TIME DEPENDENT RELIABILITY OF EMRGENCY DIESEL GENERATOR STATION

Size: px
Start display at page:

Download "TIME DEPENDENT RELIABILITY OF EMRGENCY DIESEL GENERATOR STATION"

Transcription

1 Indian J.Sci.Res.1(2) : , 2014 ISSN: (Online) ISSN : (Print) TIME DEPENDENT RELIABILITY OF EMRGENCY DIESEL GENERATOR STATION SIMA RASTAYESH 1a, SAJJAD BAHREBAR b, AND KAMRAN SEPANLOO c ab Science and Research Branch Islamic Azad University of Tehran c Daneshestan Institute of Higher Education ABSTRACT As a consequence of Emergency diesel generators (EDGs) are in stand-by status through normal operation of nuclear power plants (NPPs), it is required to make certain about their start-up in demand. Due to the fact that they are in standby mode for a long period of time, it is essential to consider time effect in system reliability during reactor age. This (Ageing) would be influence on component s reliability for plants, which are designed for more than 25 years operation. In this paper, dynamic reliability block diagram (DRBD) is used as one of time dependent methods in reliability assessment of emergency diesel generator station (EDGS) which that its unavailability would lead to a severe accident such as Fukushima. In order to consider that an appropriate time dependent reliability distribution has been selected. Timedependent reliability models have been utilized to study EDGS s reliability. All mechanical subsystems properties including: fuel storage & pumping, lubrication, cooling, starting air and air cooling system compared with each other by taking into account scheduled, corrective and preventive tasks and dependency of all sub sub systems in point of the view of considering time dependent behaviour of all components of EDGS. At the end, by applying discrete event simulation and considering maintenance policy, availability of the system is calculated for 30 years operation of a typical NPP EDGS. KEYWORDS: Ageing, Dynamic Reliability Block Diagram, Discrete Event Simulation, Maintenance, Time Dependent Reliability. Reliability assessment is a vital step, in designing and analyzing (critical) systems. In the last years, reliability assessments have gained widespread importance in many technological areas such as, the nuclear, aerospace and chemical industries (Marseguerraa, 1998). In such cases, accurate models are required to adequately take into account the impact of external environment interference or dependent behaviors affecting the system, especially if the system experiences high complexity (Distefano, 2012). An important characteristic of many engineering systems is that they behave dynamically, i.e. their response to an initial perturbation evolves over time as system components interact with each other and with the environment (Siu, 1994). Conventional reliability assessment methodologies are static in nature and have potential weaknesses when applied to dynamic process systems (Siu, 1992). Conventional methods for reliability assessment such as fault tree are designed to illustrate static relations between logical variables, and do not explicitly include time, process variables, or human behavior (which affect the system dynamic response). effects in the calculations by choosing an appropriate dynamic reliability distribution. Dynamic reliability models have been used to investigate EDGS s reliability. All mechanical subsystems properties including: fuel storage & pumping, lubrication, cooling, starting air and air cooling system compared with each other by taking into account scheduled, corrective and preventive tasks and dependency of all sub sub systems in point of the view of considering time dependent behaviour of all components of EDGS. Finally, by applying discrete event simulation and considering maintenance policy, availability is calculated for 30 years operation of Boushehr NPP EDGS. In recent years, a new generation of dynamic modeling tools for reliability evaluation of complex systems has been developed. Initially, state-space methodologies were successfully used to model systems including interdependencies that could not previously be handled by traditional combinatorial techniques (Manno, 2012). One of these methods is DRBD which can model: load-sharing, standby redundancy, interferences, dependencies, common mode failures. Furthermore, the configuration of a system considering various reliability aspects: failed component /repaired subsystem, the changed systems phases could vary (Distefano, 2007). In this paper, DRBD is used as one of dynamic approaches for reliability assessment of a critical component EDGS, which its unavailability was highlighted in Fukushima accident. One of principal aspects that could affect system s reliability is ageing. Ageing becomes an important issue as average age of operating nuclear power plants is passing over 25 years (Poghosyan). It is necessary to consider ageing INTRODUCTION OF EDGS The EDGS is intended for independent power supply to essential station services on the case of occurrence of loss of off-site power (LOOP). The EDGS incorporates four physically separated trains independent from each other. Each one provides electric power to one safety train. Each train has two diesel generators (DGs). DGs are connected in parallel. In case of power loss, two DGs of each EDGS train are startedup simultaneously and are connected to an emergency bus bar when achieving nominal voltage. It is assumed that the emergency trains won t fail in case of occurrence of initiating events requiring EDGS operation. In 1 Corresponding author

2 NPP normal operation condition, DGs are in stand-by status in a continuous readiness for start-up. By initiating event occurrence, requiring operation of DGs, the start-up of DG is performed automatically. EDGS HAVE FOLLOWING SUPPORT SYSTEMS: i. EDGs Fuel Storage & Pumping System is intended for fuel storage, preparation (sediment, filtration) and supply of fuel to the diesels. ii. EDGs Lubrication System is intended for oil storage, preparation (sediment, filtration) and supply of lubrication oil to the diesel as well as maintaining the diesel in a state of readiness for startup within 15 s. iii. EDGs Cooling Water System (cooling system) is intended for maintaining the predetermined oil and water temperature in diesel standby mode (in a state of readiness for start within 15 s) and cooling the DG and compressor during DG operation on LOOP at the NPP or in its testing mode. iv. EDGs Air Intake & Exhaust System (suction exhaust system) provides intake, cleaning and supply to the diesel of air necessary for combustion process and removal of exhaust gases during DG operation. v. EDGs starting air system is intended for compressed air generation, storage, preparation and supply of air to the diesel. vi. EDGs Air Cooling System is intended for removal of excessive heat releases and maintaining air temperature within the specified limits in DG machine rooms (IAEA-TECHDOC- 643,1992). DYNAMIC MODELING PROCESS Following introducing EDGS system, the relationship among their components is delineated by means of DRBD. Investigation was done through the whole reliability conditions and traced the results for each component, applying for probabilistic risk assessment of Boushehr nuclear power plant (Atom energoproekt, 2003) using generic data (Eide). Distribution selection Reliability model of each component is modeled through Weibull distribution taking into account shape factor (beta) equal to 2. This shape factor is used to consider ageing effect on components by increasing failure rates of them. β in Weibull distribution: β=1 Exponential distribution β 1 Decreasing Failure Rate (DFR) β 1 Increasing Failure Rate (IFR) Scale factor (alpha) was calculated utilizing goodness of fit testing method formulated by using constant failure rate (λ ) in the exponential distribution. In this way: 1 β Mean Time to Failure = = αγ( ) = αγ( ) λ β 2 (1) RESTORATION FACTOR The effect of repair and inspection on restoration of components is calculated by using a restoration factor (RF). In classic assessment, it was assumed that a repaired component is as good as new. This is usually the case when the component is replaced with a new one. The concept of a RF may be used in cases in which one wants to model imperfect repair, or a repair with a used component. The best way to indicate that a component is not as good as new is to give the component some age. A RF concept is used to better describe the existing age of a component. The RF is used to determine the age of the component after a repair or any other maintenance activity. The RF in this paper is defined as a number between 0 and 1 and has the following effect: RF value of 1 (100%) implies that the component is as good as new after repair, which in effect implies that the starting age of the component is 0. RF value of 0 implies that the component is the same as it was prior to repair, which in effect implies that the starting age of the component is the same as the age of the component at failure. RF value of 0.25 (25%) implies that the starting age of the component is equal to 75% of the age of the component at failure. Experience has showed that on the average the RF for EDGS is about 85%; this is an important part for modeling dynamic behavior of a component. These considerations are applied for both corrective tasks and scheduled task properties of each block in DRBD. Standby modeling During this process, for achieving better result for dynamic modeling through DRBD, standby containers is used since the system is considered in standby phase. In standby redundancy, the redundant components are set to be under a lighter load (or no load) condition while not used and under the operating load when activated. In standby redundancy, the components are set to have two states: active state and standby state. Components in standby redundancy have two failure distributions, one for each state. When in the standby state, they have a quiescent (or dormant) failure distribution and when operating, they have an active failure distribution. Indian J.Sci.Res.1(2) : ,

3 As an example, DRBD of Emergency DGs Fuel Storage & Pumping System is shown in (Fig. 1). Figure 1. DRBD of EDGs fuel storage & pumping system including standby containers Sub diagram modeling Furthermore, in the process of modeling sub diagram blocks are employed. Sub diagram blocks represent other diagrams within the project. Utilization of sub diagram blocks allows us to maintain separate diagrams for portions of a system and to incorporate those diagrams as components of another diagram. This also allows generating and analyzing extremely complex diagrams representing many subsystems, sub of subsystems, etc. DRBD of one EDGS train is illustrated in (Fig. 2). Figure 2. DRBD of one EDGS train Including Sub diagrams Mirror group modeling Another methodology for modelling a better dynamic behavior of system is using mirror group. Mirrored blocks allows to place the same block in more than one location. In other words, mirrored blocks allows to represent a single component more than once in a diagram or in multiple diagrams within a project. This is useful, for example, when simulating bi-directional paths within the diagram or if the same item performs more than one function and each function has a different reliability-wise impact on the system. The ability to mirror across diagrams allows to represent situations where a single component s failure affects multiple subsystems that are represented in separate sub diagrams. Any changes made to the properties of a block in a mirror group will apply to all other blocks. Switchgear in (Fig. 3) is an example of mirror group. It can also be seen in (Fig. 2). Indian J.Sci.Res.1(2) : ,

4 Figure 3. DRBD of EDGs lubrication system including mirrored blocks DISCRETE EVENT SIMULATION This is the average time the system was up and operating. This is obtained by taking the sum of the uptimes for each simulation and dividing it by the number of simulations. Obtaining from (Fig. 5) fuel storage and pumping system has the most uptime compare with other sub systems. At the end, discrete event simulation is performed as significant part of dynamic reliability analysis. In contrast to classic FT, DRBD can take into account repair and restoration actions. These actions mean that the age of system components is no longer uniform and the operation of the system is not continuous. If the information on the repair and maintenance characteristics of the components is available in the system, other information can also be obtained, such as system availability. This can be accomplished through discrete event simulation. In this simulation, random failure times are generated from each component's failure distribution. These failure times are then considered in accordance with the way the components are reliability-wise arranged within the system. The overall results are analyzed in order to determine the behavior of the entire system. (ReliaSoft, Weibull) RESULTS AND DISCUSSION The DRBD of EDGS is simulated for 30 years. Simulation results for each subsystem is shown in following figures, number of simulation is assumed Number of failures This is the average number of system downing failures, this number does not include failures with zero duration. It can be undrestood from (Fig. 4) that high percentage share of failures occur in air cooling system. So that focous on improve designing of it should be considered to eliminate numbers of failures of air cooling system. CM Downtime, T CM Down Figure 5. Uptime This is the average time the system was down for corrective maintenance actions (CM) only. This is obtained by taking the sum of the CM downtimes for each simulation and dividing it by the number of simulations Uptime, Figure 4. Number of failures Inspection Downtime This is the average time the system was down due to inspections. This is obtained by taking the sum of the inspection downtimes for each simulation and dividing it by the number of simulations. PM Downtime, This is the average time the system was down due to preventive maintenance (PM) actions. This is obtained by taking the sum of the PM downtimes for each simulation and dividing it by the number of simulations. Indian J.Sci.Res.1(2) : ,

5 Mean Availability (w/o PM, OC & Inspection), This is the mean availability due to failure events only. Downtimes caused by PM and inspections are not included. However, if the PM or inspection action results in the discovery of a failure, then these times are included. As an example, consider a component that has failed but its failure is not discovered until the component is inspected. Then the downtime from the time failed to the time restored after the inspection is counted as failure downtime, since the original event that caused this was the component's failure. Point Availability (All Events), Figure 6. Comparison of corrective maintenance,inspection and preventive downtime Mean Availability (All Events), This is the probability that the system is up at time. As an example, to obtain this value at = 300, a special counter would need to be used during the simulation. This counter is increased by one every time the system is up at 300 hours. Thus, the point availability at 300 would be the times the system was up at 300 divided by the number of simulations. For example, if this is 0.930, or 930 times out of the 1000 simulations the system was up at 300 hours. (Fig. 7) indicates the comparison among all subsystems. This is the mean availability due to all downing events, which can be thought of as the operational availability. It is the ratio of the system uptime divided by the total simulation time (total time). Indian J.Sci.Res.1(2) : ,

6 Figure 7. Comparison of availability of each subsystem MTTFF MTTFF is the mean time to first failure for the system. This is computed by keeping track of the time at which the first system failure occurred for each simulation. MTTFF is then the average of these times. Figure 8. Mean time to first failure Reliability of each sub-diagram decreases over time (30 years). This trend for air cooling system has a rapid rate which indicate that this subdiagram possess more failures than the others. As a result, design of this subdiagram should be done more carefully. For instance using redundant systems could be a solution. It can be seen in (Fig. 9): It is important to note that for each simulation run, if a first failure time is observed, then this is recorded as the system time to first failure. If no failure is observed in the system, then the simulation end time is used as a right censored (suspended) data point. MTTFF is then computed using the total operating time until the first failure divided by the number of observed failures (constant failure rate assumption). Furthermore, and if the simulation end time is much less than the time to first failure for the system, it is also possible that all data points are right censored (i.e., no system failures were observed). In this case, the MTTFF is again computed using a constant failure rate assumption, or: where is the simulation end time and is the number of simulations. One should be aware that this formulation may yield unrealistic (or erroneous) results if the system does not have a constant failure rate. If you are trying to obtain an accurate (realistic) estimate of this value, then your simulation end time should be set to a value that is well beyond the MTTF of the system (as computed analytically). As a general rule, the simulation end time should be at least three times larger than the MTTF of the system. Mean time to first failure according to (Fig. 8) for startup air system is the highest. Figure 9. Reliability vs. time for each subsystem Point reliability for each sub diagram is illustrated in Fig. 9, which shows its independency to corrective and scheduled tasks. It is shown that reliability of a system the main contribution is made by only failure model and the resulting RBD. The availability of system over 30 years decreases. As we can see from the ( Fig. 10), the maintenance policy, shows its effect here. That mean, ageing has effect on availability because it decreases by decreasing reliability and constant maintenance. Indian J.Sci.Res.1(2) : ,

7 Indian J.Sci.Res.1(2) : , 2014 ISSN: (Online) ISSN : (Print) Figure 10. Availability vs. Time for one train of EDGS over 30 years In our assumptions, upper band is 24 hours and its availability calculated , by passing time about 2 years availability become 0.8 which is reasonable because in the availability, corrective tasks and preventive maintenance (inspections) are taken into account and it is assumed that EDGS operates continuous for more than 30 years. IMPORTANCE AND EVALUATION OF RESEARCH Calculations and results of this research are prerequisite for PRA (Probabilistic Risk Assessment) which unavailability of EDGS can lead to core melt down as an example Fukushima accident. Finally, unavailability of Boushehr EDGS NPP including two parallel diesel generators calculated from the mentioned REFERENCES Marseguerraa M., Zioa E., Devooght J., Labeaub P.E.; A concept paper on dynamic reliability via Monte Carlo simulation, Mathematics and Computers in Simulation, 47: Distefano S., Puliafito A., Trivedi K.S.; Dynamic aspects and behaviors of complex systems in performance and reliability assessment, PSAM11-ESREL2012 Proceeding. Siu, N.; Risk assessment for dynamic systems: An overview, Reliability Engineering and System Safety, 43: methods discussed previously is compared with a similar EDGS from generic data (NUREG/CR 6928). It is found that the order of magnitude are at the same range. All preceding calculation are followed by classic methods, which could not calculate a long period of time such as 30 years, which is calculate in this paper. In order to compare unavailability, 24 hour of EDGS operation assumed to validate our results. Table 1. Comparison of unavailability Our calculation 1.1 According NUREG/CR In 24 hour unavailability [Siu N.0.; Dynamic Approaches - Issues and Methods: An Overview. Proceedings of the NATO Advanced Research Workshop on Reliability and Safety Assessment of Dynamic Process Systems, August: 3-7. Manno G., Chiacchio F., Compagno L., D Urso, D., Trapani N.; RAATSS, an extensible Matlab toolbox for the evaluation of repairable dynamic fault trees, PSAM11- ESREL2012 Proceeding. Distefano S., Puliafito A.; Dynamic reliability block diagrams: Overview of a methodology. Risk, Reliability and Societal Safety, ANS PSA 2011 International Topical Meeting on Probabilistic Safety Assessment and Analysis, Wilmington, NC, March 13-17, 2011, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2008). 1 Corresponding author

8 Poghosyan Sh., Amirjanyan A.; Investigation of Ageing Impact on Safety Systems Reliability. Nuclear and Radiation Safety Center. Atom energoproekt.; BVPP Probabi Listic safety Assessment, level 1, revision 3, state resarch, Design and Engineering survey Institute, Atomener goproekt. Eide S.A et al, Industry Average Performance for components and Initiating Events at U.S. Nuclear Regulatory Commission, NUREG/CR BlockSim user's guide; ReliaSoft Corporation; Indian J.Sci.Res.1(2) : ,

ENEA, Italian National Agency for New Technologies, Energy and Sustainable Economic Development Bologna, Italy

ENEA, Italian National Agency for New Technologies, Energy and Sustainable Economic Development Bologna, Italy Open issues associated with passive safety systems reliability assessment L. Burgazzi ENEA, Italian National Agency for New Technologies, Energy and Sustainable Economic Development Bologna, Italy Abstract.

More information

Design for Reliability of Complex System with Limited Failure Data; Case Study of a Horizontal Drilling Equipment

Design for Reliability of Complex System with Limited Failure Data; Case Study of a Horizontal Drilling Equipment Design for Reliability of Complex System with Limited Failure Data; Case Study of a Horizontal Drilling Equipment Morteza Soleimani a*, Mohammad Pourgol-Mohammad b a Tabriz University, Tabriz, Iran b Sahand

More information

Probabilistic Safety Assessment Safety & Regulatory Framework

Probabilistic Safety Assessment Safety & Regulatory Framework Probabilistic Safety Assessment Safety & Regulatory Framework Presentation to the CNSC August 2017 Dr. V.G. Snell 1 Purpose To summarize work done under CNSC contract 87055-16-0251: Role of the Probabilistic

More information

Meetings for Sharing International Knowledge and Experience on Stress Tests

Meetings for Sharing International Knowledge and Experience on Stress Tests Meetings for Sharing International Knowledge and Experience on Stress Tests Presented by: Peter Hughes, Ovidiu Coman, Javier Yllera Department of Nuclear Safety and Security Division of Nuclear Installation

More information

INSIGHTS FROM COMPARISON OF TURBINE HALL FIRE RISK EVALUATED BY THE SIMPLIFIED AND DETAILED APPROACHES

INSIGHTS FROM COMPARISON OF TURBINE HALL FIRE RISK EVALUATED BY THE SIMPLIFIED AND DETAILED APPROACHES INSIGHTS FROM COMPARISON OF TURBINE HALL FIRE RISK EVALUATED BY THE SIMPLIFIED AND DETAILED APPROACHES Gurgen Kanetsyan 1, Shahen Poghosyan 1, Armen Amirjanyan 1, Hovhannes Hovhannisyan 1 1 Nuclear and

More information

International Atomic Energy Agency. Impact of Extreme Events on Nuclear Facilities following Fukushima. Dr C H Shepherd Nuclear Safety Consultant, UK

International Atomic Energy Agency. Impact of Extreme Events on Nuclear Facilities following Fukushima. Dr C H Shepherd Nuclear Safety Consultant, UK Impact of Extreme Events on Nuclear Facilities following Fukushima by Dr C H Shepherd Nuclear Safety Consultant, UK CRA PSA/HFA Forum 8-9 September 2011, Warrington Contents of the Presentation IAEA views

More information

Reliability Data Analysis with Excel and Minitab

Reliability Data Analysis with Excel and Minitab Reliability Data Analysis with Excel and Minitab Kenneth S. Stephens ASQ Quality Press Milwaukee, Wisconsin Table of Contents CD-ROM Contents List of Figures and Tables xiii xvii Chapter 1 Introduction

More information

Use of PSA to Support the Safety Management of Nuclear Power Plants

Use of PSA to Support the Safety Management of Nuclear Power Plants S ON IMPLEMENTATION OF THE LEGAL REQUIREMENTS Use of PSA to Support the Safety Management of Nuclear Power Plants РР - 6/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY TABLE OF CONTENTS

More information

PROBABILISTIC SAFETY ANALYSIS IN SAFETY MANAGEMENT OF NUCLEAR POWER PLANTS

PROBABILISTIC SAFETY ANALYSIS IN SAFETY MANAGEMENT OF NUCLEAR POWER PLANTS PROBABILISTIC SAFETY ANALYSIS IN SAFETY MANAGEMENT OF NUCLEAR POWER PLANTS 1 GENERAL 3 2 PSA DURING THE DESIGN AND CONSTRUCTION OF A NPP 3 2.1 Probabilistic design objectives 3 2.2 Design phase 4 2.3 Construction

More information

A DYNAMIC ASSESSMENT OF AUXILIARY BUILDING CONTAMINATION AND FAILURE DUE TO A CYBER-INDUCED INTERFACING SYSTEM LOSS OF COOLANT ACCIDENT

A DYNAMIC ASSESSMENT OF AUXILIARY BUILDING CONTAMINATION AND FAILURE DUE TO A CYBER-INDUCED INTERFACING SYSTEM LOSS OF COOLANT ACCIDENT A DYNAMIC ASSESSMENT OF AUXILIARY BUILDING CONTAMINATION AND FAILURE DUE TO A CYBER-INDUCED INTERFACING SYSTEM LOSS OF COOLANT ACCIDENT Z.K. Jankovsky The Ohio State University Columbus, USA Email: jankovsky.3@osu.edu

More information

Regulatory Guide Monitoring the Effectiveness of Maintenance at Nuclear Power Plants

Regulatory Guide Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Regulatory Guide 1.160 Revision 2 Page 1 of 14 Revision 2 March 1997 Regulatory Guide 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Publication Information (Draft issued as

More information

1.Introduction. Hazard rate. Local time

1.Introduction. Hazard rate. Local time 1.Introduction This document discusses first important aspects of maintenance optimization in general. This involves interval optimization of component maintenance, optimum time for renewal of systems,

More information

Regulatory Actions and Follow up Measures against Fukushima Accident in Korea

Regulatory Actions and Follow up Measures against Fukushima Accident in Korea Int Conference on Effective Nuclear Regulatory Systems, April 9, 2013, Canada Regulatory Actions and Follow up Measures against Fukushima Accident in Korea Seon Ho SONG* Korea Institute of Nuclear Safety

More information

Reliability Centered Maintenance Plan for the Utility Section of a Fertilizer Industry: A Case Study

Reliability Centered Maintenance Plan for the Utility Section of a Fertilizer Industry: A Case Study Reliability Centered Maintenance Plan for the Utility Section of a Fertilizer Industry: A Case Study Muhammad Abid*, Suleman Ayub, Humza Wali, Muhammad Najam Tariq Faculty of Mechanical Engineering, Ghulam

More information

Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities

Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities DRAFT Regulatory Document RD-152 Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities Issued for Public Consultation May 2009 CNSC REGULATORY

More information

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams Reactor Technology: Materials, Fuel and Safety Dr. Tony Williams Course Structure Unit 1: Reactor materials Unit 2. Reactor types Unit 3: Health physics, Dosimetry Unit 4: Reactor safety Unit 5: Nuclear

More information

Reliability Tools. Why use the tool? Where to use the tool? What does the tool achieve? When to use the tool?

Reliability Tools. Why use the tool? Where to use the tool? What does the tool achieve? When to use the tool? Reliability Tools What does the tool achieve? When to use the tool? Why use the tool? Where to use the tool? Paul Barringer, P.E. Barringer & Associates, Inc. P.O. Box 3985 Humble, TX 77347 Phone: 281-852-6810

More information

OVERVIEW. AVL Reliability Engineering & Load Matrix

OVERVIEW. AVL Reliability Engineering & Load Matrix AVL Reliability Engineering and Load Matrix OVERVIEW January 2006 Page 1 Content The Reliability Challenge AVL s Reliability Engineering Approach The Load Matrix Conclusions January 2006 Page 2 The Reliability

More information

SIMULATION METHOD FOR RELIABILITY ASSESSMENT OF ELECTRICAL DISTRIBUTION SYSTEMS

SIMULATION METHOD FOR RELIABILITY ASSESSMENT OF ELECTRICAL DISTRIBUTION SYSTEMS SIMULATION METHOD FOR RELIABILITY ASSESSMENT OF ELECTRICAL DISTRIBUTION SYSTEMS Johan Setréus, Lina Bertling, Shima Mousavi Gargari KTH, School of Electrical Engineering, Stockholm, Sweden johan.setreus@ee.kth.se

More information

4»IEEE POWER SYSTEMS .*ISK ASSESSMENT OF. Models, Methods, and Applications. Wiley. Ph.D., Fellow, IfE, CAE, EIC SECOND EDITION

4»IEEE POWER SYSTEMS .*ISK ASSESSMENT OF. Models, Methods, and Applications. Wiley. Ph.D., Fellow, IfE, CAE, EIC SECOND EDITION .*ISK ASSESSMENT OF POWER SYSTEMS Models, Methods, and Applications SECOND EDITION Wenyuan Li, Ph.D., Fellow, IfE, CAE, EIC Chongqing University, China BC H> Canada, n IEEE PRESS SERIES ON POWER ENGINEERING

More information

Attachment VIII-1. July 21, 2011 Nuclear and Industrial Safety Agency

Attachment VIII-1. July 21, 2011 Nuclear and Industrial Safety Agency Assessment Procedures and Implementation Plan Regarding the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities Taking into Account the Accident at Fukushima Dai-ichi Nuclear

More information

Safety enhancement of NPPs in China after Fukushima Accident

Safety enhancement of NPPs in China after Fukushima Accident Safety enhancement of NPPs in China after Fukushima Accident CHAI Guohan 29 June 2015, Brussels National Nuclear Safety Administration, P. R. China Current Development of Nuclear Power Mid of year 2015

More information

Initiators and all barriers: a dynamic method for all PSAs

Initiators and all barriers: a dynamic method for all PSAs Initiators and all barriers: a dynamic method for all PSAs - A practitioners view on the practical implication on our PSAs Presented at the CRA s 8 th annual Risk Forum, 4 th -5 th October 2017 Presenter:

More information

SAFETY AND PERFORMANCE ACHIEVEMENT OF INDIAN NUCLEAR POWER PLANT. Randhir kumar NPCIL Shift charge engineer, TAPS 3&4, NPCIL, INDIA

SAFETY AND PERFORMANCE ACHIEVEMENT OF INDIAN NUCLEAR POWER PLANT. Randhir kumar NPCIL Shift charge engineer, TAPS 3&4, NPCIL, INDIA POSTER PRESENTATION IAEA-CN-164 International Conference on opportunities and challenges for water cooled reactors in the 21 st century- Vienna, Austria. 27-3 October 29 SAFETY AND PERFORMANCE ACHIEVEMENT

More information

CHAPTER - 1 RELIABILITY ENGINEERING BASICS AND OPTIMIZATION TECHNIQUES

CHAPTER - 1 RELIABILITY ENGINEERING BASICS AND OPTIMIZATION TECHNIQUES 1 CHAPTER - 1 RELIABILITY ENGINEERING BASICS AND OPTIMIZATION TECHNIQUES Table of Contents S. No. Description Page No. 1.1 Introduction 2 1.2 Reliability 5 1.3 Reliability analysis 8 1.4 Design for higher

More information

Introduction to Level 2 PSA

Introduction to Level 2 PSA Introduction to Level 2 PSA Dr Charles Shepherd Chief Consultant, Corporate Risk Associates CRA PSA/HFA FORUM 13-14 September 2012, Bristol Accident sequences modelled by the PSA INITIATING EVENTS SAFETY

More information

Attention: Farhad Kolahan Iran Ferdowsi University of Mashhad Iran. Paper Code: CIE00462, CIE00462_2.

Attention: Farhad Kolahan Iran Ferdowsi University of Mashhad Iran. Paper Code: CIE00462, CIE00462_2. Computers & Industrial Engineering An International Journal Hamed Kamal Eldin, Ph.D., PE, Founding Editor, 1976 Elsevier Press, Publishers http://www.umoncton.ca/cie/ Mohamed I. Dessouky, Ph.D., PE Journal

More information

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant 8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100

More information

CAREM-25: a Low-Risk Nuclear Option. Rivera, S.S. and Barón, J.H.

CAREM-25: a Low-Risk Nuclear Option. Rivera, S.S. and Barón, J.H. CAREM-25: a Low-Risk Nuclear Option Rivera, S.S. and Barón, J.H. Presentado en: VI General Congress on Nuclear Energy VII CGEN Minascentro-Bello Horizonte, Brasil, 31 agosto al 3 setiembre 1999 CAREM-25:

More information

APPROVED FOR PUBLIC RELEASE: DISTRIBUTION IS UNLIMITED

APPROVED FOR PUBLIC RELEASE: DISTRIBUTION IS UNLIMITED TECHNICAL MANUAL RELIABILITY/AVAILABILITY OF ELECTRICAL & MECHANICAL SYSTEMS FOR COMMAND, CONTROL, COMMUNICATIONS, COMPUTER, INTELLIGENCE, SURVEILLANCE AND RECONNAISSANCE (C4ISR) FACILITIES APPROVED FOR

More information

Enhancement of Nuclear Safety

Enhancement of Nuclear Safety Enhancement of Nuclear Safety Soon Heung Chang Handong Global University May 6, 2015 Contents 1 2 3 4 Importance of Energy Fundamentals of Nuclear Safety How to Enhance Nuclear Safety Closing Remarks 2

More information

OPERATIONS RESEARCH Code: MB0048. Section-A

OPERATIONS RESEARCH Code: MB0048. Section-A Time: 2 hours OPERATIONS RESEARCH Code: MB0048 Max.Marks:140 Section-A Answer the following 1. Which of the following is an example of a mathematical model? a. Iconic model b. Replacement model c. Analogue

More information

Chapter 4. Mathematical Modeling of Service Outages

Chapter 4. Mathematical Modeling of Service Outages Chapter 4 Mathematical Modeling of Service Outages 4.1 Introduction The end to end availability of mobile communication network is a function of the availability of all the intermediate elements. The physical

More information

ABS TECHNICAL PAPERS Jorge Ballesio, American Bureau of Shipping (ABS), Houston, USA

ABS TECHNICAL PAPERS Jorge Ballesio, American Bureau of Shipping (ABS), Houston, USA Evaluation of Classification Rules Related to Machinery for an Oil Tanker Robert Cross, ABSG Consulting, Houston, USA Jorge Ballesio, American Bureau of Shipping (ABS), Houston, USA Published in the proceedings

More information

Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency

Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident Ryodai NAKAI Japan Atomic Energy Agency Contents Introduction Japanese Government Report to the IAEA

More information

Living PSA applications and Probabilistic Safety Indicators used for the Measurement of Plant Safety Performance

Living PSA applications and Probabilistic Safety Indicators used for the Measurement of Plant Safety Performance Living PSA applications and Probabilistic Safety Indicators used for the Measurement of Plant Safety Performance Dr. Jens Uwe Klügel NPP Goesgen Daeniken 1 Overview Introduction Living PSA applications

More information

Introduction to the 2015 Darlington NGS Probabilistic Safety Assessment. Carlos Lorencez and Robin Manley Ontario Power Generation August 2015

Introduction to the 2015 Darlington NGS Probabilistic Safety Assessment. Carlos Lorencez and Robin Manley Ontario Power Generation August 2015 Introduction to the 2015 Darlington NGS Probabilistic Safety Assessment Carlos Lorencez and Robin Manley Ontario Power Generation August 2015 Introduction to the 2015 Darlington NGS Probabilistic Safety

More information

Overview of Common Mode Outages In Power Systems

Overview of Common Mode Outages In Power Systems Overview of Common Mode Outages In Power Systems Paper Prepared by Task Force of RRPA Subcommittee Presented by Chanan Singh Texas A&M University Defintions A common mode outage refers to simultaneous

More information

Global Reliability Indices Calculation Using Monte Carlo Simulation

Global Reliability Indices Calculation Using Monte Carlo Simulation Global Reliability Indices Calculation Using Monte Carlo Simulation Tadeusz Sikora, Radomír Goňo, Vladimír Král, and Stanislav Rusek Department of Electrical Power Engineering, FEECS, VŠB Technical University

More information

Full electrical LNG-plant: Highest availability and energy efficiency trough overall system design

Full electrical LNG-plant: Highest availability and energy efficiency trough overall system design Full electrical LNG-plant: Highest availability and energy efficiency trough overall system design Dr. Edwin Lerch Principal Expert Power System Dynamics Siemens AG Erlangen, Germany edwin.lerch@siemens.com

More information

The ESBWR an advanced Passive LWR

The ESBWR an advanced Passive LWR 1 IAEA PC-Based Simulators Workshop Politecnico di Milano, 3-14 October 2011 The ES an advanced Passive LWR Prof. George Yadigaroglu, em. ETH-Zurich and ASCOMP yadi@ethz.ch 2 Removal of decay heat from

More information

Isolation Condenser; water evaporation in the tank and steam into the air. Atmosphere (in Severe Accident Management, both P/S and M/S)

Isolation Condenser; water evaporation in the tank and steam into the air. Atmosphere (in Severe Accident Management, both P/S and M/S) Loss of Ultimate Heat Sink ANS AESJ AESJ Fukushima Symposium, March h4, 2012 Hisashi Ninokata, Tokyo Institute of Technology Available ultimate heat sinks at 1F1~3 1F1 (Fukushima Dai ichi Unit 1) Sea water

More information

Development and use of SAMGs in the Krško NPP

Development and use of SAMGs in the Krško NPP REPUBLIC OF SLOVENIA Development and use of SAMGs in the Krško NPP Tomaž Nemec Slovenian Nuclear Safety Administration tomaz.nemec@gov.si IAEA TM on the Verification and Validation of SAMGs, Vienna, 12

More information

Reliability Assessment of a Power Grid with Customer Operated Chp Systems Using Monte Carlo Simulation

Reliability Assessment of a Power Grid with Customer Operated Chp Systems Using Monte Carlo Simulation University of Massachusetts Amherst ScholarWorks@UMass Amherst Masters Theses 1911 - February 2014 2009 Reliability Assessment of a Power Grid with Customer Operated Chp Systems Using Monte Carlo Simulation

More information

High Energy Arcing Faults (HEAF) and Their Impact on PRA for a Nuclear Power Plant Latest International Operating Experience and Research Activities

High Energy Arcing Faults (HEAF) and Their Impact on PRA for a Nuclear Power Plant Latest International Operating Experience and Research Activities High Energy Arcing Faults (HEAF) and Their Impact on PRA for a Nuclear Power Plant Latest International Operating Experience and Research Activities Marina Roewekamp GRS ggmbh, Germany Nicholas Melly,

More information

AP1000 European 15. Accident Analysis Design Control Document

AP1000 European 15. Accident Analysis Design Control Document 15.2 Decrease in Heat Removal by the Secondary System A number of transients and accidents that could result in a reduction of the capacity of the secondary system to remove heat generated in the reactor

More information

IAEA Safety Standards for NPPs Operation

IAEA Safety Standards for NPPs Operation Safety Standards for NPPs Operation April 2010 Miroslav Lipár Operational Safety Section Division of Nuclear Installation Safety International Atomic Energy Agency Content Safety Standards: Categories

More information

Stress tests specifications Proposal by the WENRA Task Force 21 April 2011

Stress tests specifications Proposal by the WENRA Task Force 21 April 2011 Stress tests specifications Proposal by the WENRA Task Force 21 April 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the Council of the European Union declared

More information

Main Steam & T/G Systems, Safety

Main Steam & T/G Systems, Safety Main Steam & T/G Systems, Safety Page 1 This steam generator, built for the Wolsong station in Korea, was manufactured in Canada by the Babcock and Wilcox company. In Wolsong 2,3, and 4 a joint venture

More information

Index. Index

Index. Index Index 643 Index 1 10-6...163 A Access level...see Permission Access privileges...17 ALD...127 Allocation... 235,291,449,450 Ambiguity...277, 450 Analytical calculations...50 Applied values...244 Assemblies...167

More information

Power Generation. Ronaldo Jenkins Electrical Engineering Branch Chief Office of New Reactors (NRO)

Power Generation. Ronaldo Jenkins Electrical Engineering Branch Chief Office of New Reactors (NRO) Power Generation Ronaldo Jenkins Electrical Engineering Branch Chief Office of New Reactors (NRO) Agenda Overview Design Considerations 10 Code of Federal Regulations (CFR) 50 10 CFR 50, General Design

More information

DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA IN DAYA BAY NUCLEAR POWER STATION

DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA IN DAYA BAY NUCLEAR POWER STATION 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-A01-2 DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA

More information

9. Verification, Validation, Testing

9. Verification, Validation, Testing 9. Verification, Validation, Testing (a) Basic Notions (b) Dynamic testing. (c) Static analysis. (d) Modelling. (e) Environmental Simulation. (f) Test Strategies. (g) Tool support. (h) Independent Verification

More information

Reliability demonstration for complex redundant systems in railway applications

Reliability demonstration for complex redundant systems in railway applications WIT Press, www.witpress.com, ISBN -853-86- Reliability demonstration for complex redundant systems in railway applications R. Bozzo\ V. Fazio*, P. Firpo^ S. Savio* ' Dipartimento di Ingegneria Elettrica

More information

Relko Experience with Reliability Analyses of Safety Digital I&C

Relko Experience with Reliability Analyses of Safety Digital I&C Relko Experience with Reliability Analyses of Safety Digital I&C Jana Macsadiova a*, Vladimir Sopira a, Pavol Hlavac a a RELKO Ltd., Bratislava, Slovak Republic Abstract: The using of digital technologies

More information

Plant Reliability Improvement and Financial Gain: What s the Connection?

Plant Reliability Improvement and Financial Gain: What s the Connection? ASSET MANAGEMENT Plant Reliability Improvement and Financial Gain: What s the Connection? By Marcus B. Punch As hydro plant owners modernize and replace generating equipment, they are considering how decisions

More information

New Tool for the Evaluation of the Scheduling of Preventive Maintenance for Chemical Process Plants

New Tool for the Evaluation of the Scheduling of Preventive Maintenance for Chemical Process Plants 1910 Ind. Eng. Chem. Res. 2008, 47, 1910-1924 New Tool for the Evaluation of the Scheduling of Preventive Maintenance for Chemical Process Plants Duy Quang Nguyen, Christopher Brammer, and Miguel Bagajewicz*

More information

Risks Associated with Shutdown in PWRs

Risks Associated with Shutdown in PWRs International Conference Nuclear Option in Countries with Small and Mi Opatija, Croatia, 1996 Risks Associated with Shutdown in PWRs Igor Grlicarev Slovenian Nuclear Safety Administration Vojkova 59, 1113

More information

Seismic Reliability Evaluation of Electrical Power Transmission Systems and its Effect on Core Damage Frequency

Seismic Reliability Evaluation of Electrical Power Transmission Systems and its Effect on Core Damage Frequency Seismic Reliability Evaluation of Electrical Power Transmission Systems and its Effect on Core Damage Frequency Tetsukuni OIKAWA 1), Sei ichiro FUKUSHIMA 2), Hidekazu TAKASE 2), Tomoaki UCHIYAMA MURAMATSU

More information

Workshop Information IAEA Workshop

Workshop Information IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Overview of Deterministic Safety Analysis: Input Data, Verification & Validation, Conservative/BE Approaches (Part. 2) Lecturer

More information

Improvements Needed in Nuclear Power Plant Probabilistic Risk Assessments: Lessons Learned from Fukushima

Improvements Needed in Nuclear Power Plant Probabilistic Risk Assessments: Lessons Learned from Fukushima Improvements Needed in Nuclear Power Plant Probabilistic Risk Assessments: Lessons Learned from Fukushima Mohammad Modarres Professor of Nuclear Engineering Department of Mechanical Engineering University

More information

COMPUTATIONAL ANALYSIS OF A MULTI-SERVER BULK ARRIVAL WITH TWO MODES SERVER BREAKDOWN

COMPUTATIONAL ANALYSIS OF A MULTI-SERVER BULK ARRIVAL WITH TWO MODES SERVER BREAKDOWN Mathematical and Computational Applications, Vol. 1, No. 2, pp. 249-259, 25. Association for cientific Research COMPUTATIONAL ANALYI OF A MULTI-ERVER BULK ARRIVAL ITH TO MODE ERVER BREAKDON A. M. ultan,

More information

Dealing with chance Four strategies. Simple, direct Absolutes. Persuasion Top management support. Training. Corruption Alienation. 3 lines of defense

Dealing with chance Four strategies. Simple, direct Absolutes. Persuasion Top management support. Training. Corruption Alienation. 3 lines of defense Hazard avoidance overview Concepts of Hazard Avoidance Dealing with chance Four strategies Enforcement Psychological Engineering Analytical ١ ٢ Enforcement approach Simple, direct Absolutes Judgment Corruption

More information

Simulation of timing failure and downtime of production line applying dynamic systems

Simulation of timing failure and downtime of production line applying dynamic systems 11 3rd International Conference on Information and Financial Engineering IPEDR vol.12 (11) (11) IACSIT Press, Singapore Simulation of timing failure and downtime of production line applying dynamic systems

More information

Film Capacitors. Quality. Date: May 2009

Film Capacitors. Quality. Date: May 2009 Film Capacitors Quality Date: May 2009 EPCOS AG 2009. Reproduction, publication and dissemination of this publication, enclosures hereto and the information contained therein without EPCOS' prior express

More information

Palo Verde Generating Station NEI Lessons Learned. Michael Wittas September 28, 2017

Palo Verde Generating Station NEI Lessons Learned. Michael Wittas September 28, 2017 Palo Verde Generating Station NEI 16-06 Lessons Learned Michael Wittas September 28, 2017 Overview Background & History Pre-FLEX Temporary Equipment Fukushima Daiichi Response NRC RIS 2008-15 Palo Verde

More information

No Longer at a Loss for Words

No Longer at a Loss for Words No Longer at a Loss for Words Christopher G. Irwin DOE Office of Electricity Delivery & Energy Reliability 2017 Transactive Energy Systems Conference June 13, 2017 Pillars of our Community 2 and yet, here

More information

Probabilistic Safety Assessment (PSA): Case Study Leibstadt NPP. Dr. Olivier Nusbaumer Probabilistic Safety Analysis Kernkraftwerk Leibstadt AG

Probabilistic Safety Assessment (PSA): Case Study Leibstadt NPP. Dr. Olivier Nusbaumer Probabilistic Safety Analysis Kernkraftwerk Leibstadt AG Probabilistic Safety Assessment (PSA): Case Study Leibstadt NPP Dr. Olivier Nusbaumer Probabilistic Safety Analysis Kernkraftwerk Leibstadt AG Background Methodological Aspects Swiss Atomic Law Scope of

More information

Operational Safety Experience at 14 MW TRIGA Research Reactor from INR Pitesti, Romania

Operational Safety Experience at 14 MW TRIGA Research Reactor from INR Pitesti, Romania Operational Safety Experience at 14 MW TRIGA Research Reactor from INR Pitesti, Romania Marin CIOCANESCU, Daniela MLADIN Institute for Nuclear Research Pitesti, PO.Box-78, 115400-Mioveni, Romania Presented

More information

Applicability of PSA Level 2 in the Design of Nuclear Power Plants

Applicability of PSA Level 2 in the Design of Nuclear Power Plants Applicability of PSA Level 2 in the Design of Nuclear Power Plants Estelle C. SAUVAGE a, Gerben DIRKSEN b, and Thierry COYE de BRUNELLIS c a AREVA-NP SAS, Paris, France b AREVA-NP Gmbh, Erlangen, Germany

More information

CLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY

CLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY CLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY 1 Introduction 3 2 Scope of application 3 3 Classification requirements 3 3.1 Principles of safety classification 3 3.2 Classification

More information

RELIABILITY ASSESSMENT OF DISTRIBUTION NETWORS USING SEQUENTIAL MONTE CARLO SIMULATION

RELIABILITY ASSESSMENT OF DISTRIBUTION NETWORS USING SEQUENTIAL MONTE CARLO SIMULATION RELIABILITY ASSESSMENT OF DISTRIBUTION NETWORS USING SEQUENTIAL MONTE CARLO SIMULATION Srete Nikolovski *, Predrag Maric *, Ivan Mravak ** *Faculty of Electrical Engineering, K. Trpimira 2B, 31 Osijek,

More information

Today s vessels are advanced constructions

Today s vessels are advanced constructions Broad approach ensures safety and availability Alf Kåre Ådnanes Ever since shipping began, seafarers have depended on the safety of their vessels and skills of their crews. International regulations, classification

More information

Proposed - For Interim Use and Comment

Proposed - For Interim Use and Comment Proposed - For Interim Use and Comment U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD FOR mpower TM ipwr DESIGN 14.2 INITIAL PLANT TEST PROGRAM - DESIGN CERTIFICATION AND NEW LICENSE

More information

RCM Analysis, Data Management and Reporting RCM++ provides predefined profiles for the major RCM reporting standards (such as ATA MSG-3 and SAE JA1011

RCM Analysis, Data Management and Reporting RCM++ provides predefined profiles for the major RCM reporting standards (such as ATA MSG-3 and SAE JA1011 Putting the reliability back into reliability centered maintenancetm ReliaSoft's RCM++ facilitates the Reliability Centered Maintenance (RCM) analysis approach for creating effective scheduled maintenance

More information

ISA Seminars on the Web Live Experts on Hot Topics

ISA Seminars on the Web Live Experts on Hot Topics ISA Seminars on the Web Live Experts on Hot Topics Standards Certification Education and Training Publishing Conferences and Exhibits CSE PE Exam Review: Safety Systems EN00W6 Version 1.4 2011 Standards

More information

Intermediate Systems Acquisition Course. Designing a Supportable System

Intermediate Systems Acquisition Course. Designing a Supportable System Designing a Supportable System Design decisions made early in the systems engineering process can have a significant long-term impact on the operational effectiveness and cost of a system once it is deployed.

More information

Combined Heat & Power An Overview

Combined Heat & Power An Overview Combined Heat & Power An Overview 6 Distributed Generation DG is An Electric Generator Located At a Substation or Near a Building / Facility Generates at least a portion of the Electric Load DG Technologies..

More information

RELIABILITY PRIMER FOR COMMAND, CONTROL, COMMUNICATIONS, COMPUTER, INTELLIGENCE, SURVEILLANCE, AND RECONNAISSANCE (C4ISR) FACILITIES

RELIABILITY PRIMER FOR COMMAND, CONTROL, COMMUNICATIONS, COMPUTER, INTELLIGENCE, SURVEILLANCE, AND RECONNAISSANCE (C4ISR) FACILITIES TECHNICAL MANUAL RELIABILITY PRIMER FOR COMMAND, CONTROL, COMMUNICATIONS, COMPUTER, INTELLIGENCE, SURVEILLANCE, AND RECONNAISSANCE (C4ISR) FACILITIES APPROVED FOR PUBLIC RELEASE: DISTRIBUTION IS UNLIMITED

More information

International ejournals

International ejournals ISSN 2249 5460 Available online at www.internationalejournals.com International ejournals International Journal of Mathematical Sciences, Technology and Humanities 21 (2011) 205 212 ENERGY CONTROL CENTER

More information

Program Evaluation and Review Technique (PERT)

Program Evaluation and Review Technique (PERT) Program Evaluation and Review Technique (PERT) PERT Bar charts and CPM networks assume all activity durations are constant or deterministic. The assumption of constant durations may not be realistic because

More information

Support for All Types of FMEA plus Related Analyses ReliaSoft s Xfmea supports the major industry standards for all types of FMEA (including Design FM

Support for All Types of FMEA plus Related Analyses ReliaSoft s Xfmea supports the major industry standards for all types of FMEA (including Design FM Expert support for all types of FMEA and FMECATM ReliaSoft s Xfmea facilitates the FMEA/FMECA process and provides flexible data management and reporting capabilities. The software also provides integrated

More information

Engineering systems to avoid disasters

Engineering systems to avoid disasters Critical Systems Engineering Engineering systems to avoid disasters Adapted from Ian Sommerville CSE 466-1 Objectives To introduce the notion of critical systems To describe critical system attributes

More information

Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems

Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems Xu Mingxia Waste Management Division, Nuclear Safety center, State Environmental Protection Administration, Beijing

More information

Cummins power ensures uninterrupted patient care

Cummins power ensures uninterrupted patient care Cummins power ensures uninterrupted patient care Application Expertise Proven Equipment Global Support Unsurpassed Reliability, Experience and Expertise Cummins has both the products and the integration

More information

Optimization of the NAS Battery Control System

Optimization of the NAS Battery Control System Optimization of the NAS Battery Control System Background PG&E has purchased a 4MW, 28MWh sodium-sulfur (NAS) battery to be installed October, 2010 in San Jose at Hitachi headquarters. The site was chosen

More information

REGULATORY GUIDE An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis

REGULATORY GUIDE An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis REGULATORY GUIDE 1.174 An Approach for Using... Page 1 of 38 July 1998 REGULATORY GUIDE 1.174 An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to

More information

COPYRIGHTED MATERIAL RELIABILITY ENGINEERING AND PRODUCT LIFE CYCLE 1.1 RELIABILITY ENGINEERING

COPYRIGHTED MATERIAL RELIABILITY ENGINEERING AND PRODUCT LIFE CYCLE 1.1 RELIABILITY ENGINEERING 1 RELIABILITY ENGINEERING AND PRODUCT LIFE CYCLE 1.1 RELIABILITY ENGINEERING Reliability has a broad meaning in our daily life. In technical terms, reliability is defined as the probability that a product

More information

HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES

HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES D. SONG China Nuclear Power Engineering Co., Ltd. Beijing, China Email: songdy@cnpe.cc J. XING China Nuclear Power Engineering Co., Ltd. Beijing,

More information

Second Law of Thermodynamics

Second Law of Thermodynamics Second Law of Thermodynamics Content Heat engine and its efficiency. Reversible and irreversible processes. The Carnot machine. Kelvin Planck Statement. Refrigerator and Coefficient of Performance. Statement

More information

PMBOK Guide Fifth Edition Pre Release Version October 10, 2012

PMBOK Guide Fifth Edition Pre Release Version October 10, 2012 5.3.1 Define Scope: Inputs PMBOK Guide Fifth Edition 5.3.1.1 Scope Management Plan Described in Section 5.1.3.1.The scope management plan is a component of the project management plan that establishes

More information

The Nuclear Risk Research Center

The Nuclear Risk Research Center The Nuclear Risk Research Center George Apostolakis Head, Nuclear Risk Research Center apostola@mit.edu Idaho National Laboratory April 30, 1 1 Nuclear Safety in Japan Deterministic approach Few PRAs were

More information

Performance, Reliability, and Versatility. Transpector CPM. Fast, Field-ready Process Monitoring System

Performance, Reliability, and Versatility. Transpector CPM. Fast, Field-ready Process Monitoring System Performance, Reliability, and Versatility Transpector CPM Fast, Field-ready Process Monitoring System Precision measurement for modern semiconductor processes INFICON Transpector CPM has been the films.

More information

NUCLEAR POWER PLANT RISK-INFORMED SURVEILLANCE FREQUENCY CONTROL PROGRAM IMPLEMENTATION WITH A FOCUS ON INSTRUMENTATION AND CONTROL SYSTEMS

NUCLEAR POWER PLANT RISK-INFORMED SURVEILLANCE FREQUENCY CONTROL PROGRAM IMPLEMENTATION WITH A FOCUS ON INSTRUMENTATION AND CONTROL SYSTEMS NUCLEAR POWER PLANT RISK-INFORMED SURVEILLANCE FREQUENCY CONTROL PROGRAM IMPLEMENTATION WITH A FOCUS ON INSTRUMENTATION AND CONTROL SYSTEMS James K. (Jim) Liming ABSG Consulting Inc. (ABS Consulting) 300

More information

Institute of Nuclear Technology and Energy Systems

Institute of Nuclear Technology and Energy Systems Institute of Nuclear Technology and Energy Systems Experimental and Analytical Investigation of the Performance of Heat Pipes for Residual Heat Removal from Spent Fuel Pools J. Starflinger, C. Graß, R.

More information

The Risk of Nuclear Power

The Risk of Nuclear Power 13 th International Conference on Probabilistic Safety Assessment and Management [PSAM13] The Risk of Nuclear Power Soon Heung Chang Handong Global University Oct 4, 2016 Contents 1 2 3 4 Introduction:

More information

ASSESSMENT OF THE RELIABILITY OF A DYNAMIC SMART GRID SYSTEM

ASSESSMENT OF THE RELIABILITY OF A DYNAMIC SMART GRID SYSTEM International Journal of Power and Energy Systems, Vol. 3, No. 4, 20 ASSESSMENT OF THE RELIABILITY OF A DYNAMIC SMART GRID SYSTEM Arif Islam, Alex Domijan, and Aleksandar Damnjanovic Abstract One of the

More information

ASSET MANAGEMENT AND AVAILABILITY MODELLING

ASSET MANAGEMENT AND AVAILABILITY MODELLING ASSET MANAGEMENT AND AVAILABILITY MODELLING Mark Chadderton and Khalee Field Summary: Santos, with the assistance of Shell Global Solutions, has undertaken an overhaul of its Reliability and Maintenance

More information

How Energy Harvest Controls Can Increase the Benefits of Solar Direct-Drive Refrigerators

How Energy Harvest Controls Can Increase the Benefits of Solar Direct-Drive Refrigerators How Energy Harvest Controls Can Increase the Benefits of Solar Direct-Drive Refrigerators December 2016 MAILING ADDRESS PO Box 900922 Seattle, WA 98109 USA ADDRESS 2201 Westlake Avenue Suite 200 Seattle,

More information

Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors. JSC ATOMENERGOPROEKT Moscow

Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors. JSC ATOMENERGOPROEKT Moscow Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors Yu. Shvyryaev V. Morozov A. Kuchumov JSC ATOMENERGOPROEKT Moscow Content General information

More information