Technical Assessment Guide. NS-TAST-GD-014 Revision 4 Title of document ONR GUIDE Internal Hazards Document Type: Unique Document ID and Revision No: Nuclear Safety Technical Assessment Guide NS-TAST-GD-014 Revision 4 Date Issued: September 2016 Review Date:

More information

GSA POLICY ON LOCAL EXHAUST AND OTHER VENTILATION (FUME CUPBOARDS)

GSA POLICY ON LOCAL EXHAUST AND OTHER VENTILATION (FUME CUPBOARDS) GSA POLICY ON LOCAL EXHAUST AND OTHER VENTILATION (FUME CUPBOARDS) Local Exhaust Ventilation Inspection & Maintenance 1 LOCAL EXHAUST AND OTHER VENTILATION Contents 1. Introduction 2. Design specifications

More information

Health and Safety Executive. Key aspects of HS(G) 253. Andrew Hall HID CI 1G. HM Specialist Inspector (Mechanical)

Health and Safety Executive. Key aspects of HS(G) 253. Andrew Hall HID CI 1G. HM Specialist Inspector (Mechanical) Health and Safety Executive Key aspects of HS(G) 253 Andrew Hall HID CI 1G HM Specialist Inspector (Mechanical) Human Factors Human Failures can be grouped into: Errors And Violations Errors are not intended

More information

IST-203 Online DCS Migration Tool. Product presentation

IST-203 Online DCS Migration Tool. Product presentation IST-203 Online DCS Migration Tool Product presentation DCS Migration Defining the problem Table of contents Online DCS Migration Tool (IST-203) Technical background Advantages How to save money and reduce

More information

SIL Safety Manual for Fisherr ED, ES, ET, EZ, HP, or HPA Valves with 657 / 667 Actuator

SIL Safety Manual for Fisherr ED, ES, ET, EZ, HP, or HPA Valves with 657 / 667 Actuator SIL Safety Manual ED, ES, ET, EZ, HP, HPA Valves w/ 657/667 Actuator SIL Safety Manual for Fisherr ED, ES, ET, EZ, HP, or HPA Valves with 657 / 667 Actuator Purpose This safety manual provides information

More information

Training Fees 4,000 US$ per participant for Public Training includes Materials/Handouts, tea/coffee breaks, refreshments & Buffet Lunch.

Training Fees 4,000 US$ per participant for Public Training includes Materials/Handouts, tea/coffee breaks, refreshments & Buffet Lunch. Training Title CONTROL & SAFETY RELIEF VALVES Training Duration 5 days Training Venue and Dates Control & Safety Relief Valves 5 06-10 May, 2018 $4,000 Dubai, UAE Trainings will be conducted in any of

More information

T e l N o : F a x N o : E m a i l : a i s h c m c - m e. c o m w w w. c m c - m e.

T e l N o : F a x N o : E m a i l : a i s h c m c - m e. c o m w w w. c m c - m e. MU047: Practical Valve Technology: Selection, Installation, Upgrading, Inspection & Troubleshooting MU047 Rev.002 CMCT COURSE OUTLINE Page 1 of 7 Training Description: This five-day intensive course covers

More information

Rules for Classification and Construction Ship Technology

Rules for Classification and Construction Ship Technology I Rules for Classification and Construction Ship Technology 1 Seagoing Ships 14 Redundant Propulsion and Steering Systems Edition 2000 The following Rules come into force on 1 st August 2000 They are translated

More information

Regulatory Review of Safety Assessment for Decommissioning of Facilities Using Radioactive Material

Regulatory Review of Safety Assessment for Decommissioning of Facilities Using Radioactive Material SAFETY ASSESSMENT FOR DECOMMISSIONING Annex III Regulatory Review of Safety Assessment for Decommissioning of Facilities Using Radioactive Material INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA CONTENTS 1.

More information

1309 Hazard Assessment Fundamentals

1309 Hazard Assessment Fundamentals 1309 Hazard Assessment Fundamentals Jim Marko Manager, Aircraft Integration & Safety Assessment 14 November 2018 Presentation Overview Fail-safe design concept Safety Assessment principles for hazard classification

More information