A systematic approach to safety case maintenance

International Nuclear Information System (INIS)

Kelly, T.P.; McDermid, J.A.

2001-01-01

A crucial aspect of safety case management is the ongoing maintenance of the safety argument through life. Throughout the operational life of any system, changing regulatory requirements, additional safety evidence and a changing design can challenge the corresponding safety case. In order to maintain an accurate account of the safety of the system, all such challenges must be assessed for their impact on the original safety argument. This is increasingly being recognised by many safety standards. However, many safety engineers are experiencing difficulties with safety case maintenance at present, the prime reason being that they do not have a systematic and methodical approach by which to examine the impact of change on safety argument. The size and complexity of safety arguments and evidence being presented within safety cases is increasing. Nowhere is this more apparent than for Electrical, Electronic and Programmable Electronic systems attempting to comply with the requirements and recommendations of software and hardware safety standards such as and UK Defence Standards 00-54 [MoD. 00-54 Requirements of Safety Related Electronic Hardware in Defence Equipment. Ministry of Defence, Interim Defence Standard, 1999], 00-55 []. However, this increase in safety case complexity exacerbates problems of comprehension and maintainability later on in the system lifecycle. This paper defines and describes a tool-supported process, based upon the principles of goal structuring, that attempts to address these difficulties through facilitating the systematic impact assessment of safety case challenges

Designing Interventions that Last: A Classification of Environmental Behaviors in Relation to the Activities, Costs, and Effort Involved for Adoption and Maintenance

Science.gov (United States)

Moore, Harriet E.; Boldero, Jennifer

2017-01-01

Policy makers draw on behavioral research to design interventions that promote the voluntary adoption of environmental behavior in societies. Many environmental behaviors will only be effective if they are maintained over the long-term. In the context of climate change and concerns about future water security, behaviors that involve reducing energy consumption and improving water quality must be continued indefinitely to mitigate global warming and preserve scarce resources. Previous reviews of environmental behavior have focused exclusively on factors related to adoption. This review investigates the factors that influence both adoption and maintenance, and presents a classification of environmental behaviors in terms of the activities, costs, and effort required for both adoption and maintenance. Three categories of behavior are suggested. One-off behaviors involve performing an activity once, such as purchasing an energy efficient washing machine, or signing a petition. Continuous behaviors involve the performance of the same set of behaviors for adoption and for maintenance, such as curbside recycling. Dynamic behaviors involve the performance of different behaviors for adoption and maintenance, such as revegetation. Behaviors can also be classified into four categories related to cost and effort: those that involve little cost and effort for adoption and maintenance, those that involve moderate cost and effort for adoption and maintenance, those that involve a high cost or effort for adoption and less for maintenance, and those that involve less cost or effort for adoption and a higher amount for maintenance. In order to design interventions that last, policy makers should consider the factors that influence the maintenance as well as the adoption of environmental behaviors. PMID:29163265

An approach to maintenance optimization where safety issues are important

International Nuclear Information System (INIS)

Vatn, Jorn; Aven, Terje

2010-01-01

The starting point for this paper is a traditional approach to maintenance optimization where an object function is used for optimizing maintenance intervals. The object function reflects maintenance cost, cost of loss of production/services, as well as safety costs, and is based on a classical cost-benefit analysis approach where a value of prevented fatality (VPF) is used to weight the importance of safety. However, the rationale for such an approach could be questioned. What is the meaning of such a VPF figure, and is it sufficient to reflect the importance of safety by calculating the expected fatality loss VPF and potential loss of lives (PLL) as being done in the cost-benefit analyses? Should the VPF be the same number for all type of accidents, or should it be increased in case of multiple fatality accidents to reflect gross accident aversion? In this paper, these issues are discussed. We conclude that we have to see beyond the expected values in situations with high safety impacts. A framework is presented which opens up for a broader decision basis, covering considerations on the potential for gross accidents, the type of uncertainties and lack of knowledge of important risk influencing factors. Decisions with a high safety impact are moved from the maintenance department to the 'Safety Board' for a broader discussion. In this way, we avoid that the object function is used in a mechanical way to optimize the maintenance and important safety-related decisions are made implicit and outside the normal arena for safety decisions, e.g. outside the traditional 'Safety Board'. A case study from the Norwegian railways is used to illustrate the discussions.

An approach to maintenance optimization where safety issues are important

Energy Technology Data Exchange (ETDEWEB)

Vatn, Jorn, E-mail: jorn.vatn@ntnu.n [NTNU, Production and Quality Engineering, 7491 Trondheim (Norway); Aven, Terje [University of Stavanger (Norway)

2010-01-15

The starting point for this paper is a traditional approach to maintenance optimization where an object function is used for optimizing maintenance intervals. The object function reflects maintenance cost, cost of loss of production/services, as well as safety costs, and is based on a classical cost-benefit analysis approach where a value of prevented fatality (VPF) is used to weight the importance of safety. However, the rationale for such an approach could be questioned. What is the meaning of such a VPF figure, and is it sufficient to reflect the importance of safety by calculating the expected fatality loss VPF and potential loss of lives (PLL) as being done in the cost-benefit analyses? Should the VPF be the same number for all type of accidents, or should it be increased in case of multiple fatality accidents to reflect gross accident aversion? In this paper, these issues are discussed. We conclude that we have to see beyond the expected values in situations with high safety impacts. A framework is presented which opens up for a broader decision basis, covering considerations on the potential for gross accidents, the type of uncertainties and lack of knowledge of important risk influencing factors. Decisions with a high safety impact are moved from the maintenance department to the 'Safety Board' for a broader discussion. In this way, we avoid that the object function is used in a mechanical way to optimize the maintenance and important safety-related decisions are made implicit and outside the normal arena for safety decisions, e.g. outside the traditional 'Safety Board'. A case study from the Norwegian railways is used to illustrate the discussions.

Questions on maintenance of ecological safety in space of the CIS

International Nuclear Information System (INIS)

Maharramov, A.A.

2009-01-01

Disintegration of the USSR has led to disintegration uniform economic and legal space and it has led to occurrence of some problems in ecological sphere. In given article it is shown some directions of maintenance of ecological safety, agreements on this sphere and organizational mechanisms, forms of mutual relations of the CIS countries in this sphere. At the end it is shownthe basic directions on maintenance of ecological safety in framework of CIS and elements of development of mutual relations of the CIS countries

Safety of nuclear operation and maintenance

International Nuclear Information System (INIS)

Mori, M.; Nitta, T.; Sakai, K.

1994-01-01

The Kansai Electric Power Co. Inc.(Kansai EPC) aims to pursue a high quality and highly reliable operation in nuclear power generation in order to ensure safety by reducing the risk of accidents and win the confidence from the society and the public. It is emphasised that in order to realize this aim manufacturers and contractors cooperate with each other in performing high quality maintenance through plant lifetime maintenance system. TQC (Total Quality Control) activity enhances the motivation for each individual to have a quality-oriented mind and cultivate the safety culture. Under the lifetime employment practice, Kansai EPC and maintenance contractors can conduct systematic education and training, and the Maintenance Training Center helps to make it effective. 6 figs

Application of quality assurance program to safety related aging equipment or components

International Nuclear Information System (INIS)

Papaiya, N.C.

1990-01-01

This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

Influence of Non-safety Important Component on Maintenance Rule

International Nuclear Information System (INIS)

Ju, Tae Young; Kim, Wang Bae

2016-01-01

The Maintenance Rule (MR) programs in KHNP have been implemented since Jan 2009. KHNP is currently developing MR program for new built plant which has been constructed from December 2011. It is required to utilize plant-specific probabilistic safety analysis (PSA) result as risk significant criteria to determine which components are significantly important to safety. The criteria consist of three PSA risk values which are risk reduction worth (RRW), risk achievement worth (RAW) and core damage frequency (CDF) contribution. Most safety related components are classified as high risk significant, and non-safety related components as low safety significant in MR program. This paper presents the influence of the non-safety related component which has high PSA risk value on MR program of new built plant. It is considered that safety related system has at least one or more safety functions and some non-safety functions, but non-safety system doesn't have any safety function. The safety functions are defined as three functions which are required to maintain 1) integrity of reactor coolant pressure boundary, 2) capability to shut-down the reactor and maintain it in a safe shutdown, and 3) capability to prevent or mitigate the accident that could result in potential offsite exposure. The Maintenance Rule program is developed based on PSA result. Safety functions have high risk value in PSA program and considered HSS function in MR program. On the contrary, non-safety functions are generally has low risk value in PSA program and they are determined as LSS function in MR program. The AAC DG and its supporting systems are designed as non-safety systems which mean they don't have any safety function. But, AAC DG is treated as an important measure to mitigate accident in PSA program. It is determined as HSS function in MR program because it has high risk value in PSA program. AAC DG supporting systems does not have high risk value in operating plant's PSA program

Allowed outage time for test and maintenance - Optimization of safety

International Nuclear Information System (INIS)

Cepin, M.; Mavko, B.

1997-01-01

The main objective of the project is the development and application of methodologies for improvement and optimization of test and maintenance activities for safety related equipment in NPPs on basis of their enhanced safety. The probabilistic safety assessment serves as a base, which does not mean the replacement of the deterministic analyses but the consideration of probabilistic safety assessment results as complement to deterministic results. 15 refs, 2 figs

Maintenance as a safety issue.

Science.gov (United States)

White, Jim

2008-11-01

Because safety is related to electrical power systems maintenance, it seems reasonable to assume there could be legal issues if maintenance is not performed. OSHA has not yet taken the stand that not performing maintenance as required by the manufacturer, NFPA 70B, or ANSI/NETA MTS-07 constitutes a willful violation. OSHA defines a willful citation as one where: "the employer knowingly commits with plain indifference to the law. The employer either knows that what he or she is doing constitutes a violation, or is aware that a hazardous condition existed and made no reasonable effort to eliminate it". However, NFPA 70E 2009 requires this maintenance, and OSHA has stated on its Web site that NFPA 70E is "a guide for meeting the requirements of the OSHA electrical regulations". In addition, federal courts have found that NFPA 70E is "standard industry practice." Once a company receives and accepts a willful citation, especially if received as the result of an accident investigation, its worker's compensation protection no longer shields it. One definition given by a trial attorney for a willful citation was that it is equal to negligent behavior. Be smart: Maintain that equipment and save yourself major problems, including unscheduled shutdowns and possible litigation.

49 CFR 214.507 - Required safety equipment for new on-track roadway maintenance machines.

Science.gov (United States)

2010-10-01

... maintenance machines. 214.507 Section 214.507 Transportation Other Regulations Relating to Transportation... Roadway Maintenance Machines and Hi-Rail Vehicles § 214.507 Required safety equipment for new on-track roadway maintenance machines. (a) Each new on-track roadway maintenance machine shall be equipped with: (1...

Technology Trend in the Maintenance of Nuclear Power Plants

International Nuclear Information System (INIS)

Yoon, Kyungsup; Lee, Unjang

2014-01-01

In this paper, overall technology evolution is reviewed and the improvements in the plant safety, reliability and productivity are described. And the issue and some recommendation for better maintenance of Korean nuclear power plants are presented as the interim study results on the 'Management and Regulatory Policy for the Nuclear Power Plant Maintenance and Equipment Reliability' under the agreement with the Nuclear Safety and Security Commission. The future trend in the maintenance technologies is also covered. Maintenance is the essential element for the enhancement of plant safety, reliability and economics and also for public safety. Therefore the regulator's involvements and the utility's active participation is inevitable for the better maintenance. For the better sustainability of our nuclear power plants the followings are recommended. ·Establishment of the good maintenance program and continuous improvement. ·Application of OLM on the safety related and non-safety related components by step-by-step approach. ·Improvement PRA technology for the accurate and reliable risk analysis. ·Continuous training and cultivation for the qualified maintenance personnel

Technology Trend in the Maintenance of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Yoon, Kyungsup; Lee, Unjang [CTO and CEO, Seoul (Korea, Republic of)

2014-05-15

In this paper, overall technology evolution is reviewed and the improvements in the plant safety, reliability and productivity are described. And the issue and some recommendation for better maintenance of Korean nuclear power plants are presented as the interim study results on the 'Management and Regulatory Policy for the Nuclear Power Plant Maintenance and Equipment Reliability' under the agreement with the Nuclear Safety and Security Commission. The future trend in the maintenance technologies is also covered. Maintenance is the essential element for the enhancement of plant safety, reliability and economics and also for public safety. Therefore the regulator's involvements and the utility's active participation is inevitable for the better maintenance. For the better sustainability of our nuclear power plants the followings are recommended. ·Establishment of the good maintenance program and continuous improvement. ·Application of OLM on the safety related and non-safety related components by step-by-step approach. ·Improvement PRA technology for the accurate and reliable risk analysis. ·Continuous training and cultivation for the qualified maintenance personnel.

A cost summary applicable to seismic construction and maintenance of nuclear safety related piping

International Nuclear Information System (INIS)

Stevenson, J.D.

1995-01-01

This paper presents a summary of costs applicable to nuclear power plant piping for an earthquake defined as 0.2 SSE-PGA as a function of three eras of initial construction: 1967--1974, 1974--1981 and 1981--1990. Costs have been presented for both new construction and maintenance in operating plants using both the original PSAR-FSAR design criteria and current SRP requirements. It is recommended that the cost information contained in this report be considered in evaluating the cost benefit relationships associated with current and proposed future changes in seismic design procedures applicable to safety-related piping systems

Optimization of maintenance periodicity of complex of NPP safety systems

International Nuclear Information System (INIS)

Kolykhanov, V.; Skalozubov, V.; Kovrigkin, Y.

2006-01-01

The analysis of the positive and negative aspects connected to maintenance of the safety systems equipment which basically is in a standby state is executed. Tests of systems provide elimination of the latent failures and raise their reliability. Poor quality of carrying out the tests can be a source of the subsequent failures. Therefore excess frequency of tests can result in reducing reliability of safety systems. The method of optimization of maintenance periodicity of the equipment taking into account factors of its reliability and restoration procedures quality is submitted. The unavailability factor is used as a criterion of optimization of maintenance periodicity. It is offered to use parameters of reliability of the equipment and each of safety systems of NPPs received at developing PSA. And it is offered to carry out the concordance of maintenance periodicity of systems within the NPP maintenance program taking into account a significance factor of the system received on the basis of the contribution of system in CDF. Basing on the submitted method the small computer code is developed. This code allows to calculate reliability factors of a separate safety system and to determine optimum maintenance periodicity of its equipment. Optimization of maintenance periodicity of a complex of safety systems is stipulated also. As an example results of optimization of maintenance periodicity at Zaporizhzhya NPP are presented. (author)

Some aspects related to the management of maintenance for a TRIGA research reactor In Romania

International Nuclear Information System (INIS)

Vieru, G.

2003-01-01

Safety management for a nuclear research reactor involves 'good dependability management' of operations activities, such as: reliability, availability, maintainability and maintenance support. In order to evaluate the safety management aspects intended to be applied by research reactor management, the performance dependability indicators and their impact on reactor availability and reactor safety have to be established. The document ISO 9000-4/IEC 300-1 'Dependability Management' (1995), describes five internationally agreed indicators of reactor equipment dependability. Each of them can be used for corrective maintenance or for preventive maintenance, such as: I 1 - equipment Maintenance Frequency; I 2 - equipment Maintenance Effort; I 3 - equipment Maintenance Downtime Factor; I 4 - equipment Maintenance Contribution to the System Function Downtime Factor; I 5 - equipment Maintenance Contribution to the reactor Capability Loss Factor. This paper presents an evaluation of those 5 mentioned indicators with reference to the primary circuit of the INR's TRIGA research reactor and conclusion. The analyzed period was between 1994- 1999. It is to be noted that this type of analysis is performed for the first time for a research reactor. (author)

Safety instruction for execution tasks involving ionizing radiations

International Nuclear Information System (INIS)

Fonseca, G.

1985-01-01

Basic directives are presented allow operations with ionizing radiations in industrial areas with high levels of safety. Contractual, technical, operational and administrative criteria are established for the safe performance of x-rays and gamographies and the use of fixed radiation based equipment (indicators of level, density, flow, etc) as well as precautions to be taken during project, procurement, transportation, assembly and maintenance of such equipment. Finally procedures are suggested for emergencies involving radioactive sources. (author)

Safety-related control air systems

International Nuclear Information System (INIS)

Anon.

1977-01-01

This Standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This Standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this Standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

Study on application of safety checklist in preventive maintenance activities

International Nuclear Information System (INIS)

Shi Jin; Chen Song; Liu Jingquan

2013-01-01

The paper describes the principles and the characteristics of safety checklist as a risk evaluation method. Examples of application of safety checklists to preventive maintenance activities such as criteria comparison and checkup items in place in nuclear power plants are illustrated in details with issues appeared in the checklist establishment. Checklist has a good application in the RCM analysis or in the actual preventive maintenance program for Chashma Nuclear Power Plant indicated by concrete instances. In the light of safety checklist which is used to sustain preventive maintenance as a simple and applicable risk analysis approach, we can get deep knowledge of risks of nuclear power plant to perfect preventive maintenance activities. (authors)

Environmental Management Model for Road Maintenance Operation Involving Community Participation

Science.gov (United States)

Triyono, A. R. H.; Setyawan, A.; Sobriyah; Setiono, P.

2017-07-01

Public expectations of Central Java, which is very high on demand fulfillment, especially road infrastructure as outlined in the number of complaints and community expectations tweeter, Short Mail Massage (SMS), e-mail and public reports from various media, Highways Department of Central Java province requires development model of environmental management in the implementation of a routine way by involving the community in order to fulfill the conditions of a representative, may serve road users safely and comfortably. This study used survey method with SEM analysis and SWOT with Latent Independent Variable (X), namely; Public Participation in the regulation, development, construction and supervision of road (PSM); Public behavior in the utilization of the road (PMJ) Provincial Road Service (PJP); Safety in the Provincial Road (KJP); Integrated Management System (SMT) and latent dependent variable (Y) routine maintenance of the provincial road that is integrated with the environmental management system and involve the participation of the community (MML). The result showed the implementation of routine maintenance of road conditions in Central Java province has yet to implement an environmental management by involving the community; Therefore developed environmental management model with the results of H1: Community Participation (PSM) has positive influence on the Model of Environmental Management (MML); H2: Behavior Society in Jalan Utilization (PMJ) positive effect on Model Environmental Management (MML); H3: Provincial Road Service (PJP) positive effect on Model Environmental Management (MML); H4: Safety in the Provincial Road (KJP) positive effect on Model Environmental Management (MML); H5: Integrated Management System (SMT) has positive influence on the Model of Environmental Management (MML). From the analysis obtained formulation model describing the relationship / influence of the independent variables PSM, PMJ, PJP, KJP, and SMT on the dependent variable

Are cognitive "insomnia" processes involved in the development and maintenance of delayed sleep wake phase disorder?

Science.gov (United States)

Richardson, Cele E; Gradisar, Michael; Barbero, Sebastian C

2016-04-01

Although individuals with delayed sleep wake phase disorder (DSWPD) and chronic insomnia disorder (CID) share many of the same phenomenological experiences, theories relating to the development and maintenance of these disorders are distinct in focus. Unlike CID, theory relating to DSWPD is primarily physiologically based and assumes almost no cognitive pathway. However, recent research findings suggest that individuals with DSWPD also display many of the sleep-disordered cognitive processes that were previously assumed to be unique to the insomnia experience. As such, this review aims to summarise current research findings to address the question "Could cognitive processes be involved in the development and maintenance of DSWPD?" In particular, the presence of cognitive and physiological pre-sleep arousal, sleep-related attentional bias, distorted perception of sleep and daytime functioning, dysfunctional beliefs and safety behaviours will be investigated. As this emerging area of research requires a stronger evidence base, we highlight suggestions for future investigation and provide preliminary practice points for clinicians assessing and treating "insomnia" in patients with DSWPD. Copyright © 2015 Elsevier Ltd. All rights reserved.

Regulatory requirements related to maintenance and compliance monitoring

International Nuclear Information System (INIS)

Ling, A.K.H.

1997-01-01

The maintenance related regulatory requirements are identified in the regulatory documents and licence conditions. Licensee complies with these requirements by operating the nuclear power plant within the safe operating envelope as given in the operating policies and principles and do maintenance according to approved procedures and/or work plans. Safety systems are regularly tested. AECB project officers review and check to ensure that the licensee operates the nuclear power plant in accordance with the regulatory requirements and licence conditions. (author). 6 tabs

Manual on quality assurance for computer software related to the safety of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

Criteria adopted by the Argentine Nuclear Regulatory Authority for assessing digital systems related to safety

International Nuclear Information System (INIS)

Terrado, Carlos A.; Chiossi, Carlos E.; Felizia, Eduardo R.; Roca, Jose L.; Sajaroff, Pedro M.

2004-01-01

Following the technological evolution in Instrumentation and Control (I and C) design, analog components are replaced by digital in almost every industry. Due to growing challenges of obsolescence and increasing maintenance costs, licensees of nuclear and radioactive installations are increasingly upgrading or replacing their existing I and C analog systems and components. In existing installations, this involves analog to digital replacements. In new installations design, the use of digital I and C systems is being considered from the very beginning, becoming a good alternative, even in safety applications. Up to now, in Argentina, there is no specific rules for safety-related digital systems, every safety system, analog or digital, must comply with the same generic regulations. The Nuclear Regulatory Authority is now developing criteria to assess digital systems related to safety in nuclear and radioactive installations. In this paper some of those criteria, based on local research and the recognized state of the art, are explained. From a regulatory point of view, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include new failure modes, the potential for common-cause failure of redundant components, electromagnetic interference (EMI), software verification and validation, configuration management and a more exhaustive quality assurance system. The mentioned criteria comprehend the design, operation, maintenance and acquisition of digital systems and components important to safety. The main topics covered are: requirements specifications for digital systems, planning and documentation for digital system development, effectiveness of a digital system, commercial off the shelf (COTS) treatment and considerations involving tools for software development. (author)

Design of an artificial intelligence system for safety function maintenance

International Nuclear Information System (INIS)

Sharma, D.D.; Miller, D.W.; Chandrasekaran, B.

1985-01-01

The safety function (SF) maintenance concept provides a systematic approach to mitigate the consequences of an unforeseen event. Safety functions are a set of actions for mitigating or limiting consequences of a safety threatening event. The current approach to SF maintenance of selecting a success path (SP) from a library of predefined SPs is inadequate because it includes only anticipated modes of challenging an SF. To cover all possible modes of challenging an SF, the library of success paths would be extremely large and difficult to implement on any existing computer. In this paper the authors describe a method based on artificial intelligence (AI) theory of planning to synthesize an SP using available resources to satisfy a hierarchy of safety goals. The method has been applied to SF maintenance of a boiling water reactor (BWR) using data from the Perry nuclear power plant

Engineering systems reliability, safety, and maintenance an integrated approach

CERN Document Server

Dhillon, B S

2017-01-01

Today, engineering systems are an important element of the world economy and each year billions of dollars are spent to develop, manufacture, operate, and maintain various types of engineering systems around the globe. Many of these systems are highly sophisticated and contain millions of parts. For example, a Boeing jumbo 747 is made up of approximately 4.5 million parts including fasteners. Needless to say, reliability, safety, and maintenance of systems such as this have become more important than ever before.　 Global competition and other factors are forcing manufacturers to produce highly reliable, safe, and maintainable engineering products. Therefore, there is a definite need for the reliability, safety, and maintenance professionals to work closely during design and other phases. Engineering Systems Reliability, Safety, and Maintenance: An Integrated Approach eliminates the need to consult many different and diverse sources in the hunt for the information required to design better engineering syste...

MOSEG code for safety oriented maintenance management Safety of management of maintenance oriented by MOSEG code; Codigo MOSEG para la gestion de mantenimiento orientada a la seguridad

Energy Technology Data Exchange (ETDEWEB)

Torres Valle, Antonio [Instituto Superior de Tecnologias y Ciencias Aplicadas, La Habana (Cuba). Dept. Ingenieria Nuclear]. E-mail: atorres@fctn.isctn.edu.cu; Rivero Oliva, Jose de Jesus [Centro de Gestion de la Informacion y Desarrollo de la Energia (CUBAENERGIA) (Cuba)]. E-mail: jose@cubaenergia.cu

2005-07-01

Full text: One of the main reasons that makes maintenance contribute highly when facing safety problems and facilities availability is the lack of maintenance management systems to solve these fields in a balanced way. Their main setbacks are shown in this paper. It briefly describes the development of an integrating algorithm for a safety and availability-oriented maintenance management by virtue of the MOSEG Win 1.0 code. (author)

Examining the Relationship Between Passenger Airline Aircraft Maintenance Outsourcing and Aircraft Safety

Science.gov (United States)

Monaghan, Kari L.

The problem addressed was the concern for aircraft safety rates as they relate to the rate of maintenance outsourcing. Data gathered from 14 passenger airlines: AirTran, Alaska, America West, American, Continental, Delta, Frontier, Hawaiian, JetBlue, Midwest, Northwest, Southwest, United, and USAir covered the years 1996 through 2008. A quantitative correlational design, utilizing Pearson's correlation coefficient, and the coefficient of determination were used in the present study to measure the correlation between variables. Elements of passenger airline aircraft maintenance outsourcing and aircraft accidents, incidents, and pilot deviations within domestic passenger airline operations were analyzed, examined, and evaluated. Rates of maintenance outsourcing were analyzed to determine the association with accident, incident, and pilot deviation rates. Maintenance outsourcing rates used in the evaluation were the yearly dollar expenditure of passenger airlines for aircraft maintenance outsourcing as they relate to the total airline aircraft maintenance expenditures. Aircraft accident, incident, and pilot deviation rates used in the evaluation were the yearly number of accidents, incidents, and pilot deviations per miles flown. The Pearson r-values were calculated to measure the linear relationship strength between the variables. There were no statistically significant correlation findings for accidents, r(174)=0.065, p=0.393, and incidents, r(174)=0.020, p=0.793. However, there was a statistically significant correlation for pilot deviation rates, r(174)=0.204, p=0.007 thus indicating a statistically significant correlation between maintenance outsourcing rates and pilot deviation rates. The calculated R square value of 0.042 represents the variance that can be accounted for in aircraft pilot deviation rates by examining the variance in aircraft maintenance outsourcing rates; accordingly, 95.8% of the variance is unexplained. Suggestions for future research include

Review of safety reports involving electronic flight bags

Science.gov (United States)

2009-04-27

Electronic Flight Bags (EFBs) are a relatively new device used by pilots. Even so, 37 safety-related events involving EFBs were identified from the public online Aviation Safety Reporting System (ASRS) database as of June 2008. In addition, two accid...

Safety Climate, Perceived Risk, and Involvement in Safety Management

OpenAIRE

Kouabenan , Dongo Rémi; Ngueutsa , Robert ,; Safiétou , Mbaye

2015-01-01

International audience; This article examines the relationship between safety climate, risk perception and involvement in safety management by first-line managers (FLM). Sixty-three FLMs from two French nuclear plants answered a questionnaire measuring perceived workplace safety climate, perceived risk, and involvement in safety management. We hypothesized that a positive perception of safety climate would promote substantial involvement in safety management, and that this effect would be str...

Safety-related control air systems - approved 1977

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

Analysis of trends in aviation maintenance risk: An empirical approach

International Nuclear Information System (INIS)

Marais, Karen B.; Robichaud, Matthew R.

2012-01-01

Safety is paramount in the airline industry. A significant amount of effort has been devoted to reducing mechanical failures and pilot errors. Recently, more attention has been devoted to the contribution of maintenance to accidents and incidents. This study investigates and quantifies the contribution of maintenance, both in terms of frequency and severity, to passenger airline risk by analyzing three different sources of data from 1999 to 2008: 769 NTSB accident reports, 3242 FAA incident reports, and 7478 FAA records of fines and other legal actions taken against airlines and associated organizations. We analyze several safety related metrics and develop an aviation maintenance risk scorecard that collects these metrics to synthesize a comprehensive track record of maintenance contribution to airline accidents and incidents. We found for example that maintenance-related accidents are approximately 6.5 times more likely to be fatal than accidents in general, and that when fatalities do occur, maintenance accidents result in approximately 3.6 times more fatalities on average. Our analysis of accident trends indicates that this contribution to accident risk has remained fairly constant over the past decade. Our analysis of incidents and FAA fines and legal actions also revealed similar trends. We found that at least 10% of incidents involving mechanical failures such as ruptured hydraulic lines can be attributed to maintenance, suggesting that there may be issues surrounding both the design of and compliance with maintenance plans. Similarly 36% of FAA fines and legal actions involve inadequate maintenance, with recent years showing a decline to about 20%, which may be a reflection of improved maintenance practices. Our results can aid industry and government in focusing resources to continue improving aviation safety.

Advancements in the design of safety-related systems and components of the MARS nuclear plant

International Nuclear Information System (INIS)

Caira, M.; Caruso, G.; Naviglio, A.; Sorabella, L.; Farello, C.E.

1992-01-01

In the paper, the advancements in the design of safety-related systems and components of the MARS nuclear plant, equipped with a 600 MW th PWR, are described. These advancements are due to the special safety features of this plant, which relies completely on inherent and passive safety. In particular, the new steps of the design of the innovative, completely passive, and with an unlimited autonomy Emergency core Cooling System are described, together with the characteristics of the last version of the steam generator, developed in a new design involving disconnecting components, for a fast erection and an easy maintenance. (author)

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

1997-01-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

Energy Technology Data Exchange (ETDEWEB)

Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

1997-07-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

Safety and maintenance engineering: A compilation

Science.gov (United States)

1974-01-01

A compilation is presented for the dissemination of information on technological developments which have potential utility outside the aerospace and nuclear communities. Safety of personnel engaged in the handling of hazardous materials and equipment, protection of equipment from fire, high wind, or careless handling by personnel, and techniques for the maintenance of operating equipment are reported.

Operations and maintenance - Safety challenges

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Liv [Oljedirektoratet, Stavanger (Norway)

1999-07-01

With the unsteady oil prices and the possible consequences of the deregulation of the European energy markets one may expect further optimization of operating and maintenance costs. One may also expect extended use of various risk-based optimization techniques such as RCM (Reliability Centered Maintenance) and RBI (Risk Based Inspection). This presentation addresses the need for further research and development in this area. Maintenance work is necessary, but it can also create risk. The accident statistics show many examples of this. The Norwegian petroleum industry's ability to learn from previous incidents is questioned. Maintenance staff must be well trained and possess the necessary routines. Technical documentation must be updated. Uncertainties with respect to future oil and gas prices combined with the effect of the deregulation of the European energy markets will lead to even more focus on cost-effective operations and maintenance. The need for long-term research and development is stressed. Risk based techniques such as RCM and RBI are extensively used in the defence industry and the nuclear industry, but applying them to the petroleum industry requires improved risk models. Ageing effects such as corrosion, erosion, fatigue etc. can be expected, but the capability to predict, monitor and control them should be improved. At present, not even the most sophisticated risk analysis can model ageing effects. The importance of efficient use of information technology (IT) is stressed. Improving the product quality and safety often requires new technology and so research and development is important. Close cooperation with the industry is required.

Risk-Based Predictive Maintenance for Safety-Critical Systems by Using Probabilistic Inference

Directory of Open Access Journals (Sweden)

Tianhua Xu

2013-01-01

Full Text Available Risk-based maintenance (RBM aims to improve maintenance planning and decision making by reducing the probability and consequences of failure of equipment. A new predictive maintenance strategy that integrates dynamic evolution model and risk assessment is proposed which can be used to calculate the optimal maintenance time with minimal cost and safety constraints. The dynamic evolution model provides qualified risks by using probabilistic inference with bucket elimination and gives the prospective degradation trend of a complex system. Based on the degradation trend, an optimal maintenance time can be determined by minimizing the expected maintenance cost per time unit. The effectiveness of the proposed method is validated and demonstrated by a collision accident of high-speed trains with obstacles in the presence of safety and cost constrains.

Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

International Nuclear Information System (INIS)

Husseiny, A.A.; Sabri, Z.A.; Turnage, J.J.

1980-04-01

The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that would allow identification of principal types of problems which are associated with the performance of M and T tasks in LWR power plants. Frequencies of occurrence of events and their general endemic nature were analyzed using data clustering and pattern recognition techniques, as well as chi-square analyses for sparse contingency tables. The results of these analyses identified seven major categories of M and T error modes which were related to individual facilities and reactor type. Data review indicated that few M and T problems were directly related to procedural inadequacies, with the majority of events being attributable to human error

The advantages of reliability centered maintenance for standby safety systems

International Nuclear Information System (INIS)

Dam, R.F.; Ayazzudin, S.; Nickerson, J.H.; DeLong, A.I.

2002-01-01

Full text: On standby safety systems, nuclear plants have to balance the requirements of demonstrating the reliability of each system, while maintaining the system and plant availability. With the goal of demonstrating statistical reliability, these systems have extensive testing programs, which often makes the system unavailable and this can impact the plant capacity. The inputs to the process are often safety and regulatory related, resulting in programs that provide a high level of scrutiny on the systems being considered. In such cases, the value of the application of a maintenance optimization strategy, such as Reliability Centered Maintenance (RCM), is questioned. Part of the question stems from the use of the word 'Reliability' in RCM, which implies a level of redundancy when applied to a system maintenance program driven by reliability requirements. A deeper look at the RCM process, however, shows that RCM has the goal of ensuring that the system operates 'reliably' through the application of an integrated maintenance strategy. This is a subtle, but important distinction. Although the system reliability requirements are an important part of the strategy evaluation, RCM provides a broader context where testing is only one part of an overall strategy focused on ensuring that component function is maintained through a combination of monitoring technologies (including testing), predictive techniques, and intrusive maintenance strategies. Each strategy is targeted to identify known component degradation mechanisms. The conclusion is that a maintenance program driven by reliability requirements will tend to have testing defined at a frequency intended to support the needed statistics. The testing demonstrates that the desired function is available today. Maintenance driven by functional requirements and known failure causes, as developed through an RCM assessment, will have frequencies tied to industry experience with components and rely on a higher degree of

Safety constraints applied to an adaptive Bayesian condition-based maintenance optimization model

International Nuclear Information System (INIS)

Flage, Roger; Coit, David W.; Luxhøj, James T.; Aven, Terje

2012-01-01

A model is described that determines an optimal inspection and maintenance scheme for a deteriorating unit with a stochastic degradation process with independent and stationary increments and for which the parameters are uncertain. This model and resulting maintenance plans offers some distinct benefits compared to prior research because the uncertainty of the degradation process is accommodated by a Bayesian approach and two new safety constraints have been applied to the problem: (1) with a given subjective probability (degree of belief), the limiting relative frequency of one or more failures during a fixed time interval is bounded; or (2) the subjective probability of one or more failures during a fixed time interval is bounded. In the model, the parameter(s) of a condition-based inspection scheduling function and a preventive replacement threshold are jointly optimized upon each replacement and inspection such as to minimize the expected long run cost per unit of time, but also considering one of the specified safety constraints. A numerical example is included to illustrate the effect of imposing each of the two different safety constraints.

Machine-related injuries in the US mining industry and priorities for safety research.

Science.gov (United States)

Ruff, Todd; Coleman, Patrick; Martini, Laura

2011-03-01

Researchers at the National Institute for Occupational Safety and Health studied mining accidents that involved a worker entangled in, struck by, or in contact with machinery or equipment in motion. The motivation for this study came from the large number of severe accidents, i.e. accidents resulting in a fatality or permanent disability, that are occurring despite available interventions. Accident descriptions were taken from an accident database maintained by the United States Department of Labor, Mine Safety and Health Administration, and 562 accidents that occurred during 2000-2007 fit the search criteria. Machine-related accidents accounted for 41% of all severe accidents in the mining industry during this period. Machinery most often involved in these accidents included conveyors, rock bolting machines, milling machines and haulage equipment such as trucks and loaders. The most common activities associated with these accidents were operation of the machine and maintenance and repair. The current methods to safeguard workers near machinery include mechanical guarding around moving components, lockout/tagout of machine power during maintenance and backup alarms for mobile equipment. To decrease accidents further, researchers recommend additional efforts in the development of new control technologies, training materials and dissemination of information on best practices.

Maintenance strategies and safety on a deregulated market. Mapping of changes in maintenance strategies and their possible consequences

International Nuclear Information System (INIS)

Kecklund, Lena

2004-11-01

The overall purpose of the project was to make a survey of the changes in the Swedish nuclear power plants over the last five years. There is a risk that nuclear power companies after a deregulation will focus especially on reducing operation and maintenance costs and that the changes could have a negative effect on the reactor safety. The task has involved summarising the actual changes, describing the present situation, the need for future development and the differences between the plants as well as identifying possible reactor safety related risks. The survey has been carried out in a broad perspective, studying the changes in equipment, maintenance strategies and the work situation of the staff. Three case studies were carried out at the Swedish nuclear power plants. Documentation from the companies has been analysed and a selection of in total 27 'informed' employees in different positions have been interviewed in total. The project also included a fourth case study concerning railway traffic. This branch of business is interesting because of its longer experience on a deregulated and competitive market. Conclusions concerning the companies individually as well as similarities and differences between them are presented in this report. Results: There have been more changes both in strategy and organisation in the last five years than during the preceding 5-10-year-period and the pace has been relatively rapid. The deregulation of the electricity market was implemented January 1997 and became the main motive force for the changes. The staffing has been reduced or unchanged and the work demands have increased. The maintenance skills have been redistributed within the organisation. New methods and equipment, i.e. RCM, and programmable systems make increased demands for analytical and theoretical competence. In the short term, job satisfaction and motivation have in some cases been negatively influenced by the new organisation forms, according to several of the

Risk based maintenance to increase safety and decrease costs

International Nuclear Information System (INIS)

Phillips, J.H.

2000-01-01

Risk-Based techniques have been developed for commercial nuclear power plants for the last eight years by a team working through the ASME Center for Research and Technology Development (CRTD). System boundaries and success criteria is defined using the Probabilistic Risk Analysis or Probabilistic Safety Analysis developed to meet the Individual Plant Evaluation. Final ranking of components is by a plant expert panel similar to the one developed for the Maintenance Rule. Components are identified as being high risk-significant or low risk-significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of plants. Results from the first risk-based inspection pilot plant indicates safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. Pilot studies on risk-based testing indicate that about 60% of pumps and 25 to 30% of valves in plants are high safety-significant The reduction in inspection and testing reduces the person-rem exposure and resulting in further increases in safety. These techniques have been documented in publications by the ASME CRTD which are referenced. (author)

Comparison of two approaches for establishing performance criteria related to Maintenance Rule

International Nuclear Information System (INIS)

Jerng, Dong-Wook; Kim, Man Cheol

2015-01-01

Probabilistic safety assessment (PSA) serves as a tool for systemically analyzing the safety of nuclear power plants. This paper explains and compares two approaches for the establishment of performance criteria related to the Maintenance Rule: (1) the individual reliability-based approach, and (2) the PSA importance measure-based approach. Different characteristics of the two approaches were compared in a qualitative manner, while a quantitative comparison was performed through application of the two approaches to a nuclear power plant. It was observed that the individual reliability-based approach resulted in more conservative performance criteria, compared to the PSA importance measure-based approach. It is thus expected that the PSA importance measure-based approach will allow for more flexible maintenance policy under conditions of limited resources, while providing for a macroscopic view of overall plant safety. Based on insights derived through this analysis, we emphasize the importance of a balance between reliability and safety significance, and propose a balance measure accordingly. The conclusions of this analysis are likely to be applicable to other types of nuclear power plants. (author)

JRR-3 maintenance program utilizing accumulated maintenance data

International Nuclear Information System (INIS)

Izumo, Hironobu; Kato, Tomoaki; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji

2007-07-01

JRR-3(Japan Research Reactor No.3) has been operated for more than 15 years after the modification, without significant troubles by carrying out maintenance such as the preventive maintenance (mainly time-based maintenance) for the safety-grade equipments and the breakdown maintenance for the non-safety-grade equipments. Unscheduled shutdowns causes by aged non-safety-grade equipments have been increasing, and the resources such as budgets have been decreasing year by year. In this situation, JRR-3 maintenance program was reviewed about safety, reliability and economic efficiency. This report offers the policy of the maintenance review and the future direction of maintenance programs. (author)

Surry Power Station, Units 1 and 2. Annual operating report: January--December 1977, volume I--introduction, summary of operating experience; changes, tests, experiments, and safety-related maintenance; effluent releases; data tabulations

International Nuclear Information System (INIS)

1978-01-01

A chronological operating sequence including shutdowns and occurrences during the year which required load reductions or resulted in non-load related incidents is given. Data are presented concerning plant and procedure changes, tests, experiments, safety related maintenance, effluent releases and personnel radiation exposures

Prediction of the safety level in a tritium processing facility through predictive maintenance

International Nuclear Information System (INIS)

Anghel, Vasile

2007-01-01

Full text: The safety level of a nuclear facility for personnel and environment depends generally on the technological process quality of operation and maintenance and particularly on several technical, technological, economic, and human factors. The role of maintenance is fundamental because it is determined by all the technical, economic and human elements as parts of an integrated system dominated by an important feedback from upstream activities which eventually define the life cycle of the nuclear facility considered. In the maintenance activity as in case of any dynamic area, new elements may appear which, sometimes, require new methods of approach. For considered installation which is a Nuclear Detritiation Plant (NDP) operating as a division of the National Research and Development Institute for Cryogenics and Isotopic Technologies - ICSI, Rm.Valcea, in order to ensure a safety level in operation as high as possible through predictive maintenance, the fuzzy theory and software LabVIEW were applied. The final aim is to achieve the best practices in maintenance of the tritium processing plant. The safety in operation of the NDP equipment and installations is directly related with the maintenance achieved by improving the reliability through methods and advanced techniques. The maintainability is the capacity of an industrial product, in given utilization conditions, to be maintained and re-established up to achieve specified functions. In general the reliability on some interval is a probability conditioned by good operation at the beginning of the interval, representing thus the probability as the element which operated at t = t 0 to operate in the interval (t 0 , t 1 ). The failure is a fundamental event in the reliability theory. Breakdown (failure) is understood as the stop process of the function required from a given product, the failure representing the effect upon that process. The operation of a product on a certain duration can be a 'success' or a

Aviation safety and maintenance under major organizational changes, investigating non-existing accidents.

Science.gov (United States)

Herrera, Ivonne A; Nordskag, Arve O; Myhre, Grete; Halvorsen, Kåre

2009-11-01

The objective of this paper is to discuss the following questions: Do concurrent organizational changes have a direct impact on aviation maintenance and safety, if so, how can this be measured? These questions were part of the investigation carried out by the Accident Investigation Board, Norway (AIBN). The AIBN investigated whether Norwegian aviation safety had been affected due to major organizational changes between 2000 and 2004. The main concern was the reduction in safety margins and its consequences. This paper presents a summary of the techniques used and explains how they were applied in three airlines and by two offshore helicopter operators. The paper also discusses the development of safety related indicators in the aviation industry. In addition, there is a summary of the lessons learned and safety recommendations. The Norwegian Ministry of Transport has required all players in the aviation industry to follow up the findings and recommendations of the AIBN study.

Status of Technical Requirements Development for Maintenance Effectiveness Management

International Nuclear Information System (INIS)

Ahn, Sang Kyu; Kim, Yun Il; Lee, Chang Ju; Chang, Gun Hyun

2012-01-01

It is well known that proper maintenance at nuclear power plant is essential to plant safety and that there is a clear link between effective maintenance and safety as it relates to such factors as the number of transients and challenges to safety systems and the associated need for operability, availability, and reliability of safety equipment. Good maintenance is also important in providing assurance that failures of non-safety related structures, systems, and components (SSCs) that could initiate, adversely affect, or mitigate a transient or an accident are also minimized. Maintenance is also important to ensure that design assumptions and margins in the original design basis are maintained and are not degraded to an unacceptable level. Therefore, good maintenance practice at nuclear power plants is of utmost importance in protecting public health and safety. This paper introduces the status of the development of regulatory technical requirements (Drafts) for utility's management of maintenance effectiveness. The process of Maintenance Effectiveness Management is shown in Figure 1

Integrating Safety in the Aviation System: Interdepartmental Training for Pilots and Maintenance Technicians

Science.gov (United States)

Mattson, Marifran; Petrin, Donald A.; Young, John P.

2001-01-01

The study of human factors has had a decisive impact on the aviation industry. However, the entire aviation system often is not considered in researching, training, and evaluating human factors issues especially with regard to safety. In both conceptual and practical terms, we argue for the proactive management of human error from both an individual and organizational systems perspective. The results of a multidisciplinary research project incorporating survey data from professional pilots and maintenance technicians and an exploratory study integrating students from relevant disciplines are reported. Survey findings suggest that latent safety errors may occur during the maintenance discrepancy reporting process because pilots and maintenance technicians do not effectively interact with one another. The importance of interdepartmental or cross-disciplinary training for decreasing these errors and increasing safety is discussed as a primary implication.

Contribution of maintainability and maintenance to problems of safety evaluation

International Nuclear Information System (INIS)

Adnot, Serge; Meriaux, Pierre.

1977-10-01

A method has been developed for defining the contribution of Maintainability and the Maintenance Studies to Safety evaluation problems. The efficiency of this method is shown and results obtained are given for two theoretical examples approximating reality. For repairable systems, the risk defined according to such given safety criterion, becomes a characteristic of the systems in operation [fr

Control maintenance training program for special safety systems at Bruce B

International Nuclear Information System (INIS)

Reinwald, G.

1997-01-01

It was recognized from the early days of commissioning of Bruce B that Control Maintenance staff would require a level of expertise to be able to maintain Special Safety Systems in proper running order. In the early 80's this was achieved through hands on experience during the original commissioning, troubleshooting and placing of the various systems in service. Control maintenance procedures were developed and implemented as the new systems came available for commissioning, as were operating manuals,training manuals etc. Under the development of the Maintenance Manager, a Conduct of Maintenance section was organized. One of the responsibilities of this section was to develop a series of Maintenance Administrative Procedures (MAPs) that set the standards for maintenance activities including training

Nuclear power plant maintenance optimisation SENUF network activity

International Nuclear Information System (INIS)

Ahlstrand, R.; Bieth, M.; Pla, P.; Rieg, C.; Trampus, P.

2004-01-01

During providing scientific and technical support to TACIS and PHARE nuclear safety programs a large amount of knowledge related to Russian design reactor systems has accumulated and led to creation of a new Network concerning Nuclear Safety in Central and Eastern Europe called ''Safety of Eastern European type Nuclear Facilities'' (SENUF). SENUF contributes to bring together all stakeholders of TACIS and PHARE: beneficiaries, end users, Eastern und Western nuclear industries, and thus, to favour fruitful technical exchanges and feedback of experience. At present the main focus of SENUF is the nuclear power plant maintenance as substantial element of plant operational safety as well as life management. A Working Group has been established on plant maintenance. One of its major tasks in 2004 is to prepare a status report on advanced strategies to optimise maintenance. Optimisation projects have an interface with the plant's overall life management program. Today, almost all plants involved in SENUF network have an explicit policy to extend their service life, thus, component ageing management, modernization and refurbishment actions became much more important. A database is also under development, which intends to help sharing the available knowledge and specific equipment and tools. (orig.)

Formation of maintenance economic safety enterprise system

Directory of Open Access Journals (Sweden)

N. A. Serebryakova

2016-01-01

Full Text Available The article examines the issues of economic security. The operation of enterprises is being implemented in a volatile market environment, which requires a comprehensive assessment of not only the individual factors affecting the operation of the enterprise, but also encourages the need to develop a comprehensive system for the enterprise to ensure economic security. The purpose of this study is to examine the theoretical and methodological approaches to assessing and ensuring the economic security of the enterprise, the development of a mechanism to ensure the economic security of the enterprise. Measures to ensure the safety of personnel suggest preventive work with the personnel, training personnel of the security services division, formation of personnel reserve of security personnel, the organization of work with new employees, reducing staff turnover. Preventive measures to minimize include activities not directly related to the activities of security units, but to minimize losses of commercial enterprise in the course of maintenance operations: control of inventories; control document; scheduled and unscheduled inspections during the reception of the goods; selection and organization of the movement control risk goods. Development of guidelines and regulations involves the planning of a clear legal regulation of all processes for the operation of commercial facility, potentially dangerous from the point of view of any commercial activity or threats to the security risks. The success of the activities is largely determined by the speed and accuracy of enterprise responses to emerging threats, where a key determinant of the effectiveness of business, is to create a system to ensure the economic security of the enterprise.

Managing sidewalk pavement maintenance: A case study to increase pedestrian safety

Directory of Open Access Journals (Sweden)

Maria Vittoria Corazza

2016-06-01

Full Text Available Comfort is a major requirement in planning pedestrian facilities. Pedestrians walk where they feel comfortable and when they do not feel at ease, they walk elsewhere. A typical example is that filthy, distressed, or too narrow sidewalks induce pedestrians to walk on carriageways. This behaviour jeopardizes road safety and highly dangerous to most users, leave them vulnerable. Unsuitable pavements can be the result of irregular maintenance operations to restore evenness after shock damage, weather phenomena, installation of equipment (e.g., posts, fences, urban furniture with a reduction of walkable surface, or substandard repair work on pavements and patches due to emergency operations. These problems can be solved with an appropriate maintenance management system, which optimizes financial resources to make smart decisions about how to intervene with an adequate and lasting maintenance operation. This paper defines an evaluation index for sidewalk conditions as a part of an efficient set-up of a Sidewalk Management System, which is similar to the better known Road Management System. The study relies on surveys, as well as the classification and analysis of sidewalk distresses. The authors adapted an index already standardized by ASTM for roads and airports: the Pavement Condition Index (PCI. PCI has been modified to consider the specific types on the sidewalks studied within this paper. To validate the method, a case study of a residential district in Rome, Italy, was carried out. The chosen area lacks regular maintenance and has therefore resulted in a network of unsafe sidewalks. Frequent detour routes were surveyed and related to the level of distresses within a general assessment of safety. This study concentrates on sidewalks with flexible pavements because this type of pavement is the only one adopted in the survey areas and, in general, throughout Italy.

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

Study on a quantitative evaluation method of equipment maintenance level and plant safety level for giant complex plant system

International Nuclear Information System (INIS)

Aoki, Takayuki

2010-01-01

In this study, a quantitative method on maintenance level which is determined by the two factors, maintenance plan and field work implementation ability by maintenance crew is discussed. And also a quantitative evaluation method on safety level for giant complex plant system is discussed. As a result of consideration, the following results were obtained. (1) It was considered that equipment condition after maintenance work was determined by the two factors, maintenance plan and field work implementation ability possessed by maintenance crew. The equipment condition determined by the two factors was named as 'equipment maintenance level' and its quantitative evaluation method was clarified. (2) It was considered that CDF in a nuclear power plant, evaluated by using a failure rate counting the above maintenance level was quite different from CDF evaluated by using existing failure rates including a safety margin. Then, the former CDF was named as 'plant safety level' of plant system and its quantitative evaluation method was clarified. (3) Enhancing equipment maintenance level means an improvement of maintenance quality. That results in the enhancement of plant safety level. Therefore, plant safety level should be always watched as a plant performance indicator. (author)

[The experience of involvement of volunteers into maintenance of infection safety during period of implementation of mass activities].

Science.gov (United States)

Imamov, A A; Balabanova, L A; Zamalieva, M A

2016-01-01

The article presents experience of Rospotrebnadzor in the Republic of Tatarstan in the field of preventive medicine concerning training of volunteers on issues of infection safety with purpose of prevention of ictuses of infection diseases during mass activities with international participation in the period of XXVII World Summer Students Games. The model of hygienic training for volunteers provides two directions: training for volunteers ’ leaders on issues of infection safety and remote course for involved volunteers. During period of preparation for the Students Games-2013 hygienic training was organized for volunteers-leaders in the field of infection safety with following attestation. The modern training technologies were applied. The volunteers-leaders familiarized with groups of infection diseases including the most dangerous ones, investigated with expert algorithm of actions to be applied in case of suspicion on infection disease in gest or participant of the Games-2013 to secure one's health and health of immediate population. The active volunteers-leaders became trainers and coaches in the field of infection safety. The second stage of infection safety training organized by youth trainers' pool in number of 30 individuals the training technology "Equal trains equal" was applied for hygienic training of volunteers involved at epidemiologically significant objects (food objects, hotels, accompaniment of guests and sportsmen). The volunteers-leaders trained to infection safety 1400 volunteers. The format of electronic personal cabinet and remote course were selected as tools of post-training monitoring.

Parameter Estimation of a Reliability Model of Demand-Caused and Standby-Related Failures of Safety Components Exposed to Degradation by Demand Stress and Ageing That Undergo Imperfect Maintenance

Directory of Open Access Journals (Sweden)

S. Martorell

2017-01-01

Full Text Available One can find many reliability, availability, and maintainability (RAM models proposed in the literature. However, such models become more complex day after day, as there is an attempt to capture equipment performance in a more realistic way, such as, explicitly addressing the effect of component ageing and degradation, surveillance activities, and corrective and preventive maintenance policies. Then, there is a need to fit the best model to real data by estimating the model parameters using an appropriate tool. This problem is not easy to solve in some cases since the number of parameters is large and the available data is scarce. This paper considers two main failure models commonly adopted to represent the probability of failure on demand (PFD of safety equipment: (1 by demand-caused and (2 standby-related failures. It proposes a maximum likelihood estimation (MLE approach for parameter estimation of a reliability model of demand-caused and standby-related failures of safety components exposed to degradation by demand stress and ageing that undergo imperfect maintenance. The case study considers real failure, test, and maintenance data for a typical motor-operated valve in a nuclear power plant. The results of the parameters estimation and the adoption of the best model are discussed.

Good practices for effective maintenance to manage aging at NPPs

International Nuclear Information System (INIS)

Scott, W.B.; Enderlin, W.I.; Levy, I.S.

1989-01-01

The Nuclear Regulatory Commission's Office of Nuclear Regulatory Research is sponsoring this effort to study maintenance as it relates to aging, under the Nuclear Plant Aging Research (NPAR). Maintenance is the primary means of combating and correcting the effects of aging degradation at nuclear power plants. Maintenance effectiveness directly affects the safety of nuclear power plants. Several recent plant events have shown that improper maintenance or a lack of maintenance can be a significant contributory cause of plant incidents (e.g., transients at Rancho Seco and Davis Besse, and the Salem anticipated transient without scram event). In these, and other events, safety related plant equipment functions have been impaired by poor maintenance practices or a lack of maintenance on the specific equipment or in ancillary equipment that affects the ability of the safety related equipment to function. In some cases, the ancillary equipment has been nonsafety-related equipment, or balance-of-plant equipment that has not received adequate maintenance attention. In addition to the potential for causing safety significant plant transients, poor or lacking maintenance may allow the licensing basis of the plant to be eroded without detection. In some cases, time-related aging degradation of equipment that has not been detected, corrected or managed by the maintenance program has been a significant contributory factor. The NPAR program has developed significant information on aging degradation, detection, mitigation, and correction practices for safety-significant structures, systems and components that can be factored into maintenance programs and their effectiveness

CANDU plant maintenance: Recent developments

International Nuclear Information System (INIS)

Charlebois, P.

2000-01-01

CANDU units have long been recognized for their exceptional safety and reliability. Continuing development in the maintenance area has played a key role in achieving this performance level. For over two decades, safety system availability has been monitored closely and system maintenance programs adjusted accordingly to maintain high levels of performance. But as the plants approach mid life in a more competitive environment and component aging becomes a concern, new methods and techniques are necessary. As a result, recent developments are moving the maintenance program largely from a corrective and preventive approach to predictive and condition based maintenance. The application of these techniques is also being extended to safety related systems. These recent developments include use of reliability centred methods to define system maintenance requirements and strategies. This approach has been implemented on a number of systems at Canadian CANDU plants with positive results. The pilot projects demonstrated that the overall maintenance effort remained relatively constant while the system performance improved. It was also possible to schedule some of the redundant component maintenance during plant operation without adverse impact on system availability. The probabilistic safety assessment was found to be useful in determining the safety implications of component outages. These new maintenance strategies are now making use of predictive and condition based maintenance techniques to anticipate equipment breakdown and schedule preventive maintenance as the need arises rather than time based. Some of these techniques include valve diagnostics, vibration monitoring, oil analysis, thermography. Of course, these tools and techniques must form part of an overall maintenance management system to ensure that maintenance becomes a living program. To facilitate this process and contain costs, new information technology tools are being introduced to provide system engineers

Manual on maintenance of systems and components important to safety

International Nuclear Information System (INIS)

1986-01-01

The Manual should serve as guidance at the plant management level for the maintenance of systems and components important to safety. It includes a detailed description of management systems, administrative controls and procedures. The Annexes contain examples of documents and practices adopted by Operating Organizations of some Member States. It is not the intention of this Manual to address the technical problem of how to maintain a particular component but rather to cover the programmatic aspects of maintenance. It also contains some aspects of surveillance and verification activities. The Manual makes only general statements about radiation protection provisions in connection with maintenance; detailed guidance can be found in other IAEA documents

47 CFR 80.1074 - Radio maintenance personnel for at-sea maintenance.

Science.gov (United States)

2010-10-01

... maintenance. 80.1074 Section 80.1074 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety... Global Maritime Distress and Safety System related to Sea Areas A3 and A4. [57 FR 9065, Mar. 16, 1992, as...

A study on maintenance rule program and its application at Korean NPPs

International Nuclear Information System (INIS)

Hwang, Mee Jeong; Kim, Kil Yoo; Kang, Dae Il; Yang, Joon Eon; Ha, Jae Joo

2000-11-01

The objective of the Maintenance Rule is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that safety related and certain nonsafety-related SSCs are capable of performing their intended functions and, for nonsafety-related equipment failures will not occur that prevent the fulfillment of safety-related functions, and failures resulting in scrams and unnecessary actuations of safety-related systems are minimized. That is, proper maintenance is essential to plant safety. U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially adopted in Korea by Korean regulatory body. However, since many PSA and IPE have been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as well as performance-based regulation are being acceptable. We survey the Maintenance Rule program and applications in the USA, and also developed the Maintenance Rule program to apply to Korean NPPs. In addition, we applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the Maintenance Rule Program developed in this project

A study on maintenance rule program and its application at Korean NPPs

Energy Technology Data Exchange (ETDEWEB)

Hwang, Mee Jeong; Kim, Kil Yoo; Kang, Dae Il; Yang, Joon Eon; Ha, Jae Joo

2000-11-01

The objective of the Maintenance Rule is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that safety related and certain nonsafety-related SSCs are capable of performing their intended functions and, for nonsafety-related equipment failures will not occur that prevent the fulfillment of safety-related functions, and failures resulting in scrams and unnecessary actuations of safety-related systems are minimized. That is, proper maintenance is essential to plant safety. U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially adopted in Korea by Korean regulatory body. However, since many PSA and IPE have been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as well as performance-based regulation are being acceptable. We survey the Maintenance Rule program and applications in the USA, and also developed the Maintenance Rule program to apply to Korean NPPs. In addition, we applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the Maintenance Rule Program developed in this project.

Nuclear power plant maintenance optimisation SENUF network activity

Energy Technology Data Exchange (ETDEWEB)

Ahlstrand, R.; Bieth, M.; Pla, P.; Rieg, C.; Trampus, P. [Inst. for Energy, EC DG Joint Research Centre, Petten (Netherlands)

2004-07-01

During providing scientific and technical support to TACIS and PHARE nuclear safety programs a large amount of knowledge related to Russian design reactor systems has accumulated and led to creation of a new Network concerning Nuclear Safety in Central and Eastern Europe called ''Safety of Eastern European type Nuclear Facilities'' (SENUF). SENUF contributes to bring together all stakeholders of TACIS and PHARE: beneficiaries, end users, Eastern und Western nuclear industries, and thus, to favour fruitful technical exchanges and feedback of experience. At present the main focus of SENUF is the nuclear power plant maintenance as substantial element of plant operational safety as well as life management. A Working Group has been established on plant maintenance. One of its major tasks in 2004 is to prepare a status report on advanced strategies to optimise maintenance. Optimisation projects have an interface with the plant's overall life management program. Today, almost all plants involved in SENUF network have an explicit policy to extend their service life, thus, component ageing management, modernization and refurbishment actions became much more important. A database is also under development, which intends to help sharing the available knowledge and specific equipment and tools. (orig.)

Engineering and maintenance applied to safety-related valves in nuclear power plants

International Nuclear Information System (INIS)

Verdu, M. F.; Perez-Aranda, J.

2014-01-01

Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

Routine maintenance: safety term based work selection; Selecao de trabalho baseado no prazo seguro

Energy Technology Data Exchange (ETDEWEB)

Camargo, Albair de; Filho, Antnio S.; Brendler, Fabiano E.; Adamatti, Gilberto A.; Naruto, Itiro; Araujo, Luiz C.F.; Puerari, Roberto [PETROBRAS, Rio de Janeiro, RJ (Brazil)

2004-07-01

This work has objective to present the experience of improvement of routine maintenance system in some refineries of the PETROBRAS system, with the purpose to increase the efficiency in the Industrial Maintenance Management (cost), Utilization and HSE (Health, Safety and Environment), key of success of a petroleum company. The new system is based on the implantation of the culture of work selection in the safe period, through elaboration of new maintenance procedure, with emphasis in decisions shared between Operation and Maintenance Team, resulting in reduction of emergencies, making possible contract of services of maintenance for packages and improved allocation of resources. This work treat about improvement of the system in use, in view of that it has already taken in consideration the consequence of fail in the maintenance with participation of the operators. Besides of these challenge, this modification was made without causing riots in the process of implantation of SAP. As main result, financial profits had got better of resources with increase of safety, considering that they are analyzed in a way it that systematized potential risks. (author)

Dukovany NPP maintenance management

International Nuclear Information System (INIS)

Siegel, F.

2005-01-01

Maintenance planning and management for the technological equipment of the Dukovany NPP are described. A Maintenance Control and Evaluation System has been developed and is in use to help manage the complex maintenance issue. Practical examples of outputs of the System, with a comprehensive use of the cost, reliability and safety related data, are presented. (author)

AVIATION SAFETY CULTURE MEASUREMENT MODEL FIT VALIDATION OF A SURVEY FOR THE AVIATION MAINTENANCE REPAIR ORGANIZATIONS

OpenAIRE

Vahap ÖNEN

2017-01-01

It is believed that safety is the major issue for the aviation industry. According to Boeing Study %15 of the fatal accidents are incurred by maintenance sources related. On the other hand, from the last ten years safety management system which firstly introduced by ICAO became popular in the aviation industry. In the beginning, enforcement by ICAO Annex 19 then following it consequtively by EASA’s regulation, at the same time issued many advisory circulars by FAA that SMS entried in force an...

Maintenance of reactor safety and control computers at a large government facility

International Nuclear Information System (INIS)

Brady, H.G.

1985-01-01

In 1950 the US Government contracted the Du Pont Company to design, build, and operate the Savannah River Plant (SRP). At the time, it was the largest construction project ever undertaken by man. It is still the largest of the Department of Energy facilities. In the nearly 35 years that have elapsed, Du Pont has met its commitments to the US Government and set world safety records in the construction and operation of nuclear facilities. Contributing factors in achieving production goals and setting the safety records are a staff of highly qualified personnel, a well maintained plant, and sound maintenance programs. There have been many ''first ever'' achievements at SRP. These ''firsts'' include: (1) computer control of a nuclear rector, and (2) use of computer systems as safety circuits. This presentation discusses the maintenance program provided for these computer systems and all digital systems at SRP. An in-house computer maintenance program that was started in 1966 with five persons has grown to a staff of 40 with investments in computer hardware increasing from $4 million in 1970 to more than $60 million in this decade. 4 figs

EDA activities related to safety

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2001-01-01

This article reviews the accomplishments in ITER safety analysis during the course of the Engineering Design Activities (EDA). The key aspects of ITER safety analysis are: effluents and emissions from normal operation, including planned maintenance activities; occupational safety for workers at the facility; radioactive materials and wastes generated during operation and from decommissioning ; potential incidents and accidents and the resulting transients. As a result of the work during the EDA it is concluded that ITER is safe

Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

International Nuclear Information System (INIS)

Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

2000-01-01

Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

Criteria for safety-related operator actions

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1983-01-01

The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

The method for assurance to operational safety of cryogenics equipment through definite maintenance

International Nuclear Information System (INIS)

Anghel, Vasile

2004-01-01

The present paper reports about a method of ensuring operational safety of cryogenics equipment through specific maintenance measures which imply a definite concept of maintainability and operational reliability, methods of maintenance, necessary logistic and necessary personnel. The stages of the concept should succeed in a logical order and must be based on detailed analyses of the process of maintenance. The method starts from the operation conditions of cryogenic equipment in nuclear regime. Thus maintenance policy must be well defined within the boundaries of the nuclear plant through definition of coherent objectives and responsibility delegation for the personnel implied in maintenance activity. This method ensures performance in maintenance and an efficient feedback from equipment analysis. (author)

Design of the system of maintenance operations occupational safety and health database application of nuclear power station

International Nuclear Information System (INIS)

Wang Xuehong; Li Xiangyang; Ye Yongjun

2011-01-01

Based on the KKS code of building equipment in nuclear power station, this paper introduces the method of establishing the system of maintenance operation occupational safety and health database application. Through the application system of maintenance occupational safety and health database, it can summarize systematically all kinds of maintenance operation dangerous factor of nuclear power station, and make a convenience for staff to learn the maintenance operation dangerous factors and the prevention measures, so that it can achieve the management concept of 'precaution crucial, continuous improvement' that advocated by OSHMS. (authors)

On-line maintenance at Cofrentes NPP

International Nuclear Information System (INIS)

Roldan Vilches, J.; Moreno Matarranz, M. A.; Hermana Mendioroz, I.

1998-01-01

Cofrentes NPP has begun in 1997 activities related to At Power Preventive Maintenance over trains or systems which lead to a voluntary entry in a Limitative Condition of Operation (LCO) of the Technical Specifications. From others benefits, this program ha improved the risk management and the staff's knowledge over the functions and safety implications of the different systems, the better exploit of the resources, the co-ordination of the different organisations involved (Maintenance an Operation) and the reductions of works during shutdowns. Previous to each work, a feasibility study analyzes qualitative and quantitative (PSA), using the Risk Monitor, the implications on safety of all the tasks, assuring that the global safety of the Plant is always maintained. Tech. Spec. are analyzed in detail and also are analyzed situations of simultaneous unavailabilities of systems which could lead to a high risk situation. Two different risk controls are defined (punctual and accumulated) to assure that high risk situations will not be given. Finally, historical risk profile is analyzed to assure that the accumulated risk increase is not significant. Risk Monitor helps staff in the schedule and follow-up of the activities of On-Line Maintenance. Each one of the tasks are deeply planned and harshly analyzed and are carried out by high qualified workers. By the moment, this program is running with fully satisfaction on the Plant. (Author)

A study on maintenance rule program and its application to Korean NPP - Rev.1

International Nuclear Information System (INIS)

Hwang, Mee Jeong; Kim, Kil Yoo; Yang, Joon Eon; Ha, Jae Joo

2001-03-01

The objective of the Maintenance Rule is to require monitoring of the overall continuing effectiveness of licensee maintenance programs to ensure that safety related and certain nonsafety-related SSCs are capable of performing their intended functions and, for nonsafety-related equipment failures will not occur that prevent the fulfillment of safety-related functions, and failures resulting in scrams and unnecessary actuations of safety-related systems are minimized. That is, proper maintenance is essential to plant safety. U.S. Maintenance Rule, which was effective July 1996 in USA., was not officially adopted in Korea by Korean regulatory body. However, since many PSA and IPE have been performed for NPPs, the philosophy and usefulness of the Maintenance Rule as well as performance-based regulation are being acceptable. We survey the Maintenance Rule program and applications in the USA, and also developed the Maintenance Rule program to apply to Korean NPPs. In addition, we applied the Maintenance Rule Program apply to Ulchin 3,4 Units roughly with the Maintenance Rule Program developed in this project

Equipment maintenance as a tool for raising of safety and efficiency of the NPP'Kozloduy' operation

International Nuclear Information System (INIS)

Kichev, E.

1999-01-01

The role of the maintenance in the NPP management is discussed. The main links in the management are: NPP executives and their position; maintenance; quantitative characteristics of the maintenance. The described management process gives the opportunity the maintenance optimization on different levels: component, system, unit, plant. The results are valid for other areas with high safety requirements

Sensor/signal monitoring and plant maintenance

International Nuclear Information System (INIS)

Ciftcioglu, Oe.; Tuerkcan, E.

1994-02-01

Nuclear Power Plant (NPO) availability is determined by the intended functionality of safety related system and components. Therefore, maintenance is an important issue in a power plant connected to the plant's reliability and safety. The traditional maintenance policies proved to be rather costly and even not effectively addressing NPP requirements. Referring to these drawbacks, in the last decade, in the nuclear reliability centered maintenance (RCM) gained substantial interest due to its merits. In the formal implementation of RCM, apparently, predictive maintenance is not considered. However, with the impact of modern real-time and on-line surveillance and monitoring methodologies, the predictive maintenance procedures like sensor/signal verification and validation are to be included into RCM. (orig.)

An analysis of electronic health record-related patient safety concerns

Science.gov (United States)

Meeks, Derek W; Smith, Michael W; Taylor, Lesley; Sittig, Dean F; Scott, Jean M; Singh, Hardeep

2014-01-01

Objective A recent Institute of Medicine report called for attention to safety issues related to electronic health records (EHRs). We analyzed EHR-related safety concerns reported within a large, integrated healthcare system. Methods The Informatics Patient Safety Office of the Veterans Health Administration (VA) maintains a non-punitive, voluntary reporting system to collect and investigate EHR-related safety concerns (ie, adverse events, potential events, and near misses). We analyzed completed investigations using an eight-dimension sociotechnical conceptual model that accounted for both technical and non-technical dimensions of safety. Using the framework analysis approach to qualitative data, we identified emergent and recurring safety concerns common to multiple reports. Results We extracted 100 consecutive, unique, closed investigations between August 2009 and May 2013 from 344 reported incidents. Seventy-four involved unsafe technology and 25 involved unsafe use of technology. A majority (70%) involved two or more model dimensions. Most often, non-technical dimensions such as workflow, policies, and personnel interacted in a complex fashion with technical dimensions such as software/hardware, content, and user interface to produce safety concerns. Most (94%) safety concerns related to either unmet data-display needs in the EHR (ie, displayed information available to the end user failed to reduce uncertainty or led to increased potential for patient harm), software upgrades or modifications, data transmission between components of the EHR, or ‘hidden dependencies’ within the EHR. Discussion EHR-related safety concerns involving both unsafe technology and unsafe use of technology persist long after ‘go-live’ and despite the sophisticated EHR infrastructure represented in our data source. Currently, few healthcare institutions have reporting and analysis capabilities similar to the VA. Conclusions Because EHR-related safety concerns have complex

Pilot Study for Maintenance Rule at KSNP

International Nuclear Information System (INIS)

Choi, Kwang Hee; Jeong, Hyeon Jong; Jee, Moon Hak; Hong, Sung Yull

2005-01-01

Maintenance Rule (MR), which was developed to monitor the effectiveness of maintenance in a nuclear power plant (NPP), has been received as highly successful program by and large since its implementation in 1996 in the United States. Korea has initiated two pilot programs to implement the Maintenance Rule program in 2003. Selected plants for the pilot implementation are Kori 3 and 4 units and Ulchin 3 and 4 units, where Kori 3 and 4 units are Westinghouse units and Ulchin 3 and 4 units are Korean Standardized Nuclear Power (KSNP) Plant units. This paper describes the results of each key tasks completed to date and insights gained from pilot study on the KSNP units. Currently, Scoping of the functions of maintenance rule and determination of safety significance level have been completed during first year. As first task, total 607 functions were identified and defined by detailed function analysis on 135 systems that cover all plant systems. About 55% of total functions are selected as within the scope of maintenance rule. Among these inscoped functions, 56% of scoped functions are safety related and 44% are non-safety related functions. Evaluation of safety significance for each function was determined by expert panel consist of eight experts in field of plant maintenance, operation, PSA, work schedule and system engineers. As a result, about 46% of functions were determined to be high safety significant functions and rest of the functions were classified as low safety significant. The remaining tasks that are included determination of performance criteria and preparation of implementing guideline will be performed in following years

Maintenance of relational information in working memory leads to suppression of the sensory cortex.

Science.gov (United States)

Ikkai, Akiko; Blacker, Kara J; Lakshmanan, Balaji M; Ewen, Joshua B; Courtney, Susan M

2014-10-15

Working memory (WM) for sensory-based information about individual objects and their locations appears to involve interactions between lateral prefrontal and sensory cortexes. The mechanisms and representations for maintenance of more abstract, nonsensory information in WM are unknown, particularly whether such actively maintained information can become independent of the sensory information from which it was derived. Previous studies of WM for individual visual items found increased electroencephalogram (EEG) alpha (8-13 Hz) power over posterior electrode sites, which appears to correspond to the suppression of cortical areas that represent irrelevant sensory information. Here, we recorded EEG while participants performed a visual WM task that involved maintaining either concrete spatial coordinates or abstract relational information. Maintenance of relational information resulted in higher alpha power in posterior electrodes. Furthermore, lateralization of alpha power due to a covert shift of attention to one visual hemifield was marginally weaker during storage of relational information than during storage of concrete information. These results suggest that abstract relational information is maintained in WM differently from concrete, sensory representations and that during maintenance of abstract information, posterior sensory regions become task irrelevant and are thus suppressed. Copyright © 2014 the American Physiological Society.

Cost effective maintenance to supply end user value: Visionary or utopian

NARCIS (Netherlands)

Wessels, J.; Alten, K.; Turk, M.R.; Palić, S.Š.

2013-01-01

Infrastructure stakeholders expect maintenance managers to deliver acceptable End User Service Levels (EUSL), such as availability, comfort, and safety. Means of controlling these requirements involve technical maintenance and operative measures. Within the ERANET Road Program 'Effective asset

The safety monitor and RCM workstation as complementary tools in risk based maintenance optimization

International Nuclear Information System (INIS)

Rawson, P.D.

2000-01-01

Reliability Centred Maintenance (RCM) represents a proven technique for rendering maintenance activities safer, more effective, and less expensive, in terms of systems unavailability and resource management. However, it is believed that RCM can be enhanced by the additional consideration of operational plant risk. This paper discusses how two computer-based tools, i.e., the RCM Workstation and the Safety Monitor, can complement each other in helping to create a living preventive maintenance strategy. (author)

Maintenance analysis method and operational feedback: a comprehensive maintenance management

International Nuclear Information System (INIS)

Mathieu Riou; Victor Planchon

2006-01-01

components instead of cask. Safety Analysis Reports have now exhaustive periodic upkeep program, listing all the inspections mandatory to guarantee transportations safety and cask's conformity with current approval certificates. Some inspections have been deleted, leading to a radiation exposure reduction. Some criteria have been widened, leading to replacement component optimization. It is currently too early to have a precise estimation of waste optimization, as the relation between waste quantity and maintenance operations. This methodology will be applied on the other casks of the COGEMA LOGISTICS fleet. As soon as the new procedures are applicable, an assessment will be carried out. (authors)

Perceived personal safety in relation to urban woodland vegetation – A review

OpenAIRE

Jansson, Märit; Fors, Hanna; Lindgren, Therese; Wiström, Björn

2013-01-01

Urban woodland vegetation provides people with many aesthetic, ecological and psychological benefits, but can also generate problems concerning people’s perception of safety. This paper reviews existing knowledge about perceived personal safety in relation to vegetation, particularly woodland vegetation, in urban green spaces such as parks and residential areas. Individual and social factors, but also vegetation character, maintenance and design, proved to be important for perceived personal ...

Applying reliability centered maintenance analysis principles to inservice testing

International Nuclear Information System (INIS)

Flude, J.W.

1994-01-01

Federal regulations require nuclear power plants to use inservice test (IST) programs to ensure the operability of safety-related equipment. IST programs are based on American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code requirements. Many of these plants also use Reliability Centered Maintenance (RCM) to optimize system maintenance. ASME Code requirements are hard to change. The process for requesting authority to use an alternate strategy is long and expensive. The difficulties of obtaining this authority make the use of RCM method on safety-related systems not cost effective. An ASME research task force on Risk Based Inservice Testing is investigating changing the Code. The change will allow plants to apply RCM methods to the problem of maintenance strategy selection for safety-related systems. The research task force is working closely with the Codes and Standards sections to develop a process related to the RCM process. Some day plants will be able to use this process to develop more efficient and safer maintenance strategies

Reliability Centered Maintenance (RCM) Methodology and Application to the Shutdown Cooling System for APR-1400 Reactors

Energy Technology Data Exchange (ETDEWEB)

Faragalla, Mohamed M.; Emmanuel, Efenji; Alhammadi, Ibrahim; Awwal, Arigi M.; Lee, Yong Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2016-10-15

Shutdown Cooling System (SCS) is a safety-related system that is used in conjunction with the Main Steam and Main or Auxiliary Feedwater Systems to reduce the temperature of the Reactor Coolant System (RCS) in post shutdown periods from the hot shutdown operating temperature to the refueling temperature. In this paper RCM methodology is applied to (SCS). RCM analysis is performed based on evaluation of Failure Modes Effects and Criticality Analysis (FME and CA) on the component, system and plant. The Logic Tree Analysis (LTA) is used to determine the optimum maintenance tasks. The main objectives of RCM is the safety, preserve the System function, the cost-effective maintenance of the plant components and increase the reliability and availability value. The RCM methodology is useful for improving the equipment reliability by strengthening the management of equipment condition, and leads to a significant decrease in the number of periodical maintenance, extended maintenance cycle, longer useful life of equipment, and decrease in overall maintenance cost. It also focuses on the safety of the system by assigning criticality index to the various components and further selecting maintenance activities based on the risk of failure involved. Therefore, it can be said that RCM introduces a maintenance plan designed for maximum safety in an economical manner and making the system more reliable. For the SCP, increasing the number of condition monitoring tasks will improve the availability of the SCP. It is recommended to reduce the number of periodic maintenance activities.

A new modeling approach to the safety evaluation of N-modular redundant computer systems in presence of imperfect maintenance

International Nuclear Information System (INIS)

Flammini, Francesco; Marrone, Stefano; Mazzocca, Nicola; Vittorini, Valeria

2009-01-01

A large number of safety-critical control systems are based on N-modular redundant architectures, using majority voters on the outputs of independent computation units. In order to assess the compliance of these architectures with international safety standards, the frequency of hazardous failures must be analyzed by developing and solving proper formal models. Furthermore, the impact of maintenance faults has to be considered, since imperfect maintenance may degrade the safety integrity level of the system. In this paper, we present both a failure model for voting architectures based on Bayesian networks and a maintenance model based on continuous time Markov chains, and we propose to combine them according to a compositional multiformalism modeling approach in order to analyze the impact of imperfect maintenance on the system safety. We also show how the proposed approach promotes the reuse and the interchange of models as well the interchange of solving tools.

Assessment and management of aging of nuclear power plant safety-related structures

International Nuclear Information System (INIS)

Naus, D.J.; Graves, H.L. III; Ellingwood, B.R.

2003-01-01

Background information and data have been developed for improving existing and developing new methods to assist in quantifying the effects of age-related degradation on the performance of nuclear power plant (NPP) safety-related structures. Factors that can lead to age-related degradation of safety-related structures are identified and their manifestations described. Current regulatory testing and inspection requirements are reviewed and a summary of degradation experience presented. Techniques commonly used to inspect NPP concrete structures to assess and quantify age-related degradation are summarized. An approach for conduct of condition assessments of structures in NPPs is presented. Criteria, based primarily on visual indications, are provided for use in classification and assessment of concrete degradation. Materials and techniques for repair of degraded structures are noted and guidance provided on repair options available for various forms of degradation. A probabilistic methodology for condition assessment and reliability-based life prediction has been developed and applied to structures subject to combinations of structural load processes and to structural systems. The methodology has also been used to investigate optimization of in-service inspection and maintenance strategies to maintain failure probability below a specified target value as well as to minimize costs. Fragility assessments involving analytical solutions and finite-element methods have been utilized to predict the effect of aging degradation on structural component performance. (author)

Human cognitive task distribution model for maintenance support system of a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Park, Young Ho

2007-02-15

In human factors research, more attention has been devoted to the operation of nuclear power plants (NPPs) than to their maintenance. However, human error related to maintenance is 45% among the total human errors from 1990 to 2005 in Korean nuclear power plants. Therefore, it is necessary to study human factors in the maintenance of an NPP. There is a current trend toward introducing digital technology into both safety and non-safety systems in NPPs. A variety of information about plant conditions can be used digitally. In the future, maintenance support systems will be developed based on an information-oriented NPP. In this context, it is necessary to study the cognitive tasks of the personnel involved in maintenance and the interaction between the personnel and maintenance support systems. The fundamental purpose of this work is how to distribute the cognitive tasks of the personnel involved in the maintenance in order to develop a maintenance support system that considers human factors. The second purpose is to find the causes of errors due to engineers or maintainers and propose system functions that are countermeasures to reduce these errors. In this paper, a cognitive task distribution model of the personnel involved in maintenance is proposed using Rasmussen's decision making model. First, the personnel were divided into three groups: the operators (inspectors), engineers, and maintainers. Second, human cognitive tasks related to maintenance were distributed based on these groups. The operators' cognitive tasks are detection and observation; the engineers' cognitive tasks are identification, evaluation, target state, select target, and procedure: and the maintainers' cognitive task is execution. The case study is an analysis of failure reports related to human error in maintenance over a period of 15years. By using error classification based on the information processing approach, the human errors involved in maintenance were classified

Human cognitive task distribution model for maintenance support system of a nuclear power plant

International Nuclear Information System (INIS)

Park, Young Ho

2007-02-01

In human factors research, more attention has been devoted to the operation of nuclear power plants (NPPs) than to their maintenance. However, human error related to maintenance is 45% among the total human errors from 1990 to 2005 in Korean nuclear power plants. Therefore, it is necessary to study human factors in the maintenance of an NPP. There is a current trend toward introducing digital technology into both safety and non-safety systems in NPPs. A variety of information about plant conditions can be used digitally. In the future, maintenance support systems will be developed based on an information-oriented NPP. In this context, it is necessary to study the cognitive tasks of the personnel involved in maintenance and the interaction between the personnel and maintenance support systems. The fundamental purpose of this work is how to distribute the cognitive tasks of the personnel involved in the maintenance in order to develop a maintenance support system that considers human factors. The second purpose is to find the causes of errors due to engineers or maintainers and propose system functions that are countermeasures to reduce these errors. In this paper, a cognitive task distribution model of the personnel involved in maintenance is proposed using Rasmussen's decision making model. First, the personnel were divided into three groups: the operators (inspectors), engineers, and maintainers. Second, human cognitive tasks related to maintenance were distributed based on these groups. The operators' cognitive tasks are detection and observation; the engineers' cognitive tasks are identification, evaluation, target state, select target, and procedure: and the maintainers' cognitive task is execution. The case study is an analysis of failure reports related to human error in maintenance over a period of 15years. By using error classification based on the information processing approach, the human errors involved in maintenance were classified

Influence of Employee Involvement in Total Productive Maintenance Practices on Job Characteristics: The Malaysian Scenario

Directory of Open Access Journals (Sweden)

Aizzat Mohd. Nasurdin

2005-09-01

Full Text Available The main goal of this study is to examine whether the extent of involvement in Total Productive Maintenance (TPM practices has a positive effect on job characteristics. Data was gathered from a sample of 184 respondents derived from manufacturing companies in Malaysia. Results from the regression analyses revealed that the extent of employee’s involvement in TPM practices is positively related to the five core job dimensions (skill variety, task identity, task significance, autonomy, and feedback. Theoretical and managerial implications of the findings are discussed.

Improving human performance in maintenance personnel

International Nuclear Information System (INIS)

Gonzalez Anez, Francisco; Agueero Agueero, Jorge

2010-01-01

The continuous evolution and improvement of safety-related processes has included the analysis, design and development of training plans for the qualification of maintenance nuclear power plant personnel. In this respect, the international references in this area recommend the establishment of systematic qualification programmes for personnel performing functions or carrying out safety related tasks. Maintenance personnel qualification processes have improved significantly, and training plans have been designed and developed based on Systematic Approach to Training methodology to each job position. These improvements have been clearly reflected in recent training programmes with new training material and training facilities focused not only on developing technical knowledge and skills but also on improving attitudes and safety culture. The objectives of maintenance training facilities such as laboratories, mock-ups real an virtual, hydraulic loops, field simulators and other training material to be used in the maintenance training centre are to cover training necessities for initial and continuous qualification. Evidently, all these improvements made in the qualification of plant personnel should be extended to include supplemental personnel (external or contracted) performing safety-related tasks. The supplemental personnel constitute a very spread group, covering the performance of multiple activities entailing different levels of responsibility. Some of these activities are performed permanently at the plant, while others are occasional or sporadic. In order to establish qualification requirements for these supplemental workers, it is recommended to establish a rigorous analysis of job positions and tasks. The objective will be to identify the qualification requirements to assure competence and safety. (authors)

Applying artificial intelligence to safety and maintenance (in nuclear plants)

International Nuclear Information System (INIS)

Anon.

1987-01-01

Under contract from the US DoE, Odetics Inc. is developing a prototype advisory expert system which may eventually be used for the maintenance and safety of a nuclear plant. The objective of the system will be to determine off-normal conditions and to help operations personnel through a course of action which would lead to a stable plant. (UK)

Modeling of preventive maintenance changes influence upon flight safety indexes

Directory of Open Access Journals (Sweden)

А.В. Гончаренко

2004-03-01

Full Text Available  It is considered a simplified model of connection between the catastrophic events flow frequency and both preventive maintenance changes periodicity and diagnosis depth of aviation equipment. It is deduced specific formulas for computing the changes and diagnostics parameters influence upon the values of both the catastrophic events flow frequency and technical-economical control factor criterion of flight safety levels.

Relative Effects of Psychological Flexibility, Parental Involvement ...

African Journals Online (AJOL)

A critical analysis and understanding of secondary students' experiences and of safety in public schools are currently lacking in the literature and warrant further research. This study investigated the relative effects of psychological flexibility, parental involvement and school climate on secondary school student's school ...

Tele-maintenance 'intelligent' system for technical plants result management

International Nuclear Information System (INIS)

Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

2009-01-01

The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

Design, maintenance and lifetime of nuclear components

International Nuclear Information System (INIS)

Noel, R.L.; Eisenhut, D.G.; Carey, J.J.; Reynes, L.J.

1989-01-01

Division D of SMiRT deals with experience feedback relating to the in-service behavior of nuclear components, the design and construction of this equipment, its maintenance and the evaluation and management of its lifetime. The nuclear industry now having reached maturity, with more than 300 units in service worldwide, these problems are now of predominant importance to the activity of the industry and in its development programs. This applies particularly to the problems relating to the lifetime of nuclear plants, problems which are rightly of such concern both to the utilities, in view of the enormous investments involved, and also to the safety authorities. These contributions have been reviewed for the purpose of analyzing the essential points. This analysis highlights the considerable advances achieved during the recent decades in design and maintenance methods and practices. It also identifies the areas in which progress still remains to be made

Practicing industrial safety - issues involved

International Nuclear Information System (INIS)

Gunasekaran, P.

2016-01-01

Industrial safety is all about measures or techniques implemented to reduce the risk of injury, loss to persons, property or the environment in any industrial facility. The issue of industrial safety evolved concurrently with industrial development as a shift from compensation to prevention as well. Today, industrial safety is widely regarded as one of the most important factors that any business, large or small, must consider in its operations, as prevention of loss is also a part of profit. Factories Act of Central government and Rules made under it by the state deals with the provisions on industrial safety legislation. There are many other acts related to safety of personnel, property and environment. Occupational health and safety is also of primary concern. The aim is to regulate health and safety conditions for all employers. It includes safety standards and health standards. These acts encourage employers and employees to reduce workplace hazards and to implement new or improve existing safety and health standards; and develop innovative ways to achieve them. Maintain a reporting and record keeping system to monitor job-related injuries and illnesses; establish training programs to increase the number and competence of occupational safety and health personnel

Main indicators used in french PWR units for safety, operation and maintenance

International Nuclear Information System (INIS)

Guio, J.M. de

1990-01-01

The development of analyses aimed at improving nuclear plant operations through an optimum use of experience feedback naturally leads to the implementation of trend indicators in the fields of safety, operation and maintenance. This process, part of the more general framework of promoting safety culture, facilitates collective thinking on these matters at the local site level, and, at the national level, allows a clearer definition of the main lines of strategy and helps coordinate the resulting actions

Trend analysis of incidents involving setpoint drift in safety or safety/relief valves at U.S. LWRs

International Nuclear Information System (INIS)

Watanabe, Norio

2008-01-01

Since the beginning of the 1980's, in the United States, there have been many licensee event reports (LERs) involving setpoint drift in safety or safety/relief valves. The United States Nuclear Regulatory Commission (NRC) has issued a lot of generic communications on this issue and the industry has made efforts to resolve the issue. However, the NRC staff recently highlighted that over 70 LERs involved instances where safety or safety/relief valves failed to meet the allowed setpoint tolerance from 2001 through August 2006. In the present study, we analyzed the U.S. experience with setpoint drift in safety/relief valves (SRVs) at BWRs, pressurizer safety valves (PSVs), and main steam safety valves (MSSVs) at PWRs by reviewing approximately 90 LERs from 2000 to 2006 and examined the trend focusing on causes and setpoint deviation ranges. This study indicates that for SRVs and MSSVs, disc-seat bonding is a dominant cause of the setpoint drifting high and has a tendency to result in a relatively large deviation of the setpoint. This means that disc-seat bonding might be a safety concern from the view point of overpressure protection. For PSVs, the deviation of setpoints is generally small, although its causes are not specified in many instances. (author)

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

Maintenance of a labour safety and ecological safety in chinks at extraction of uranium

International Nuclear Information System (INIS)

Svambaev, Z.A.; Svambaev, E.A.; Sultanbekov, G.A; Tusupbekova, S.T.; Svambaev, A.S.

2010-01-01

The authors of scientific work inform results of research on maintenance of a labour safety and ecological safety in chinks at extraction of uranium. Practical actions on increase of safety and a labour safety in chinks at extraction of uranium in opinion of the author is the practical actions directed on perfection of technological processes, development of means of the control and management of technological processes, modernization of the equipment, the organization of safe workplaces of the personnel. It is necessary to give significant attention to actions connected with improvement of physical protection of radioactive dangerous objects. The basic radiating, toxicological danger at the enterprises underground extractions of uranium are natural atoms uranium - the thorium lines, contained in technological solutions, in finished goods, in radioactive waste products, on a surface of the process equipment, vehicles and packings. In manufacture of uranium use highly toxic substances, such as the concentrated sulfuric acid, hydrogen H 2 O 2 , ammonia water with maintenance - not less than 25 %. The technological circuit of reception sour - oxide natural uranium is represented in the following. The solutions acting from uterus sobered after sedimentation from mechanical impurity and after clarification moves in technical unit sonar where it is possible a sulfuric acid and submit through pump down chinks under pressure to uranium horizon where the productive solution of uranium is formed. The productive solution of uranium with the help of deep pumps through pump out chinks acts on unit of reception of a productive solution, then in modular capacity where there is a process clarification, his ambassador moves on sobered to extraction of uranium that is for processing. On a processing complex the productive solution from modular capacity acts on sobered columns in them occurs sobered uranium from a productive solution on ion exchange pitches or so the sorbent, and

Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

International Nuclear Information System (INIS)

SCHWEHR, B.A.

1999-01-01

This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

Hotline Allegations Involving Contracts for Programmed Depot Maintenance of KC-135 Aircraft

National Research Council Canada - National Science Library

1998-01-01

Introduction. We performed the audit in response to 15 allegations made to the Defense Hotline involving two contracts on the Programmed Depot Maintenance of the KC-135 Aircraft, which Oklahoma City Air logistics...

Maintenance of nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, providing maintenance facilities and equipment, procuring stores and spare parts, selecting and training maintenance personnel, reviewing and controlling plant modifications arising from maintenance, and for generating, collecting and retaining maintenance records. Maintenance shall be subject to quality assurance in all aspects important to safety. Because quality assurance has been dealt with in detail in other Safety Guides, it is only included here in specific instances where emphasis is required. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other maintenance activities or to ensure continuing capability of structures, systems and components important to safety to perform their intended functions

Study on how to evaluate the effectiveness of maintenance activities for giant complex plant system

International Nuclear Information System (INIS)

Aoki, Takayuki

2010-01-01

If we try to check the effectiveness of maintenance activities in nuclear power plant, it is necessary to evaluate plant performance from the viewpoint of nuclear safety and economy. So, in this paper, after the relation among maintenance optimization, maintenance performance targets, maintenance effectiveness indicator and maintenance key parameters important to nuclear safety and economy was made clear, a method to evaluate the effectiveness of maintenance activities was discussed. As a result of consideration, it was concluded that the maintenance effectiveness indicator proposed in this paper can evaluate maintenance effectiveness and can show the direction of improving existing maintenance program because the relation with maintenance performance target and maintenance key parameters is clear. (author)

Configuration management of on-line maintenance

International Nuclear Information System (INIS)

Grantom, C.R.

1996-01-01

Maintenance activities are performed on station equipment to ensure continued safe and reliable performance. Equipment reliability is thereby improved, resulting in greater confidence that the component will be capable of performing its intended (safety) function. Probabilistic Safety Assessments (PSAs) consider equipment reliability and availability to calculate Core Damage Frequency (CDF) and other risk-related values. Since maintenance activities are included in PSA analyses, the effect of equipment outages on CDF can be analyzed. Results from these types of studies can be scaled to reflect different time periods and show the time-dependent impact of planned equipment outages on CDF. These time-dependent impacts on CDF are graphically presented and referred to as ''risk profiles''. Risk profiles are being successfully used at the South Texas Project (STP) to plan preventive maintenance activities and to assess the impact of unplanned maintenance activities on plant safety. At STP, planned maintenance activities are scheduled to minimize the risk impact of unavailable equipment and to prevent the Occurrence of undesirable plant configurations. The features of the risk profiles used at STP enable the evaluation of both work scope and duration of maintenance activities to be evaluated. This is possible since the risk profile illustrates both instantaneous CDF effects and cumulative impacts to CDF

On the concept of e-maintenance: Review and current research

International Nuclear Information System (INIS)

Muller, Alexandre; Crespo Marquez, Adolfo; Iung, Benoit

2008-01-01

The importance of the maintenance function has increased because of its role in keeping and improving system availability and safety, as well as product quality. To support this role, the development of the communication and information technologies has allowed the emergence of the concept of e-maintenance. Within the era of e-manufacturing and e-business, e-maintenance provides the opportunity for a new maintenance generation. As we will discuss later in this paper, e-maintenance integrates existing telemaintenance principles, with Web services and modern e-collaboration principles. Collaboration allows to share and exchange not only information but also knowledge and (e)-intelligence. By means of a collaborative environment, pertinent knowledge and intelligence become available and usable at the right place and time, in order to facilitate reaching the best maintenance decisions. This paper outlines the basic ideas within the e-maintenance concept and then provides an overview of the current research and challenges in this emerging field. An underlying objective is to identify the industrial/academic actors involved in the technological, organizational or management issues related to the development of e-maintenance. Today, this heterogeneous community has to be federated in order to bring up e-maintenance as a new scientific discipline

29 CFR 2201.10 - Maintenance of statistics.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Maintenance of statistics. 2201.10 Section 2201.10 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH REVIEW COMMISSION REGULATIONS IMPLEMENTING THE FREEDOM OF INFORMATION ACT § 2201.10 Maintenance of statistics. (a) The FOIA Disclosure...

Nuclear safety - Topical issues

International Nuclear Information System (INIS)

1995-01-01

The following topical issues related to nuclear safety are discussed: steam generators; maintenance strategies; control rod drive nozzle cracks; core shrouds cracks; sump strainer blockage; fire protection; computer software important for safety; safety during shutdown; operational safety experience; external hazards and other site related issues. 5 figs, 5 tabs

Implemented organisation for subcontracting companies involved in the maintenance of the French nuclear stock - Sheet nr 39

International Nuclear Information System (INIS)

2011-01-01

Every year, some 20,000 subcontracted salaried employees are mobilised for maintenance operations in the French nuclear reactors. Subcontracting is an answer to different needs: specific abilities, the short delay for maintenance during which a reactor is stopped, and which requires a very important contribution of labour, and specialised labour for some interventions. The document evokes a rigorous selection and certification process, and indicates the different specific training which are organised for anyone intervening in a nuclear power plant. It outlines that radiation protection and safety arrangements are the same for all (dosimetry), and that some measurements are performed on some temporary workers. Some data shows that these controls are efficient and that safety is improving

Probabilistic safety assessment support for the maintenance rule at Duke Power Company

International Nuclear Information System (INIS)

Brewer, H. Duncan; Canady, Ken S.

1999-01-01

The Nuclear Regulatory Commission (NRC) published the Maintenance Rule on July 10, 1991 with an implementation date of July 10, 1996 . Maintenance rule implementation at the Duke Power Company has used probabilistic safety assessment (PSA) insights to help focus the monitoring of structures, systems and components (SSC) performance and to ensure that maintenance is effectively performed. This paper describes how the probabilistic risk assessment (PRA) group at the Duke Power Company provides support for the maintenance rule by performing the following tasks: (1) providing a member of the expert panel; (2) determining the risk-significant SSCs; (3) establishing SSC performance criteria for availability and reliability; (4) evaluating past performance and its impact on core damage risk as part of the periodic assessment; (5) providing input to the PRA matrix; (6) providing risk analyses of combinations of SSCs out of service; (7) providing support for the SENTINEL program; and (8) providing support for PSA training. These tasks are not simply tied to the initial implementation of the rule. The maintenance rule must be kept consistent with the current design and operation of the plant. This will require that the PRA models and the many PSA calculations performed to support the maintenance rule are kept up-to-date. Therefore, support of the maintenance rule will be one of the primary roles of the PSA group for the remainder of the life of the plant

A study of adopting maintenance rule under the periodic safety review and reliability centered maintenance program

International Nuclear Information System (INIS)

Kilyoo, Kim

2001-01-01

U.S Maintenance Rule (MR) has three main functions. One is to monitor the performance changes of SSCs (Structure, System, and Component) caused by risk informed applications. Periodic Safety Review (PSR) program is widely adopted in Europe while it is not adopted in U. S. A where MR and new oversight program are instead used. Recently, in Korea, it was determined to adopt PSR, and the first PSR program has started this year for Kori unit 1 as a pilot plant. Also, a traditional Reliability Centered Maintenance (RCM) has been performed for 4 systems of YGN unit 1 and 2 and it will be applied to the other nuclear power plants in Korea. However, since MR is adopting many useful concept of RCM, traditional RCM could not be further performed without being associated with MR. Thus, MR, RCM and PSR have recently become hot issue policies which should be well associated each other in Korea, and this paper suggests a desirable new maintenance process which would embrace the concepts of the three policies, and also discusses whether U.S. MR is necessary even though a PSR program is already adopted, and if necessary, then how cost-effectively it can be introduced to. (author)

A comparative analysis between France and Japan on local governments' involvement in nuclear safety governance

International Nuclear Information System (INIS)

Sugawara, Shin-etsu; Shiroyama, Hideaki

2011-01-01

This paper shows a comparative analysis between France and Japan on the way of the local governments' involvement in nuclear safety governance through some interviews. In France, a law came into force that requires related local governments to establish 'Commision Locale d'Information' (CLI), which means the local governments officially involve in nuclear regulatory activity. Meanwhile, in Japan, related local governments substantially involve in the operation of nuclear facilities through the 'safety agreements' in spite of the lack of legal authority. As a result of comparative analysis, we can point out some institutional input from French cases as follows: to clarify the local governments' roles in the nuclear regulation system, to establish the official channels of communication among nuclear utilities, national regulatory authorities and local governments, and to stipulate explicitly the transparency as a purpose of safety regulation. (author)

Patient involvement in blood transfusion safety: patients' and healthcare professionals' perspective.

Science.gov (United States)

Davis, R; Murphy, M F; Sud, A; Noel, S; Moss, R; Asgheddi, M; Abdur-Rahman, I; Vincent, C

2012-08-01

Blood transfusion is one of the major areas where serious clinical consequences, even death, related to patient misidentification can occur. In the UK, healthcare professional compliance with pre-transfusion checking procedures which help to prevent misidentification errors is poor. Involving patients at a number of stages in the transfusion pathway could help prevent the occurrence of these incidents. To investigate patients' willingness to be involved and healthcare professionals' willingness to support patient involvement in pre-transfusion checking behaviours. A cross-sectional design was employed assessing willingness to participate in pre-transfusion checking behaviours (patient survey) and willingness to support patient involvement (healthcare professional survey) on a scale of 1-7. One hundred and ten patients who had received a transfusion aged between 18 and 93 (60 male) and 123 healthcare professionals (doctors, nurses and midwives) involved in giving blood transfusions to patients. Mean scores for patients' willingness to participate in safety-relevant transfusion behaviours and healthcare professionals' willingness to support patient involvement ranged from 4.96-6.27 to 4.53-6.66, respectively. Both groups perceived it most acceptable for patients to help prevent errors or omissions relating to their hospital identification wristband. Neither prior experience of receiving a blood transfusion nor professional role of healthcare staff had an effect on attitudes towards patient participation. Overall, both patients and healthcare professionals view patient involvement in transfusion-related behaviours quite favourably and appear in agreement regarding the behaviours patients should adopt an active role in. Further work is needed to determine the effectiveness of this approach to improve transfusion safety. © 2012 The Authors. Transfusion Medicine © 2012 British Blood Transfusion Society.

Study on sociological approach to resolve maintenance related social problems

International Nuclear Information System (INIS)

Aoki, Takayuki

2007-01-01

This study proposes a sociological approach to resolve maintenance related social problems. As a result of consideration, the followings were found. (1) In general, solutions to some kinds of questions can be deduced from basic laws using some theories or methodologies in the field of the natural science or engineering. The approach to resolve maintenance related social problems is similar to the approach in the natural science or engineering. (2) The points of view based on fundamental human rights, market principles and community principles, and so on, are very important in resolving maintenance related social problems and can be placed as theories or tools for resolution. (3) If such theories or tools for resolving maintenance related social problems as described above are systematically prepared, it is estimated that it becomes very much easier to resolve maintenance related social problems. (author)

A Study on Human Factors in Maintenance of a Nuclear Power Plant (NPP)

International Nuclear Information System (INIS)

Park, Young Ho; Seong, Poong Hyun

2006-01-01

In human factors research, more attention has been devoted to the operation of a nuclear power plant (NPP) than to their maintenance. However, more NPP incidents are caused by inadequate maintenance rather than by faulty operation. There is a trend in NPP toward introducing digital technology into safety and non-safety systems. This lead to changes of maintenance, and support systems such as diagnosis system, augmentation system and handy terminal will be developed. In this context, it is important to identify tasks of human related to each phase of maintenance and their relation in order to apply those to maintenance. However, there are few researches of human factors in maintenance. This paper studies on framework of cognitive task analysis for developing maintenance support systems

Development of methodologies for optimization of surveillance testing and maintenance of safety related equipment at NPPs. Report of a research coordination meeting. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

This report summarizes the results of the first meeting of the Coordinated Research Programme (CRP) on Development of Methodologies for Optimization of Surveillance Testing and Maintenance of Safety Related Equipment at NPPs, held at the Agency Headquarters in Vienna, from 16 to 20 December 1996. The purpose of this Research Coordination Meeting (RCM) was that all Chief Scientific Investigators of the groups participating in the CRP presented an outline of their proposed research projects. Additionally, the participants discussed the objective, scope, work plan and information channels of the CRP in detail. Based on these presentations and discussions, the entire project plan was updated, completed and included in this report. This report represents a common agreed project work plan for the CRP. Refs, figs, tabs.

Regulatory issues in the maintenance of Argentine nuclear power plants

International Nuclear Information System (INIS)

Castro, E.; Caruso, G.

1997-01-01

The influence of maintenance activities upon nuclear safety and their relevance as means to detect and prevent aging make them play an outstanding role among the fields of interest of the Argentine nuclear regulatory body (ENREN). Such interest is reinforced by the fact that the data obtained during maintenance are used - among other - as inputs in the Probabilistic Safety Analyses required for those nuclear power plants. This paper provides a brief description of the original requirements by the regulatory body concerning maintenance, of the factors that led to review the criteria involved in such requirements and of the key items identified during the reviewing process. The latter shall be taken into account in the maintenance regulatory policy, for the consequent issue of new requirements from the utilities and for the eventual publication of a specific regulatory standard. (author)

Reliability of containment and safety-related structures

International Nuclear Information System (INIS)

Nessim, M.A.

1995-09-01

A research program on Reliability of Containment and Safety-related Structures has been developed and is described in this document. This program is designed to support AECB's regulatory activities aimed at ensuring the safety of these structures. These activities include evaluating submissions by operators and requesting special assessments when necessary. The results of the proposed research will also be useful in revising and enhancing the CSA design standards for containment and safety-related structures. The process of developing the research program started with an information collection and review phase. The sources of information included C-FER's previous work in the area, various recent research publications, regulatory documents and relevant design standards, and a detailed discussion with AECB staff. The second step was to outline the process of reliability evaluation, and identify the required models and parameters. Comparison between the required and available information was used to identify gaps in the state-of-the-art, and the research program was designed to fill these gaps. The program is organized in four major topics, namely: development of an approach for reliability analysis; compilation and development of the required analysis tools; application to specific problems related to design, assessment, maintenance and testing of structures; and testing and validation. It is suggested that the program should be supported by an on-going process of communication and consultation between AECB staff and industry experts. This will lend credibility to the results and facilitate their future application. (author). 1 fig

Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Maintenance Area

International Nuclear Information System (INIS)

1993-01-01

Tiger Team Assessments and Technical Safety Appraisals (TSA) were reviewed and evaluated for concerns in the Maintenance Area (MA). Two hundred and thirty one (231) maintenance concerns were identified by the Tiger Team Assessments and TSA reports. These recurring concerns appear below. A summary of the Noteworthy Practices that were identified and a compilation of the maintenance concerns for each performance objective that were not considered as recurring are also included. Where the Tiger Team Assessment and TSA identified the operating contractor or facility by name, the concern has been modified to remove the name while retaining the intent of the comment

Risk-based equipment removal guide for on-line maintenance at PSE ampersand G

International Nuclear Information System (INIS)

Knoll, A.; Smith, C.; Pollock, J.

1995-01-01

On-line maintenance plays an important role in achieving safe and reliable power generation in a nuclear power plant. However, maintenance, if not properly planned and performed, may also be an important contributor to plant risk. Therefore, plant-specific procedures are needed for equipment removal from service to enhance the benefits of on-line maintenance and minimize the risks involved. The problem is to identify and implement the most effective on-line maintenance policy in the form of a proceduralized guide to assure plant safety under various operation and maintenance constraints. This paper presents a methodology to develop plant-specific on-line maintenance strategies and acceptance criteria using a multivariate safety approach based on risk assessment. Based on plant-specific data as modeled in the individual plant evaluation (IPE) and the updated probabilistic safety assessment (PSA), the risk-based methodology is currently being applied to the development of proceduralized equipment removal guides at Hope Creek and Salem units 1 and 2 of Public Service Electric and Gas Company (PSE ampersand G)

Program integration of predictive maintenance with reliability centered maintenance

International Nuclear Information System (INIS)

Strong, D.K. Jr; Wray, D.M.

1990-01-01

This paper addresses improving the safety and reliability of power plants in a cost-effective manner by integrating the recently developed reliability centered maintenance techniques with the traditional predictive maintenance techniques of nuclear power plants. The topics of the paper include a description of reliability centered maintenance (RCM), enhancing RCM with predictive maintenance, predictive maintenance programs, condition monitoring techniques, performance test techniques, the mid-Atlantic Reliability Centered Maintenance Users Group, test guides and the benefits of shared guide development

Basic Characteristics of Human Erroneous Actions during Test and Maintenance Activities Leading to Unplanned Reactor Trips

International Nuclear Information System (INIS)

Kim, Jae Whan; Park, Jin Kyun

2010-01-01

Test and maintenance (T and M) activities of nuclear power plants are essential for sustaining the safety of a power plant and maintaining the reliability of plant systems and components. However, the potential of human errors during T and M activities has also the potential to induce unplanned reactor trips or power derate or making safety-related systems unavailable. According to the major incident/accident reports of nuclear power plants in Korea, contribution of human errors takes up about 20% of the total events. The previous study presents that most of human-related unplanned reactor trip events during normal power operation are associated with T and M activities (63%), which are comprised of plant maintenance activities such as a 'periodic preventive maintenance (PPM)', a 'planned maintenance (PM)' and a 'corrective maintenance (CM)'. This means that T and M activities should be a major subject for reducing the frequency of human-related unplanned reactor trips. This paper aims to introduce basic characteristics of human erroneous actions involved in the test and maintenance-induced unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants. The basic characteristics are described by dividing human erroneous actions into planning-based errors and execution-based errors. For the events associated with planning failures, they are, firstly, classified according to existence of the work procedure and then described for what aspects of the procedure or work plan have deficiency or problem. On the other hand, for the events associated with execution failures, they are described from the aspect of external error modes

Fatigue-related crashes involving express buses in Malaysia: will the proposed policy of banning the early-hour operation reduce fatigue-related crashes and benefit overall road safety?

Science.gov (United States)

Mohamed, Norlen; Mohd-Yusoff, Mohammad-Fadhli; Othman, Ilhamah; Zulkipli, Zarir-Hafiz; Osman, Mohd Rasid; Voon, Wong Shaw

2012-03-01

Fatigue-related crashes have long been the topic of discussion and study worldwide. The relationship between fatigue-related crashes and time of day is well documented. In Malaysia, the possibility of banning express buses from operating during the early-hours of the morning has emerged as an important consideration for passenger safety. This paper highlights the findings of an impact assessment study. The study was conducted to determine all possible impacts prior to the government making any decision on the proposed banning. This study is an example of a simple and inexpensive approach that may influence future policy-making process. The impact assessment comprised two major steps. The first step involved profiling existing operation scenarios, gathering information on crashes involving public express buses and stakeholders' views. The second step involved a qualitative impact assessment analysis using all information gathered during the profiling stage to describe the possible impacts. Based on the assessment, the move to ban early-hour operations could possibly result in further negative impacts on the overall road safety agenda. These negative impacts may occur if the fundamental issues, such as driving and working hours, and the need for rest and sleep facilities for drivers, are not addressed. In addition, a safer and more accessible public transportation system as an alternative for those who choose to travel at night would be required. The proposed banning of early-hour operations is also not a feasible solution for sustainability of express bus operations in Malaysia, especially for those operating long journeys. The paper concludes by highlighting the need to design a more holistic approach for preventing fatigue-related crashes involving express buses in Malaysia. Copyright © 2011 Elsevier Ltd. All rights reserved.

Final hazard classification and auditable safety analysis for the 308 Building Complex during post-deactivation surveillance and maintenance mode

International Nuclear Information System (INIS)

Dexheimer, D.

1996-11-01

This document summarizes the inventories of radioactive and hazardous materials present within the 308 Building Complex, and presents the hazard evaluation methodology used to prepare the hazard classification for the Complex. The complex includes the 308 Building (process area and office facilities) and the 308 Building Annex, which includes the former Neutron Radiography Facility containing a shutdown (and partially decommissioned) reactor. This document applies to the post-deactivation surveillance and maintenance mode only, and provides an authorization basis limited to surveillance and maintenance activities. This document does not authorize decommissioning and decontamination activities, movement of fissile materials, modification to facility confinement structures, nor the introduction or storage of additional radionuclides in the 308 Building Complex. This document established a final hazard classification and identifies appropriate and adequate safety functions and controls to reduce or mitigate the risk associated with the surveillance and maintenance mode. The most consequential hazard event scenario is a postulated unmitigated release from an earthquake event involving the entire complex. That release is equivalent to 30% of the Nuclear Category 3 threshold adjusted as allowed by DOE-STD-1027-92 (DOE 1992). The dominant isotopes are 239 Pu, 240 Pu, and 241 Am in the gloveboxes

Improving regulatory oversight of maintenance programs

International Nuclear Information System (INIS)

Cook, S.

2008-01-01

Safe nuclear power plant operation requires that risks due to failure or unavailability of Structures, Systems and Components (SSCs) be minimized. Implementation of an effective maintenance program is a key means for achieving this goal. In its regulatory framework, the important relationship between maintenance and safety is acknowledged by the CNSC. A high level maintenance program requirement is included in the Class I Facilities Regulations. In addition, the operating licence contains a condition based on the principle that the design function and performance of SSCs needs to remain consistent with the plant's design and analysis documents. Nuclear power plant licensees have the primary responsibility for safe operation of their facilities and consequently for implementation of a successful maintenance program. The oversight role of the Canadian Nuclear Safety Commission (CNSC) is to ensure that the licensee carries out that responsibility. The challenge for the CNSC is how to do this consistently and efficiently. Three opportunities for improvement to regulatory maintenance oversight are being pursued. These are related to the regulatory framework, compliance verification inspection activities and monitoring of self-reporting. The regulatory framework has been improved by clarifying expectations through the issuance of S-210 'Maintenance Programs for Nuclear Power Plants'. Inspection activities have been improved by introducing new maintenance inspections into the baseline program. Monitoring is being improved by making better use of self-reported and industry produced maintenance related performance indicators. As with any type of program change, the challenge is to ensure the consistent and optimal application of regulatory activities and resources. This paper is a summary of the CNSC's approach to improving its maintenance oversight strategy. (author)

Stakeholder involvement in building and maintaining radiation safety infrastructure in Latvia: The case studies

International Nuclear Information System (INIS)

Eglajs, A.; Salmins, A.

2003-01-01

This paper comprises the assessment of interests for central and local governments, different authorities, public and commercial companies, political parties and non-governmental organizations, organised and ad-hock groups of public, which could contribute to development and maintenance of infrastructure for radiation safety, general environmental protection, as well as for public health among other similar fields. Understanding of these interests allows to be prepared for eventual demonstrations or publications against decisions about significant modifications of infrastructure and provides ideas how to explain needs of financial and human resources for maintaining of supervisory system and management of major facilities, which are vital for safety infrastructure. Two case studies are presented in this report related to modification of the framework law and the preparation of radioactive waste management strategy. (author)

49 CFR 214.513 - Retrofitting of existing on-track roadway maintenance machines; general.

Science.gov (United States)

2010-10-01

... maintenance machines; general. 214.513 Section 214.513 Transportation Other Regulations Relating to... SAFETY On-Track Roadway Maintenance Machines and Hi-Rail Vehicles § 214.513 Retrofitting of existing on-track roadway maintenance machines; general. (a) Each existing on-track roadway maintenance machine...

Research priorities at the European Commission in relation to maintenance optimization and nuclear power plant life management

International Nuclear Information System (INIS)

Contri, Paolo

2009-01-01

Analysis of experience in many countries operating nuclear power plants (NPPs) suggests that, while differences in long term operation (LTO) programs are mainly related to the various national regulatory processes, the main features and basic technical requirements are similar. The implementation of these however needs reshaping in an integrated plant life management (PLIM) framework, bearing in mind the specific safety implications of LTO. R and D is essential to support this process, not only for long term extrapolation of the component integrity and behaviour, but also for a proper maintenance system and for an adequate management structure ensuring effective management strategies at plant level, able to address organisational issues, spare part management, staff ageing, component obsolescence, etc. This is recognised by the European Commission, which supports R and D in targeted areas in the framework of the EURATOM programme, both by “direct actions” i.e. projects managed and executed by its Directorate General Joint Research Centers (JRC) and by indirect actions i.e. funding of selected projects, managed by the Directorate General Research (RTD). This paper outlines the JRC's priorities in the current 7th Framework Programme in relation to R and D tasks for maintenance and ISI to support the highest safety level at member's NPPs and appropriate decision-making tools for the optimisation of these programs. A newly developed UE model for PLIM, also integrating maintenance optimisation issues, is presented for further discussion. (author)

Maintenance of nuclear power plants

International Nuclear Information System (INIS)

Migaud, D.; Hutin, J.P.; Jouette, I.; Eymond, P.; Devie, P.; Cudelou, C.; Magnier, S.; Frydman, M.

2016-01-01

This document gathers different articles concerning the maintenance of the French nuclear power plants. The first article analyses the impact of the recent law on the energetic transition that sets the share of nuclear power at 50% of the electricity produced by 2025. A consequence may be the decommissioning of 17 to 20 reactors by 2025 and the huge maintenance program called 'Grand Carenage' whose aim is to extend operating life over 40 years will have to be re-considered in order to avoid useless expenses. The second article shows that in 2015 the French nuclear reactor fleet got very good results in terms of availability and safety. There were 49 scheduled outages and among them some ended ahead of time. The third article describes the specificities of the maintenance of a nuclear power plant, for instance the redundancy of some systems implies that maintenance has to deal with systems that have never functioned but must be ready to operate at any moment. Another specificity is the complexity of a nuclear power plant that implies an essential phase of preparation for maintenance operations. Because of safety requirements any maintenance operation has to be controlled, checked and may provide feedback. The fourth article presents the 'Grand Carenage' maintenance program that involves the following operations: the replacement of steam generators, the re-tubing of condensers, the replacement of the filtering drums used for cooling water, the testing of the reactor building, the hydraulic test of the primary circuit and the inspection of the reactor vessel. The fifth article focuses on the organization of the work-site for maintenance operations and the example of the Belleville-sur-Loire is described in the sixth article. Important maintenance operations like 'Grand Carenage' requires a strong collaboration with a network of specialized enterprises and as no reactor (except Flamanville EPR) is being built in France, maintenance

Maintenance Support System Development for Maintenance Personnel in Nuclear Power Plants

International Nuclear Information System (INIS)

Yim, Ho Bin; Kim, In; Lee, Seung Min; Seong, Poong Hyun

2009-01-01

As plants or factories get old, the number of maintenance activities increases, and so does the necessity of maintenance itself. Industries have adopted the latest technologies such as RFID, wireless sensor networking, and augmented reality to develop systems which increase human performances as well as productivity. Due to safety related concerns, nuclear power industries have been reluctant to use these fancy technologies. However, from the economics point of view, it is necessary to take advantages of novel technologies. This empirical study considers not only ergonomics view, but also the economics view when building maintenance support systems. This paper introduces brief features of five subsystems which were built to reduce human errors and advantages when each system successfully reduces those human errors

Maintenance Support System Development for Maintenance Personnel in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Yim, Ho Bin; Kim, In; Lee, Seung Min; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2009-05-15

As plants or factories get old, the number of maintenance activities increases, and so does the necessity of maintenance itself. Industries have adopted the latest technologies such as RFID, wireless sensor networking, and augmented reality to develop systems which increase human performances as well as productivity. Due to safety related concerns, nuclear power industries have been reluctant to use these fancy technologies. However, from the economics point of view, it is necessary to take advantages of novel technologies. This empirical study considers not only ergonomics view, but also the economics view when building maintenance support systems. This paper introduces brief features of five subsystems which were built to reduce human errors and advantages when each system successfully reduces those human errors.

Nuclear power and safety

International Nuclear Information System (INIS)

Chidambaram, R.

1992-01-01

Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

Maintenance and test strategies to optimize NPP equipment performance

International Nuclear Information System (INIS)

Mayer, S.; Tomic, B.

2000-01-01

This paper proposes an approach to maintenance optimization of nuclear power plant components, which can help to increase both safety and availability. In order to evaluate the benefits of preventive maintenance on a quantitative basis, a software code has been developed for component performance and reliability simulation of safety related nuclear power plant equipment. A three state Markov model will be introduced, considering a degraded state in addition to an operational state and a failed state. (author)

Maintenance optimization of the Ignalina NPP safety systems

International Nuclear Information System (INIS)

Zuokas, D.; Augutis, J.

2000-01-01

This paper represents some theses and mathematical approach to optimization of technical specification problems of the diesel generators system (DGS) at the Ignalina NPP (INPP) in Lithuania. Analysis unites three chapters, each attributed to the solving of related problems: dependency of the Core Damage Frequency (CDF) on DGS test interval (Chapter 2), analysis and comparison of two different maintenance strategies for DGS (Chapter 3), DGS test interval's optimisation (averaged loss function minimisation) taking into consideration maintenance and DGS failure's consequence costs (Chapter 4). The mathematical model was developed which lets to estimate DGS failure probability, the averaged loss function value and study the influence of different parameters into final results. (author)

Safety Behavior After Extinction Triggers a Return of Threat Expectancy

NARCIS (Netherlands)

van Uijen, S.L.; Leer, A.; Engelhard, I.M.

2018-01-01

Safety behavior is involved in the maintenance of anxiety disorders, presumably because it prevents the violation of negative expectancies. Recent research showed that safety behavior is resistant to fear extinction. This fear conditioning study investigated whether safety behavior after fear

Global optimization of maintenance and surveillance testing based on reliability and probabilistic safety assessment. Research project

International Nuclear Information System (INIS)

Martorell, S.; Serradell, V.; Munoz, A.; Sanchez, A.

1997-01-01

Background, objective, scope, detailed working plan and follow-up and final product of the project ''Global optimization of maintenance and surveillance testing based on reliability and probabilistic safety assessment'' are described

Maintenance of a commercial fusion power station and its implications for safety

International Nuclear Information System (INIS)

Sherwood, D.V.; Pearcey, J.; Thompson, H.M.; Sublet, J.-Ch.; Taylor, N.P.

1994-11-01

A recent study was undertaken to identify a maintenance scheme which would lead to an acceptable level of availability for a future commercial fusion power station. It was thought that a scheme involving the servicing of the divertor through dedicated maintenance ports provided in each sector of the torus and the sub-division of the blanket in both the radial and poloidal directions to allow it to be handled through two radial access ports, could lead to a plant availability in the order of 80% (including 7% unplanned shutdown) i.e. comparable with that expected from APWRs. The method of blanket replacement proposed is radically different from that of the ITER CDA. The maintenance scheme has now been developed sufficiently to allow the main potential hazards requiring control during maintenance to be identified. Taking these into account, a more accurate assessment of the plant availability has been possible which confirms that 80% should be possible. The scheme is considered to present little risk to the maintenance staff and with proper safeguards there would be little potential for the spread of contamination. (author)

Auditable safety analysis for the surveillance and maintenance of the REDOX complex

International Nuclear Information System (INIS)

Cuneo, V.J.

1997-02-01

The Reduction-Oxidation (REDOX) Complex is an inactive surplus facility that contains two former fuel processing facilities (the 202-S Canyon Building and the 233-S Plutonium Concentration Facility) and a number of ancillary support structures. Deactivation started in 1967 and was completed in 1969 when the plant was transferred to surveillance and maintenance (S ampersand M). This document provides the auditable safety analysis (ASA) for the post-deactivation, long-term S ampersand M phase of the above grade structures of the REDOX Complex. The S ampersand M phase is conducted for the following reasons: (1) Maintain confinement of residual inventories of radioactive materials and other contaminants until the facility is ultimately dispositioned, (2) Prevent deterioration of confinement structures, (3) Respond to potential accident conditions requiring response and mitigation, (4) Provide for the safety of workers involved in the S ampersand M phase, and (5) Provide the basis for evaluation and selection of ultimate disposal alternatives. The ability of the existing facilities to withstand the effects of natural phenomena hazard events is evaluated and the active support systems used to maintain ventilation and/or prevent the spread of contamination are described. This auditable safety analysis document evaluates the routinely required S ampersand M activities (i.e., the S ampersand M of facility barriers, equipment, structures, and postings [including repair and upgrade]; measures to identify, remove, or repair damaged asbestos; measures to identify, remove, or appropriately manage existing containers of hazardous substances; and the performance of spill response measures as needed). For the REDOX Complex, the movement of cell cover blocks is also evaluated, as D-cell cover block was removed a number of years ago and should be replaced. The type and nature of the hazards presented by the REDOX Complex and the REDOX-specific controls required to maintain these

An initial examination of aging related degradation in turbine drives and governors for safety related pumps

International Nuclear Information System (INIS)

Cox, D.F.

1991-01-01

This study is being performed to examine the relationship between time dependent degradation, and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized water reactor (PWR) plants, and the Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant Injection (HPCI) systems for Boiling Water Reactor (BWR) facilities. This research has been conducted by examining current information in NPRDS, reviewing Licensee Event Reports, and thoroughly investigating contacts with operating plant personnel, and by personal observation. The reported information was reviewed to determine the cause of the event and the method of discovery. From this data attempts have been made at determining the predictability of events and possible preventive measures that may be implemented. Findings in a recent study on the Auxiliary Feedwater System (NUREG/CR-5404) indicate that the turbine drive is the single largest contributor to AFW system degradation. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design seem to indicate that this equipment can be a reliable component in safety systems

Maintenance philosophy and program at Cernavoda NPP

International Nuclear Information System (INIS)

Bobos, M.; Enciu, G.

1994-01-01

Maintenance plays a key role in ensuring safe and reliable operation. An effective maintenance program should ensure that installed equipment operates when needed and the equipment malfunctions or deficiencies are corrected in time and rarely recur. Maintenance includes not only the activities traditionally associated with identifying or correcting current or potential equipment deficiencies but also extends to supporting technical functions for the conduct of these activities (for example, engineering, technical support, chemistry control, radiological protection, industrial safety and training). The maintenance management program should clearly define the relationship among these supporting groups as it is related to overall plant maintenance and promotes the concept of a successful integrated team effort. (Author)

Proposal for the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system

CERN Document Server

2005-01-01

This document concerns the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system. The Finance Committee is invited to agree to the negotiation of a contract with the consortium CEGELEC CENTRE EST (FR) â?" CEGELEC (NL) â?" SEMER (FR), the lowest bidder, for the supply, installation, commissioning and maintenance for five years of the LHC access safety system for a total amount of 891 423 euros (1 367 633 Swiss francs), subject to revision for inflation for the maintenance of the system from 1 January 2007, with an option for the supply of safety PLCs for a total amount of 894 951 euros (1 373 046 Swiss francs), not subject to revision, bringing the total amount to 1 786 374 euros (2 740 679 CHF).The rate of exchange used is that stipulated in the tender.

Review of maintenance personnel practices at nuclear power plants

International Nuclear Information System (INIS)

Chockie, A.D.; Badalamente, R.V.; Hostick, C.J.; Vickroy, S.C.; Bryant, J.L.; Imhoff, C.H.

1984-05-01

As part of the Nuclear Regulatory Commission (NRC) sponsored Maintenance Qualifications and Staffing Project, the Pacific Northwest Laboratory (PNL) has conducted a preliminary assessment of nuclear power plant (NPP) maintenance practices. As requested by the NRC, the following areas within the maintenance function were examined: personnel qualifications, maintenance training, overtime, shiftwork and staffing levels. The purpose of the assessment was to identify the primary safety-related problems that required further analysis before specific recommendations can be made on the regulations affecting NPP maintenance operations

Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

International Nuclear Information System (INIS)

Nummi, O.; Kylloenen, J.; Eurajoki, T.

2012-12-01

This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90 Sr followed by long-lived nuclides 129 I and 108 mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

Task types and error types involved in the human-related unplanned reactor trip events

International Nuclear Information System (INIS)

Kim, Jae Whan; Park, Jin Kyun

2008-01-01

In this paper, the contribution of task types and error types involved in the human-related unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants are analysed in order to establish a strategy for reducing the human-related unplanned reactor trips. Classification systems for the task types, error modes, and cognitive functions are developed or adopted from the currently available taxonomies, and the relevant information is extracted from the event reports or judged on the basis of an event description. According to the analyses from this study, the contributions of the task types are as follows: corrective maintenance (25.7%), planned maintenance (22.8%), planned operation (19.8%), periodic preventive maintenance (14.9%), response to a transient (9.9%), and design/manufacturing/installation (6.9%). According to the analysis of the error modes, error modes such as control failure (22.2%), wrong object (18.5%), omission (14.8%), wrong action (11.1%), and inadequate (8.3%) take up about 75% of the total unplanned trip events. The analysis of the cognitive functions involved in the events indicated that the planning function had the highest contribution (46.7%) to the human actions leading to unplanned reactor trips. This analysis concludes that in order to significantly reduce human-induced or human-related unplanned reactor trips, an aide system (in support of maintenance personnel) for evaluating possible (negative) impacts of planned actions or erroneous actions as well as an appropriate human error prediction technique, should be developed

Task types and error types involved in the human-related unplanned reactor trip events

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Whan; Park, Jin Kyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

In this paper, the contribution of task types and error types involved in the human-related unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants are analysed in order to establish a strategy for reducing the human-related unplanned reactor trips. Classification systems for the task types, error modes, and cognitive functions are developed or adopted from the currently available taxonomies, and the relevant information is extracted from the event reports or judged on the basis of an event description. According to the analyses from this study, the contributions of the task types are as follows: corrective maintenance (25.7%), planned maintenance (22.8%), planned operation (19.8%), periodic preventive maintenance (14.9%), response to a transient (9.9%), and design/manufacturing/installation (6.9%). According to the analysis of the error modes, error modes such as control failure (22.2%), wrong object (18.5%), omission (14.8%), wrong action (11.1%), and inadequate (8.3%) take up about 75% of the total unplanned trip events. The analysis of the cognitive functions involved in the events indicated that the planning function had the highest contribution (46.7%) to the human actions leading to unplanned reactor trips. This analysis concludes that in order to significantly reduce human-induced or human-related unplanned reactor trips, an aide system (in support of maintenance personnel) for evaluating possible (negative) impacts of planned actions or erroneous actions as well as an appropriate human error prediction technique, should be developed.

Maintenance Policy in Public-Transport Involving Government Subsidy

Science.gov (United States)

Pasaribu, U. S.; Bayuzetra, Y.; Gunawan, L. E.; Husniah, H.

2018-02-01

A public transport with government subsidy is considered to encourage the sustainability of the transportation. The transportations revenue is determined by the maximum of the uptimes of the vehicle. In this paper, we study a one-dimensional maintenance policy for new vehicle which is characterized by age parameter. We consider that the degradation of the vehicle is affected by the age of the vehicle, and modelled by using a one-dimensional approach. The owner performs both preventive and corrective maintenance actions, and the preventive maintenance action will reduce the vehicle failure rate and hence it will decrease the corrective maintenance cost during the life time of the vehicle. The decision problem for the owner is to find the optimal preventive maintenance time of the vehicle of each subsidy option offered by maximizing the expected profit for each subsidy.

Track 6: safety and risk management. Plant operational risk management. Plant Configuration Risk Assessment Methodology Development for Periodic Maintenance

International Nuclear Information System (INIS)

Yang, Huichang; Chung, Chang Hyun; Sung, Key Yong

2001-01-01

As the operation experiences of nuclear power plants (NPPs) in Korea accumulate and NPP safety functions become enhanced, the role of stable and optimal NPP operation within acceptable safety criteria becomes important at present. To accomplish the goal of safe and optimal operation, maintenance and its related activities should be regarded as the issues of most concern. Studies of methodologies for maintenance improvement and optimization have focused on system performance rather than on the hardware itself. From this point of view, the probabilistic methods are most useful. In terms of risk including core damage frequency and unavailability, the cause that might impact plant safety during normal maintenance activities can be identified and evaluated effectively. The results from these probabilistic analyses can provide insightful information for the reallocation of risk-contributing maintenance activity. This information can be utilized in a way that separates the significant risk-contributing maintenance activities from each other unless they are timely related. In Korea, the risk-monitoring program for operating NPPs is under development and will be implemented in 2003. To accomplish the risk-monitoring program objectives, suitable risk evaluation methods should be developed before the implementation of the risk-monitoring program. The plant configuration assessment methodology was developed for these reasons, and this method is to incorporate the field experiences into the risk calculation exactly within the limit of probabilistic methods. During normal plant operation, the plant operational risk changes frequently depending on the status of the plant system and the arrangement of the components. Specific plant systems or components are typically removed from service because of random equipment failure, planned preventive/predictive maintenance, corrective maintenance, surveillance testing, and operational bypass activities, and such events usually impact the

Six Sigma methodology as a road to intelligent maintenance

Directory of Open Access Journals (Sweden)

Michał Zasadzień

2017-06-01

Full Text Available An enterprise which is managed in a modern way should be based on the concept of knowledge management. It is particularly important in the case of processes related to facility maintenance, where the efficiency and effectiveness of work is directly connected with the employees’ knowledge. Improvement of processes involved in facility maintenance has a real influence on the productivity of a manufacturing enterprise. High accessibility of technical equipment and its correct functioning influence not only production efficiency but also the quality of products and the safety of operators. The article is a description of an attempt to implement one of quality engineering methods for improving the facility maintenance process. The author decided to use the 8D method to shorten the duration of downtimes caused by breakdowns. Owing to the conducted analysis and the implementation of the improvement and preventive actions, we were able to shorten the duration of a downtime of a machine having a crucial importance for the company. Investigations and implementation were conducted in one of Silesian production plants.

Soldering and brazing safety guide: A handbook on space practice for those involved in soldering and brazing

Science.gov (United States)

This manual provides those involved in welding and brazing with effective safety procedures for use in performance of their jobs. Hazards exist in four types of general soldering and brazing processes: (1) cleaning; (2) application of flux; (3) application of heat and filler metal; and (4) residue cleaning. Most hazards during those operations can be avoided by using care, proper ventilation, protective clothing and equipment. Specific process hazards for various methods of brazing and soldering are treated. Methods to check ventilation are presented as well as a check of personal hygiene and good maintenance practices are stressed. Several emergency first aid treatments are described.

Status of online maintenance in the world

International Nuclear Information System (INIS)

Mizumachi, Wataru; Kobayashi, Masahide

2009-01-01

In many countries, online maintenance has been already introduced. Especially in US, online maintenance has been introduced to many nuclear plants which has (N+1) redundant safety systems as Japanese plants. There experience will contribute us to discuss how to introduce online maintenance in Japan. In IAEA's nuclear safety criteria and guidance, it is recognized that the outage of one safety system for maintenance is usual operation. This is normal sense in the world. In US, the risk when online maintenance is done is controlled mainly by PRA. We have to discuss how to introduce online maintenance in JAPAN under these conditions in the world. (author)

IAEA activity related to safety of nuclear desalination

International Nuclear Information System (INIS)

Gasparini, M.

2000-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

Systematic analysis and prevention of human originated common cause failures in relation to maintenance activities at Finnish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Laakso, K. [VTT Industrial Systems, Espoo (Finland)

2006-12-15

The focus in human reliability analysis of nuclear power plants has traditionally been on human performance in disturbance conditions. On the other hand, human maintenance failures and design deficiencies, remained latent in the system, have an impact on the severity of a disturbance, e.g. by disabling safety-related equipment on demand. Especially common cause failures (CCFs) of safety related systems can affect the core damage risk to a significant extent. The topic has been addressed in Finnish studies, where experiences of latent human errors have been searched and analysed systematically from the maintenance history stored in the the power plant information systems of the Loviisa and Olkiluoto NPPs. Both the single and multiple errors (CCFs) were classified in detail and documented as error and event reports. The human CCFs involved human, organisational and technical factors. The review of the analysed single and multiple errors showed that instrumentation and control and electrical equipment are more prone to human error caused failure events than the other maintenance objects. The review of the analysed experience showed that most errors stem from the refuelling and maintenance outage periods. More than half of the multiple errors from the outages remained latent to the power operating periods. The review of the analysed multiple errors showed that difficulties with small plant modifications and planning of maintenance and operability were significant sources of common cause failures. The most dependent human errors originating from small modifications could be reduced by a more tailored planning and coverage of their start-up testing programs. Improvements could also be achieved by identifying better in work planning from the operating experiences those complex or intrusive repair and preventive maintenance work tasks and actions which are prone to errors. Such uncertain cases in important equipment require a more tailored work planning of the installation

Systematic analysis and prevention of human originated common cause failures in relation to maintenance activities at Finnish nuclear power plants

International Nuclear Information System (INIS)

Laakso, K.

2006-12-01

The focus in human reliability analysis of nuclear power plants has traditionally been on human performance in disturbance conditions. On the other hand, human maintenance failures and design deficiencies, remained latent in the system, have an impact on the severity of a disturbance, e.g. by disabling safety-related equipment on demand. Especially common cause failures (CCFs) of safety related systems can affect the core damage risk to a significant extent. The topic has been addressed in Finnish studies, where experiences of latent human errors have been searched and analysed systematically from the maintenance history stored in the the power plant information systems of the Loviisa and Olkiluoto NPPs. Both the single and multiple errors (CCFs) were classified in detail and documented as error and event reports. The human CCFs involved human, organisational and technical factors. The review of the analysed single and multiple errors showed that instrumentation and control and electrical equipment are more prone to human error caused failure events than the other maintenance objects. The review of the analysed experience showed that most errors stem from the refuelling and maintenance outage periods. More than half of the multiple errors from the outages remained latent to the power operating periods. The review of the analysed multiple errors showed that difficulties with small plant modifications and planning of maintenance and operability were significant sources of common cause failures. The most dependent human errors originating from small modifications could be reduced by a more tailored planning and coverage of their start-up testing programs. Improvements could also be achieved by identifying better in work planning from the operating experiences those complex or intrusive repair and preventive maintenance work tasks and actions which are prone to errors. Such uncertain cases in important equipment require a more tailored work planning of the installation

MPV17-related mitochondrial DNA maintenance defect: New cases and review of clinical, biochemical, and molecular aspects.

Science.gov (United States)

El-Hattab, Ayman W; Wang, Julia; Dai, Hongzheng; Almannai, Mohammed; Staufner, Christian; Alfadhel, Majid; Gambello, Michael J; Prasun, Pankaj; Raza, Saleem; Lyons, Hernando J; Afqi, Manal; Saleh, Mohammed A M; Faqeih, Eissa A; Alzaidan, Hamad I; Alshenqiti, Abduljabbar; Flore, Leigh Anne; Hertecant, Jozef; Sacharow, Stephanie; Barbouth, Deborah S; Murayama, Kei; Shah, Amit A; Lin, Henry C; Wong, Lee-Jun C

2018-04-01

Mitochondrial DNA (mtDNA) maintenance defects are a group of diseases caused by deficiency of proteins involved in mtDNA synthesis, mitochondrial nucleotide supply, or mitochondrial dynamics. One of the mtDNA maintenance proteins is MPV17, which is a mitochondrial inner membrane protein involved in importing deoxynucleotides into the mitochondria. In 2006, pathogenic variants in MPV17 were first reported to cause infantile-onset hepatocerebral mtDNA depletion syndrome and Navajo neurohepatopathy. To date, 75 individuals with MPV17-related mtDNA maintenance defect have been reported with 39 different MPV17 pathogenic variants. In this report, we present an additional 25 affected individuals with nine novel MPV17 pathogenic variants. We summarize the clinical features of all 100 affected individuals and review the total 48 MPV17 pathogenic variants. The vast majority of affected individuals presented with an early-onset encephalohepatopathic disease characterized by hepatic and neurological manifestations, failure to thrive, lactic acidemia, and mtDNA depletion detected mainly in liver tissue. Rarely, MPV17 deficiency can cause a late-onset neuromyopathic disease characterized by myopathy and peripheral neuropathy with no or minimal liver involvement. Approximately half of the MPV17 pathogenic variants are missense. A genotype with biallelic missense variants, in particular homozygous p.R50Q, p.P98L, and p.R41Q, can carry a relatively better prognosis. © 2017 Wiley Periodicals, Inc.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Maintenance work management system

International Nuclear Information System (INIS)

Kanai, T.; Takahashi, Y.; Takahashi, K.; Nishino, M.; Takeshige, R.

2000-01-01

The maintenance work management system supports the efficient drawing up of various documents for the maintenance work at nuclear power stations and the speeding up of the permission procedure. In addition, it improves the quality assurance of the safety and reliability of the maintenance work. Key merits of the system are: 1. Efficiently drawing up various documents for the maintenance work by using the stored data for the previous maintenance work and the pipe and instrument diagram (P and ID) data. 2. Supporting the management work for the completion of maintenance work safety by using the isolation information stored on the computer system. 3. Speeding up the permission procedure by electronic mail and electronic permission. 4. Displaying additional information such as the specifications of equipment, maintenance result, and maintenance plan by linking up with the database of another system. 5. Reducing the cost of hardware devices by using client/server network configurations of personal computers and a personal computer server. (author)

An analysis of human maintenance failures of a nuclear power plant

International Nuclear Information System (INIS)

Pyy, P.

2000-01-01

In the report, a study of faults caused by maintenance activities is presented. The objective of the study was to draw conclusions on the unplanned effects of maintenance on nuclear power plant safety and system availability. More than 4400 maintenance history reports from the years 1992-1994 of Olkiluoto BWR nuclear power plant (NPP) were analysed together with the maintenance personnel. The human action induced faults were classified, e.g., according to their multiplicity and effects. This paper presents and discusses the results of a statistical analysis of the data. Instrumentation and electrical components appeared to be especially prone to human failures. Many human failures were found in safety related systems. Several failures also remained latent from outages to power operation. However, the safety significance of failures was generally small. Modifications were an important source of multiple human failures. Plant maintenance data is a good source of human reliability data and it should be used more in the future. (orig.)

Statistical analysis of human maintenance failures of a nuclear power plant

International Nuclear Information System (INIS)

Pyy, P.

2000-01-01

In this paper, a statistical study of faults caused by maintenance activities is presented. The objective of the study was to draw conclusions on the unplanned effects of maintenance on nuclear power plant safety and system availability. More than 4400 maintenance history reports from the years 1992-1994 of Olkiluoto BWR nuclear power plant (NPP) were analysed together with the maintenance personnel. The human action induced faults were classified, e.g., according to their multiplicity and effects. This paper presents and discusses the results of a statistical analysis of the data. Instrumentation and electrical components are especially prone to human failures. Many human failures were found in safety related systems. Similarly, several failures remained latent from outages to power operation. The safety significance was generally small. Modifications are an important source of multiple human failures. Plant maintenance data is a good source of human reliability data and it should be used more, in future. (orig.)

Development of a daily maintenance work management system for nuclear power plants

International Nuclear Information System (INIS)

Yoshimura, Sadanori; Maita, Keikichi; Ogawa, Koutaro; Tabata, Nobuyuki; Shibuya, Shinya

1999-01-01

Maintenance work plays an important role in keeping the safety and reliability of nuclear power plants. Especially, with the recent trends of reducing the outage length, safe and reliable execution of maintenance work is more earnestly required than ever. Taking this situation into account, a daily maintenance work management system has been developed to support the execution of maintenance work for nuclear power plants. This system supports maintenance personnel in writing and approving the daily work instruction sheet and reduces their workload by providing predetermined lists of items necessary for filling up the sheet and by applying an electronic approval procedure. It also provides information through a computer network to improve the communication among maintenance personnel. For work steps to be treated in the daily work instruction sheet, an analysis was made to identify potential human errors and related counter measures, which were then linked to safety and quality assurance instructions of the sheet. Based on this information, the system automatically presents the safety and quality assurance instructions related to the work content listed in the sheet to improve the appropriateness of the instructions. A prototype of the daily maintenance work management system was developed and a trial use was made for actual periodic maintenance work at a nuclear power plant. This experience shows the usefulness of the system in reducing the workload of maintenance personnel and in providing safer work instructions. (author)

Regulatory instrument review: Management of aging of LWR [light water reactor] major safety-related components

International Nuclear Information System (INIS)

Werry, E.V.

1990-10-01

This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging

Modification and backfitting in safety related systems at Ringhals 2

Energy Technology Data Exchange (ETDEWEB)

Lidh, B. [KSU, Nykoeping (Sweden); Stroemqvist, E. [ES-Konsult AB, Stockholm (Sweden)

1995-08-01

This report is intended for use by the Swedish Nuclear Power Inspectorate. It has been published to enable comparison of modification and backfitting implemented at Ringhals-2, with those implemented at other plants, both domestic and abroad. The report summarizes the more notable modifications and backfitting carried out on any safety-related equipment, or software, at Barsebaeck, and covers the decade 1984 to 1994. Modifications to hardware, and to some extent to software, are catalogued, but not described in any detail. No general procedures (operational or maintenance) are dealt with. 4 refs.

Modification and backfitting in safety related systems at Ringhals 2

International Nuclear Information System (INIS)

Lidh, B.; Stroemqvist, E.

1995-08-01

This report is intended for use by the Swedish Nuclear Power Inspectorate. It has been published to enable comparison of modification and backfitting implemented at Ringhals-2, with those implemented at other plants, both domestic and abroad. The report summarizes the more notable modifications and backfitting carried out on any safety-related equipment, or software, at Barsebaeck, and covers the decade 1984 to 1994. Modifications to hardware, and to some extent to software, are catalogued, but not described in any detail. No general procedures (operational or maintenance) are dealt with. 4 refs

Grounds Maintenance Equipment and Procedures. Building Maintenance. Module VI. Instructor's Guide.

Science.gov (United States)

Crank, Virgil

This curriculum guide, one of six modules keyed to the building maintenance competency profile developed by industry and education professionals, provides materials for two units on grounds maintenance equipment and procedures. The first unit deals with grounds maintenance equipment and includes the following lessons: safety; changing oil/filter…

Regulatory requirements related to risk-based inspection and maintenance

International Nuclear Information System (INIS)

Schroeder, H.C.; Kauer, R.

2003-01-01

By asking the question why new inspection and maintenance strategies have to be developed one can often be made aware that there is always a continue demand for cost reduction and optimisation. In this framework, general trends involving staff reduction, outsourcing, benchmarking etc. can often be observed nearly everywhere. Since inspection and maintenance are amongst the few cost factors, which could be actively influenced in the short term, and in combination with the recent regulatory fundamental changes (e.g. PED) yielding to considerably greater responsibilities for the operator of a plant, also the demand for documentation and comprehensibility of measures will increase. (orig.)

Maintenance strategies and safety on a deregulated market. Mapping of changes in maintenance strategies and their possible consequences; Underhaallsstrategier och saekerhet paa en avreglerad elmarknad. En kartlaeggning av foeraendrade underhaallsstrategier och dess moejliga konsekvenser

Energy Technology Data Exchange (ETDEWEB)

Kecklund, Lena [MTO Psykologi AB, Huddinge (Sweden)

2004-11-01

The overall purpose of the project was to make a survey of the changes in the Swedish nuclear power plants over the last five years. There is a risk that nuclear power companies after a deregulation will focus especially on reducing operation and maintenance costs and that the changes could have a negative effect on the reactor safety. The task has involved summarising the actual changes, describing the present situation, the need for future development and the differences between the plants as well as identifying possible reactor safety related risks. The survey has been carried out in a broad perspective, studying the changes in equipment, maintenance strategies and the work situation of the staff. Three case studies were carried out at the Swedish nuclear power plants. Documentation from the companies has been analysed and a selection of in total 27 'informed' employees in different positions have been interviewed in total. The project also included a fourth case study concerning railway traffic. This branch of business is interesting because of its longer experience on a deregulated and competitive market. Conclusions concerning the companies individually as well as similarities and differences between them are presented in this report. Results: There have been more changes both in strategy and organisation in the last five years than during the preceding 5-10-year-period and the pace has been relatively rapid. The deregulation of the electricity market was implemented January 1997 and became the main motive force for the changes. The staffing has been reduced or unchanged and the work demands have increased. The maintenance skills have been redistributed within the organisation. New methods and equipment, i.e. RCM, and programmable systems make increased demands for analytical and theoretical competence. In the short term, job satisfaction and motivation have in some cases been negatively influenced by the new organisation forms, according to several

Regulatory oversight of maintenance activities at nuclear power plants in France

International Nuclear Information System (INIS)

Bouton, J.P.; Lallement, J.

1997-01-01

In France the nuclear safety authority sets out the main safety objectives but the operator remains the first responsible for the NPP safety. During the operation, operators have to demonstrate that the safety level remains the same as defined in the design studies. Maintenance contributes to meet this objective. The French regulation insists on the quality of the safety related components maintenance, especially in the 1984 order. All gap between results and requirements have to be analyzed by operator who provide feedback measures to avoid similar failure to occur. This gap have to be mentioned to regulators. The use of probabilistic safety analysis (PSA) and reliability centered maintenance (RCM) methods is not well developed in France to optimize maintenance. For the French regulatory, the major difficulties in the use of PSA are: The impossibility to detect unanticipated failure mode; the validity of the input data; the validity of model use, based on ''engineering judgement''. For the specific case of passive components inspection, such as the vessel of the primary circuit, the French regulator has already indicated to the operator that the optimization of maintenance by use of PSA cannot be used, for the following reasons: The safety analysis does not take into account the failure of the vessel; unanticipated failure modes have already damaged part of the primary circuit; the use of defense in depth concept requires a systematic detection of any defect on the vessel. (author)

49 CFR 214.511 - Required audible warning devices for new on-track roadway maintenance machines.

Science.gov (United States)

2010-10-01

... roadway maintenance machines. 214.511 Section 214.511 Transportation Other Regulations Relating to... SAFETY On-Track Roadway Maintenance Machines and Hi-Rail Vehicles § 214.511 Required audible warning devices for new on-track roadway maintenance machines. Each new on-track roadway maintenance machine shall...

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

Kozinsky, E.J.; Gray, L.H.; Beare, A.N.; Barks, D.B.; Gomer, F.E.

1984-03-01

This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria

Experience based reliability centered maintenance

International Nuclear Information System (INIS)

Haenninen, S.; Laakso, K.

1993-03-01

The systematic analysis and documentation of operating experiences should be included in a living NPP life management program. Failure mode and effects and maintenance effects analyses are suitable methods for analysis of the failure and corrective maintenance experiences of equipment. Combined use of the information on occurred functional failures and the decision tree logic of the reliability centered maintenance identifies applicable and effective preventive maintenance tasks of equipment in an old plant. In this study the electrical motor drives of closing and isolation valves (MOV) of TVO and Loviisa nuclear power plants were selected to serve as pilot study objects. The study was limited to valve drives having actuators manufactured by AUMA in Germany. The fault and maintenance history of MOVs from 1981 up to and including October 1991 in different safety and process systems at TVO 1 and 2 nuclear power units was at first analyzed in a systematic way. The scope of the components studied was 81 MOVs in safety-related systems and 127 other MOVs per each TVO unit. In the case of the Loviisa plant, the observation period was limited to three years, i.e. from February 1989 up to February 1992. The scope of the Loviisa 1 and 2 components studied was 44 respectively 95 MOVs. (25 refs., 22 figs., 8 tabs.)

Maintenance of ageing CANDU reactors. A regulatory perspective

International Nuclear Information System (INIS)

Dunstan, T.

1996-01-01

The subject of this paper is, 'requirements for maintenance of ageing reactors from the perspective of a regulator', with a focus on the particular theme of; 'continuing safety assurance'. A major role of maintenance is to ensure the continuing reliability and effectiveness of safety related systems and equipment. Continuing safety assurance is an issue the Atomic Energy Control Board has been wrestling with for some time. From my perspective, much remains to be done before the AECB can be confident that Canadian nuclear plants have the necessary programs in place to achieve continuing safety assurance. To introduce the topic, it would be appropriate to say a few words about the AECB's position with respect to the situation at the Pickering NGS. Why did we blow the whistle last August and, what are we doing about it? (author)

Plant maintenance and aging management: Are they the same?

International Nuclear Information System (INIS)

Lofaro, R.J.

1995-01-01

As part of the NRC's Nuclear Plant Aging Research Program, a number of aging studies were performed on safety-related systems and components which found that, even with current maintenance and monitoring practices in place, a large number of the reported failures are related to aging. This suggests that current practices are not sufficient to completely manage aging degradation, and other factors need to be considered. This paper examines the aging management process and the degree to which maintenance plays a part in it. Component failures and degradation mechanisms identified in aging studies of several different safety systems are summarized and evaluated, then con-elated with the components most frequently failed. This information, along with an analysis of failure causes, is then used to determine the extent to which aging is managed by current maintenance practices. Conclusions and recommendations for proper aging management arc also presented

49 CFR 214.341 - Roadway maintenance machines.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Roadway maintenance machines. 214.341 Section 214... Roadway maintenance machines. (a) Each employer shall include in its on-track safety program specific provisions for the safety of roadway workers who operate or work near roadway maintenance machines. Those...

Use of the Safety probabilistic analysis for the risk monitor before maintenance

International Nuclear Information System (INIS)

Gonzalez C, M.

2004-01-01

In this work the use of the Safety Probabilistic Analysis (APS) of the Laguna Verde Power plant to quantify the risk before maintenance is presented. Beginning to describe the nature of the Rule of Maintenance and their risk evaluations, it is planned about the paper of the APS for that purpose, and a systematic form to establish the reaches for this use open of the model is delineated. The work provides some technique details of the implantation methods of the APS like risk monitor, including the form of introducing the systems, trains and components to the user, as well as the fitness to the models and improvements to the used platform. There are covered some of the measures taken to achieve the objectives of preserving the base model approved, to facilitate the periodic realize, and to achieve acceptable times of execution for their efficient use. (Author)

The Expert System For Safety Assesment Of Kartini Reactor Operation And Maintenance

International Nuclear Information System (INIS)

Syarip

2000-01-01

An expert system for safety assessment of Kartini reactor operation and maintenance based on fuzzy logic method has been made. The expert system is developed from the Fuzzy Expert System Tools (FEST), i.e. by developing the knowledge base and data base files of Kartini research reactor system and operations with an inference engine based on FEST. The knowledge base is represented in the procedural knowledge as heuristic rules or generally known as rule-base in the from of If-then rule. The fuzzy inference process and the conclusion of the rule is done by FEST based on direct chaining method with interactive as well as non-interactive modes. The safety assessment of Kartini reactor based on this method gives more realistic value than the conventional method or binary logic

Inspection of licensee - Maintenance programme and activities

International Nuclear Information System (INIS)

2013-01-01

An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

Enhancing NPP Safety Through an Effective Dependability Management

Energy Technology Data Exchange (ETDEWEB)

Vieru, G., E-mail: g_vieru@yahoo.com [AREN, Bucharest (Romania)

2014-10-15

Taking into account the importance of the continuous improvement of the performance and reliability of a NPP and practical measures to strengthen nuclear safety and security, it is to be noted that a good management for a nuclear power reactor involves a ''good dependability management'' of the activities, such as: Reliability, Availability, Maintainability (RAM) and maintenance support. In order to evaluate certain safety assessment criteria intended to be applied at the level of the nuclear reactor unit management, equipment dependability indicators and their impact over the availability and reactor safety have to be evaluated. Reactor equipment dependability indicators provide a quantitative indication of equipment RAM performances (Reliability, Availability and Maintenance). One of the important benefits of maintenance and failure data gathering is that it can be used as a support of probabilistic safety assessment (PSA). Also, a good dependability management implementation may be used to complement reactor level unit performance indicators in the field of safe operation, maintenance and improving operating parameters, as well as for Strengthening Safety and Improving Reliability of a NPP. This paper underlines the importance of nuclear safety and security as prerequisites for nuclear power. In addition, it demonstrates how different technical aspects, through implementation of a good dependability management, contribute to a strengthened safety and an improvement of availability of the NPP through dependability indicators determination and evaluation. (author)

Good safety culture maintenance at Leningrad nuclear power plant

International Nuclear Information System (INIS)

Ardanov, A.

1996-01-01

The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document

Good safety culture maintenance at Leningrad nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Ardanov, A [Safety Control Dept., Leningrad Nuclear Power Plant, Leningrad (Russian Federation)

1997-12-31

The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document.

Discussion on allowed outage time at online maintenance in Japan

International Nuclear Information System (INIS)

Kobayashi, Masahide

2009-01-01

The purpose of this report is clarification of the handling of online maintenance in important system for nuclear safety of nuclear power plant in Japan, and discusses future tasks of online maintenance in Japan. Now, online maintenance is limited few cases in Japan. But, the needs and importance of online maintenance will be increase near future. It is necessary to evaluate safety at the online maintenance, and if necessary PSA results were used. It will be safety to do online maintenance within AOT, but safety of repetition of online maintenance must be evaluated. And, it is necessary to evaluate the influence to which the man-power during year is leveled by OLM. (author)

A knowledge-based assistant for valve maintenance planning

International Nuclear Information System (INIS)

Winter, M.J.; Danofsky, R.A.; Spinrad, B.I.; Howard, K.

1987-01-01

A knowledge-based program is being developed to assist engineers in maintenance planning for safety related, motor-operated valves at a boiling water reactor. The purpose of this project is to develop the general framework for a prototype system that demonstrates the capabilities for diagnosing valve symptoms and prescribing corrective maintenance, completing a portion of the Corrective Maintenance Action Request (CMAR) form which must be prepared for each job, and managing an interactive valve data base. Minimizing user input and providing output in a form that is familiar to the maintenance planning engineer are important goals for the program. This paper describes the present features of the valve maintenance advisory system which is currently being tested

49 CFR 214.521 - Flagging equipment for on-track roadway maintenance machines and hi-rail vehicles.

Science.gov (United States)

2010-10-01

... maintenance machines and hi-rail vehicles. 214.521 Section 214.521 Transportation Other Regulations Relating... WORKPLACE SAFETY On-Track Roadway Maintenance Machines and Hi-Rail Vehicles § 214.521 Flagging equipment for on-track roadway maintenance machines and hi-rail vehicles. Each on-track roadway maintenance machine...

The Impact Of Occupational Hazards In Workplaces - Maintenance, A Main Target For Ensuring The Safety Of Working Equipment

Science.gov (United States)

Antonov, Anca Elena; Buica, Georgeta; Darabont, Doru Costin; Beiu, Constantin

2015-07-01

For use of work equipment having the economic performance and the highest level of safety, it must be ensured that it complies with the conditions set by the manufacturer in terms of putting into service, use and maintenance operations, ensuring appropriate technical and environmental requirements, including appropriate measures and means of protection. The research aimed to identify and analyze the occupational hazards associated to maintenance operations, in terms of the history of the adjustments, maintenance, cleaning and repair, including the case that occur after the incidents, capital repairs and upgrades. The results of the research consisted in the development of recommendations on the effective management of maintenance activities of work equipment and a software model to enable an efficient management of maintenance, as a tool for occupational hazards in companies - premise for increasing the competitiveness of employers in the market economy.

Guidance for the design and management of a maintenance plan to assure safety and improve the predictability of a DOE nuclear irradiation facility. Final report

International Nuclear Information System (INIS)

Booth, R.S.; Kryter, R.C.; Shepard, R.L.; Smith, O.L.; Upadhyaya, B.R.; Rowan, W.J.

1994-10-01

A program is recommended for planning the maintenance of DOE nuclear facilities that will help safety and enhance availability throughout a facility's life cycle. While investigating the requirements for maintenance activities, a major difference was identified between the strategy suitable for a conventional power reactor and one for a research reactor facility: the latter should provide a high degree of predicted availability (referred to hereafter as ''predictability'') to its users, whereas the former should maximize total energy production. These differing operating goals necessitate different maintenance strategies. A strategy for scheduling research reactor facility operation and shutdown for maintenance must balance safety, reliability,and predicted availability. The approach developed here is based on three major elements: (1) a probabilistic risk analysis of the balance between assured reliability and predictability (presented in Appendix C), (2) an assessment of the safety and operational impact of maintenance activities applied to various components of the facility, and (3) a data base of historical and operational information on the performance and requirements for maintenance of various components. These factors are integrated into a set of guidelines for designing a new highly maintainable facility, for preparing flexible schedules for improved maintenance of existing facilities, and for anticipating the maintenance required to extend the life of an aging facility. Although tailored to research reactor facilities, the methodology has broader applicability and may therefore be used to improved the maintenance of power reactors, particularly in anticipation of peak load demands

Ranking procedure on maintenance tasks for monitoring of embankment dams

International Nuclear Information System (INIS)

Andersen, G.R.; Bouvier, C.; Back, W.E.

1999-01-01

A multistep strategy for the prioritization of maintenance and repair funds for the monitoring of embankment dams is proposed wherein the most important device in the worst condition is preferred. The strategy involves determining the importance of each device (in terms of dam safety) and measuring its condition through field inspections. A condition definition for each device is developed in terms of its ability to function optimally in its diagnostic role. Relative importance of the monitoring devices is defined in terms of diagnostic value and proceeds by considering: (1) the failure modes and their conditional probabilities; (2) adverse conditions and their conditional probabilities; (3) indicators that provide information on these adverse conditions and their relative diagnostic value; and (4) monitoring devices that are used to assess the presence of the indicators and their relative diagnostic value. A panel of dam safety experts is used to answer the questions necessary to implement this methodology through a process of expert elicitation. An interactive DOS-based C++ computer program has been developed to assist in the expert elicitation necessary to implement this methodology

Periodic safety review of the experimental fast reactor JOYO. Review of aging management

International Nuclear Information System (INIS)

Isozaki, Kazunori; Ogawa, To-ru; Nishino, Kazunari

2005-05-01

Periodic safety review (Review of the aging management) which consisted of ''Technical review on aging for the safety related structures, systems and components'' and ''Establishment a long term maintenance program'' was carried out up to April 2005. 1. Technical review on aging for the safety related structures, systems and components. It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them. 2. Establishment of long term maintenance program. The long term maintenance during JFY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection and renewal based on the long term maintenance program, in addition to the spontaneous inspection of the long term voluntary long-term inspection plan, could prevent the loss of function of the safety related structures, systems and components. (author)

Olfactory short-term memory encoding and maintenance - an event-related potential study.

Science.gov (United States)

Lenk, Steffen; Bluschke, Annet; Beste, Christian; Iannilli, Emilia; Rößner, Veit; Hummel, Thomas; Bender, Stephan

2014-09-01

This study examined whether the memory encoding and short term maintenance of olfactory stimuli is associated with neurophysiological activation patterns which parallel those described for sensory modalities such as vision and auditory. We examined olfactory event-related potentials in an olfactory change detection task in twenty-four healthy adults and compared the measured activation to that found during passive olfactory stimulation. During the early olfactory post-processing phase, we found a sustained negativity over bilateral frontotemporal areas in the passive perception condition which was enhanced in the active memory task. There was no significant lateralization in either experimental condition. During the maintenance interval at the end of the delay period, we still found sustained activation over bilateral frontotemporal areas which was more negative in trials with correct - as compared to incorrect - behavioural responses. This was complemented by a general significantly stronger frontocentral activation. Summarizing, we were able to show that olfactory short term memory involves a parallel sequence of activation as found in other sensory modalities. In addition to olfactory-specific frontotemporal activations in the memory encoding phase, we found slow cortical potentials over frontocentral areas during the memory maintenance phase indicating the activation of a supramodal memory maintenance system. These findings could represent the neurophysiological underpinning of the 'olfactory flacon', the olfactory counter-part to the visual sketchpad and phonological loop embedded in Baddeley's working memory model. Copyright © 2014 Elsevier Inc. All rights reserved.

Cernavoda NPP risk - Based test and maintenance planning - Methodology development

International Nuclear Information System (INIS)

Georgescu, G.; Popa, P.; Petrescu, A.; Naum, M.; Gutu, M.

1997-01-01

The Cernavoda Power Plant starts the commercial operation in November 1996. During operation of the nuclear power plant, several mandatory tests and maintenance are performed on stand-by safety system components to ensure their availability in case of accident. The basic purpose of such activities is the early detection of any failure and degradation, and timely correction of deteriorations. Because of the large number of such activities, emphasis on plant safety and allocation of resources becomes difficult. The probabilistic model and methodology can be effectively used to obtain the risk significance of these activities so that the resources are directed to the most important areas. The proposed Research Contract activity is strongly connected with other safety related areas under development. Since, the Cernavoda Probabilistic Safety Evaluation Level 1 PSA Study (CPSE) was performed and now the study is revised taking into account the as-built information, it is recommended to implement into the model the necessary modeling features to support further PSA application, especially related to Test and Maintenance optimization. Methods need to be developed in order to apply the PSA model including risk information together with other needed information for Test and Maintenance optimization. Also, in parallel with the CPSE study updating, the software interface for the PSA model is under development (Risk Monitor Software class), methods and models needing to be developed for the purpose of using it for qualified monitoring of Test and Maintenance Strategy efficiency. Similar, the Data Collection System need to be appropriate for the purpose of an ongoing implementation of a risk - based Test and Maintenance Strategy. (author). 4 refs, 1 fig

Transport company safety climate - the impact on truck driver behaviour and crash involvement

OpenAIRE

Sullman, Mark J. M.; Stephens A. N.; Pajo K.

2017-01-01

Objective: The present study investigated the relationships between safety climate and driving behavior and crash involvement. Methods: A total of 339 company-employed truck drivers completed a questionnaire that measured their perceptions of safety climate, crash record, speed choice, and aberrant driving behaviors (errors, lapses, and violations). Results: Although there was no direct relationship between the drivers' perceptions of safety climate and crash involvement, safety clima...

Report on safety related occurrences and reactor trips July 1, 1976-December 31, 1976

International Nuclear Information System (INIS)

Andermo, L.

1977-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1, 1976 to December 31, 1976 inclusive. The facilities involved are Oskarshamn 1 and 2, Ringhals 1 and 2 and Barsebaeck 1. During this period of the 6 months 37 safety related occurrences and 34 reactor trips have been reported to the Nuclear Power Inspectorate. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The fact that even small deviations from prescribed operation results in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The number of reactor trips are almost as low as during the last period, which is a drastic reduction compared to earlier time periods. The greatest outages are caused by occurrences without safety significance.(author)

Plant design and layout of the different buildings with respect to safety, operational and maintenance requirements

International Nuclear Information System (INIS)

Liebich, H.

1981-01-01

The descriptions and pictures in this lecture show that the arrangement of the buildings and the location of components and systems are based on proven ideas with the aim to fulfil safety, operational and maintenance requirements also from the point of view of plant layout. (orig.)

The application and practice of predictive maintenance at CANDU equipment management

International Nuclear Information System (INIS)

Yu Guangting

2014-01-01

The equipment in Qinshan CANDU unit is characterized by large number and complex structure. Some equipment failure has no relation with the operation time, it is impossible to avoid the failure of these equipment only by periodical maintenance. To improve the equipment reliability, increase the equipment usability and decrease the maintenance cost, for important equipment related to nuclear safety and generating electricity, it is required to perform condition monitoring and the predictive maintenance (PdM). According to different characteristics of equipment, it is required to use suitable equipment condition monitoring method, content and frequency. In this way, some potential equipment failure can be found, preventive maintenance can be arranged in advance, and equipment maintenance management can be optimized. (author)

Radiological safety assessment of a reference INTOR facility

International Nuclear Information System (INIS)

Khan, T.A.; Stasko, R.R.; Watts, R.T.; Shaw, G.; Morrison, C.A.; Russell, S.; Kempe, T.; Zimmerman, R.

1985-03-01

This report consists of a number of separate studies all of which were performed in support of INTOR Critical Issue D: Tritium Containment and Personnel Access vs Remote Maintenance. The common thread running through these studies is the radiological safety element in the design and operation of the INTOR facility. The intent is to help establish a firm basis for comparisons between a reactor cell maintenance option which requires personnel access, and one which involves completely remote maintenance

Optimum Maintenance Strategies for Highway Bridges

DEFF Research Database (Denmark)

Frangopol, Dan M.; Thoft-Christensen, Palle; Das, Parag C.

As bridges become older and maintenance costs become higher, transportation agencies are facing challenges related to implementation of optimal bridge management programs based on life cycle cost considerations. A reliability-based approach is necessary to find optimal solutions based on minimum...... expected life-cycle costs or maximum life-cycle benefits. This is because many maintenance activities can be associated with significant costs, but their effects on bridge safety can be minor. In this paper, the program of an investigation on optimum maintenance strategies for different bridge types...... is described. The end result of this investigation will be a general reliability-based framework to be used by the UK Highways Agency in order to plan optimal strategies for the maintenance of its bridge network so as to optimize whole-life costs....

Suncor maintenance and reliability

Energy Technology Data Exchange (ETDEWEB)

Little, S. [Suncor Energy, Calgary, AB (Canada)

2006-07-01

Fleet maintenance and reliability at Suncor Energy was discussed in this presentation, with reference to Suncor Energy's primary and support equipment fleets. This paper also discussed Suncor Energy's maintenance and reliability standard involving people, processes and technology. An organizational maturity chart that graphed organizational learning against organizational performance was illustrated. The presentation also reviewed the maintenance and reliability framework; maintenance reliability model; the process overview of the maintenance and reliability standard; a process flow chart of maintenance strategies and programs; and an asset reliability improvement process flow chart. An example of an improvement initiative was included, with reference to a shovel reliability review; a dipper trip reliability investigation; bucket related failures by type and frequency; root cause analysis of the reliability process; and additional actions taken. Last, the presentation provided a graph of the results of the improvement initiative and presented the key lessons learned. tabs., figs.

Safety related experience in FFTF startup and operation

International Nuclear Information System (INIS)

Peterson, R.E.; Halverson, T.G.; Daughtry, J.W.

1982-06-01

The Fast Flux Test Facility (FFTF) is a 400 MW(t) sodium cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US LMFBR program. Startup and initial power ascension testing of the facility involved a comprehensive series of readiness reviews and acceptance tests, many of which relate to the inherent safety of the plant. Included are physics measurements, natural circulation, integrated containment leakage, shielding effectiveness, fuel failure detection, and plant protection system tests. Described are the measurements taken to confirm the design safety margins upon which the operating authorization of the plant was based. These measurements demonstrate that large margins of safety are available in the FFTF design

49 CFR 214.519 - Floors, decks, stairs, and ladders of on-track roadway maintenance machines.

Science.gov (United States)

2010-10-01

... roadway maintenance machines. 214.519 Section 214.519 Transportation Other Regulations Relating to... SAFETY On-Track Roadway Maintenance Machines and Hi-Rail Vehicles § 214.519 Floors, decks, stairs, and ladders of on-track roadway maintenance machines. Floors, decks, stairs, and ladders of on-track roadway...

Evaluation of implementation an Integrated Safety and Preventive Maintenance System for Improving of Safety Indexes

Directory of Open Access Journals (Sweden)

I mohammadfam

2014-03-01

Full Text Available Accident analysis shows that one of the main reasons for accidents is non-integration of maintenance units with safety. Merging these two processes through an integrated system can reduce and or eliminate accidents, diseases, and environmental pollution. These issues lead to improvement in organizational performance, as well. The aim of this study is to design and establish an integrated system for obtaining the aforementioned goal. Integration was carried out at Nirou Moharreke Machine Tools Company via Structured System Analysis & Design Method (SSADM. In order to measure the effectiveness of the system, selected indexes were compared using statistical methods prior and after system establishment. Results show that the accident severity index reduced from 135.46 in 2010, to 43.85 in 2012. Moreover, system effectiveness improved equipment reliability and availability (e.g. reliability of the Pfeiffer Milling machine (P (t>50 increased from 0.89 in 2010, to 0.9 in 2012. This system by forecasting various failures, and planning and designing the required operations for preventing occurrence of these failures, plays an important role in improving safety conditions of equipment, and increasing organizational performance, and is capable of presenting an excellent accident prevention program.

Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care.

Science.gov (United States)

Trier, Hans; Valderas, Jose M; Wensing, Michel; Martin, Helle Max; Egebart, Jonas

2015-09-01

Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based recommendations in this area. Scoping review of the literature 2006-2011 about methods and effects of involving patients in patient safety in primary care identified evidence for previous experiences of patient involvement in patient safety. This information was fed back to an expert panel for the development of recommendations for healthcare professionals and policy makers. The scoping review identified only weak evidence in support of the effectiveness of patient involvement. Identified barriers included a number of patient factors but also the healthcare workers' attitudes, abilities and lack of training. The expert panel recommended the integration of patient safety in the educational curricula for healthcare professionals, and expected a commitment from professionals to act as first movers by inviting and encouraging the patients to take an active role. The panel proposed a checklist to be used by primary care clinicians at the point of care for promoting patient involvement. There is only weak evidence on the effectiveness of patient involvement in patient safety. The recommendations of the panel can inform future policy and practice on patient involvement in safety in primary care.

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

Energy Technology Data Exchange (ETDEWEB)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2015-10-15

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant.

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

International Nuclear Information System (INIS)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung

2015-01-01

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant

Tools and Techniques for Evaluating the Effects of Maintenance Resource Management (MRM) in Air Safety

Science.gov (United States)

Taylor, James C.

2002-01-01

This research project was designed as part of a larger effort to help Human Factors (HF) implementers, and others in the aviation maintenance community, understand, evaluate, and validate the impact of Maintenance Resource Management (MRM) training programs, and other MRM interventions; on participant attitudes, opinions, behaviors, and ultimately on enhanced safety performance. It includes research and development of evaluation methodology as well as examination of psychological constructs and correlates of maintainer performance. In particular, during 2001, three issues were addressed. First a prototype process for measuring performance was developed and used. Second an automated calculator was developed to aid the HF implementer user in analyzing and evaluating local survey data. These results include being automatically compared with the experience from all MRM programs studied since 1991. Third the core survey (the Maintenance Resource Management Technical Operations Questionnaire, or 'MRM/TOQ') was further developed and tested to include topics of added relevance to the industry.

Maintenance of safety behaviors via response-produced stimuli.

Science.gov (United States)

Angelakis, Ioannis; Austin, Jennifer L

2015-11-01

Animal studies suggest that safety behaviors may be maintained by internally or externally produced safety signals, which function as positive reinforcers. We designed two experiments to test this phenomenon with humans. Participants played a computerized game in which they could earn or lose treasures by clicking on a map. In baseline, losses could be postponed by pressing a pedal that also produced a blue bar at the bottom of the screen. During test conditions, no losses were programmed, and pedal presses turned the bar from yellow to blue (Test 1) or blue to yellow (Test 2). In Experiment 2, new participants were exposed to the same conditions but were given information about the safety of the test environment. In both experiments, participants engaged in high rates of pedal pressing when presses were followed by blue bars, suggesting the bar functioned as a safety signal. We discuss how these findings may relate to safety behaviors commonly observed in certain mental health disorders. © The Author(s) 2015.

Report on safety related occurrences and reactor trips July 1, 1979 - December 31, 1979

International Nuclear Information System (INIS)

Olsson, S.; Andermo, L.

1980-01-01

This is a report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1979 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 76 safety related occurrences and 27 reactor trips have been reported to the Nuclear Power Inspectorate. It is to the greatest extent conventional components such as valves and pumps which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant system and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips are normal. The average value for these 6 months is 4.5 trips/unit. Approximetely one half of the reactor trips happened at zero or very low power operation. The fact that even small deviations from prescribed operation result in an automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences without safety significance. (author)

Patient Involvement in Patient Safety: A Qualitative Study of Nursing Staff and Patient Perceptions.

Science.gov (United States)

Bishop, Andrea C; Macdonald, Marilyn

2017-06-01

The risk associated with receiving health care has called for an increased focus on the role of patients in helping to improve safety. Recent research has highlighted that patient involvement in patient safety practices may be influenced by patient perceptions of patient safety practices and the perceptions of their health care providers. The objective of this research was to describe patient involvement in patient safety practices by exploring patient and nursing staff perceptions of safety. Qualitative focus groups were conducted with a convenience sample of nursing staff and patients who had previously completed a patient safety survey in 2 tertiary hospital sites in Eastern Canada. Six focus groups (June 2011 to January 2012) were conducted and analyzed using inductive thematic analysis. Four themes were identified: (1) wanting control, (2) feeling connected, (3) encountering roadblocks, and (4) sharing responsibility for safety. Both patient and nursing staff participants highlighted the importance of building a personal connection as a precursor to ensuring that patients are involved in their care and safety. However, perceptions of provider stress and nursing staff workload often reduced the ability of the nursing staff and patient participants to connect with one another and promote involvement. Current strategies aimed at increasing patient awareness of patient safety may not be enough. The findings suggest that providing the context for interaction to occur between nursing staff and patients as well as targeted interventions aimed at increasing patient control may be needed to ensure patient involvement in patient safety.

Recent activities within Nuclear Electric related to the qualification of digital systems and the extension of maintenance intervals

International Nuclear Information System (INIS)

Holt, G.P.

1993-01-01

Nuclear Electric is pursuing a program of modernization and enhancement of existing control and safety (C ampersand I) systems to improve power plant availability and increase power output. This paper describes recent experience in qualifying digital systems for safety applications. Also, described is the work currently in hand to reduce the frequency of maintenance periods for safety C ampersand I equipment. The qualification of digital systems is shown to be a more rigorous and much more extensive (and thus costly) exercise than the qualification of conventional equipment. This is illustrated by brief references to two software-based safety systems, the Single Channel Trip System at the Dungeness open-quotes Bclose quotesAGR and the Primary Protection System for the new PWR at Sizewell open-quotes Bclose quotes. The emphasis of the paper is on the use of Application Specific Integrated Circuits (ASICs) in safety systems, to reduce, or eliminate dependence on software for the fulfillment of requirements which need implementations that are complex or of a high functional density. Recent experience in the development of a prototype safety system based on ASICs, The Gaseous Activity Monitor and Trip Equipment (GAM), is used to illustrate their possible benefits and potential problems. When using complex integrated circuits like microprocessors or ASICs in digital systems a difficulty arises in analyzing the failure modes of the system. Efforts to overcome this difficulty led to the development of a method for performing failure analyses based on functional blocks. The techniques and benefits of such an approach are outlined. Finally, efforts to reduce maintenance costs, yet at the same time enhance safety, are leading towards an extension of maintenance intervals, for some safety equipment, from 3 months to 4 months and also towards lengthening the period between AGR outages from 2 years to 3 years

Equipment reliability process improvement and preventive maintenance optimization

International Nuclear Information System (INIS)

Darragi, M.; Georges, A.; Vaillancourt, R.; Komljenovic, D.; Croteau, M.

2004-01-01

The Gentilly-2 Nuclear Power Plant wants to optimize its preventive maintenance program through an Integrated Equipment Reliability Process. All equipment reliability related activities should be reviewed and optimized in a systematic approach especially for aging plants such as G2. This new approach has to be founded on best practices methods with the purpose of the rationalization of the preventive maintenance program and the performance monitoring of on-site systems, structures and components (SSC). A rational preventive maintenance strategy is based on optimized task scopes and frequencies depending on their applicability, critical effects on system safety and plant availability as well as cost-effectiveness. Preventive maintenance strategy efficiency is systematically monitored through degradation indicators. (author)

Safety aspects on dependability management for a TRIGA research reactor in Romania

International Nuclear Information System (INIS)

Vieru, Gheorghe

2002-01-01

Safety on the management for a nuclear research reactor involves a 'good dependability management' of the activities, such as: reliability, availability, maintainability and maintenance support. In order to evaluate the safety management aspects intended to be applied at a research reactor management, the performance dependability indicators and their impact over the availability and reactor safety have to be established. The document ISO 9000-4/IEC 300-1 'Dependability Management' (1995), describes five internationally agreed indicators of the reactor equipment dependability, each of them can be used for corrective maintenance or for preventive maintenance, such as: I 1 - equipment Maintenance Frequency; I 2 - equipment Maintenance Effort; I-3 - equipment Maintenance Downtime Factor; I 4 - equipment Maintenance Contribution to the System Function Downtime Factor; I 5 - equipment Maintenance Contribution to the reactor Capability Loss Factor. The paper presents an evaluation of those 5 mentioned indicators with referring only at the primary circuit of the INR's TRIGA research reactor and conclusion. The analyzed period was stated between 1994-1999. It is to be noted that this type of analyze is performed for the first time for a research reactor. (author)

Plant design and layout of the different buildings with respect to safety, operational and maintenance requirements

International Nuclear Information System (INIS)

Linder, C.

1981-01-01

Design and layout of the buildings of a nuclear power plant are governed by the safety requirements regarding nearby population as called for by government regulations as well as by operational and maintenance requirements called for by the power utilities in order to assure smooth operation and easy service conditions. The lecture will focus on the different functional circumstances to be considered, their relative importance, criteria to be applied, pertinent regulations etc. and also give examples on the solutions to the above requirements. Main topics to be covered will be those circumstances that impose the highest demands on the civil engineering layout and design: airplane impact, earthquake, loss of coolant accident, pipe whipping, fuel cask transfer, annual overhaul, leak detection etc. (orig./RW)

Aging related degradation in turbine drives and governors for safety related pumps

International Nuclear Information System (INIS)

Cox, D.F.

1991-01-01

This study is being performed to examine the relationship between time dependent degradation, and current industry practices in the areas of maintenance, surveillance, and operation of stem turbine drive for safety related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized water reactor (PWR) plants, and the Reactor Core Isolation Cooking (RCIC) and High Pressure Coolant Injection (HPCI) systems for Boiling Water Reactor (BWR) facilities. This research has been conducted by examining current information in the Nuclear Plant Reliability Data System (NPRDS), reviewing Licensee Event Reports, thoroughly investigating contacts with operating plant personnel, and by personal observation. This information was reviewed to determine the cause of each reported event and the method of discovery. From this data attempts have been made at determining the predictability of events and possible preventive measures that may be implemented

49 CFR 214.525 - Towing with on-track roadway maintenance machines or hi-rail vehicles.

Science.gov (United States)

2010-10-01

... or hi-rail vehicles. 214.525 Section 214.525 Transportation Other Regulations Relating to... SAFETY On-Track Roadway Maintenance Machines and Hi-Rail Vehicles § 214.525 Towing with on-track roadway maintenance machines or hi-rail vehicles. (a) When used to tow pushcars or other maintenance-of-way equipment...

Road safety issues for bus transport management.

Science.gov (United States)

Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

2013-11-01

Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

Education as a Basic Element of Improving Professional Important Qualities of Aviation Technical Maintenance Personnel

Directory of Open Access Journals (Sweden)

Gorbačovs Oļegs

2016-12-01

Full Text Available In this article the importance of professional qualities, competence and their increase, directly dependent on the training of aviation technical maintenance personnel and determination the level of flight safety is covered. This publication analyses necessary training and requirements for aviation technical personnel involved in aircraft maintenance, as well as the requirements for aviation training organizations, defined as per Part-147, for such personnel preparation and training.

EPR design for maintenance

International Nuclear Information System (INIS)

Krugmann, U.

1998-01-01

Preventive maintenance is very important in achieving high plant availability. For the European Pressurized Reactor (EPR) preventive maintenance has been carefully addressed in the design stage. This is particularly necessary because of the traditionally different maintenance strategies employed in France and Germany. This paper emphasizes the following features introduced in the ERP design to minimize the duration of the refueling outage: (1) containment accessibility during power operation; (2) overall plant layout to facilitate inspections and maintenances within the containment; and (3) safety system design for enabling preventive maintenance during power operation. (author)

Environmental qualification - walkdowns: The documentation of configuration information for safety related components, equipment and systems

International Nuclear Information System (INIS)

Melmer, J.; Waters, M.

1995-01-01

Environmental Qualification walkdowns are conducted to collect field data to verify/validate/document configurations of safety related equipment and systems. This paper describes the process for conducting walkdowns and the justification for using an electronic format. The following are described: a) Background; b) Preparing, executing and processing walkdowns; c) Hardware/software; d) Impact of a paperless system on walkdown execution, maintenance and work planning; e) Other applications for the technology

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2017-01-01

This publication establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2017-01-01

This publication establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Addressing imperfect maintenance modelling uncertainty in unavailability and cost based optimization

International Nuclear Information System (INIS)

Sanchez, Ana; Carlos, Sofia; Martorell, Sebastian; Villanueva, Jose F.

2009-01-01

Optimization of testing and maintenance activities performed in the different systems of a complex industrial plant is of great interest as the plant availability and economy strongly depend on the maintenance activities planned. Traditionally, two types of models, i.e. deterministic and probabilistic, have been considered to simulate the impact of testing and maintenance activities on equipment unavailability and the cost involved. Both models present uncertainties that are often categorized as either aleatory or epistemic uncertainties. The second group applies when there is limited knowledge on the proper model to represent a problem, and/or the values associated to the model parameters, so the results of the calculation performed with them incorporate uncertainty. This paper addresses the problem of testing and maintenance optimization based on unavailability and cost criteria and considering epistemic uncertainty in the imperfect maintenance modelling. It is framed as a multiple criteria decision making problem where unavailability and cost act as uncertain and conflicting decision criteria. A tolerance interval based approach is used to address uncertainty with regard to effectiveness parameter and imperfect maintenance model embedded within a multiple-objective genetic algorithm. A case of application for a stand-by safety related system of a nuclear power plant is presented. The results obtained in this application show the importance of considering uncertainties in the modelling of imperfect maintenance, as the optimal solutions found are associated with a large uncertainty that influences the final decision making depending on, for example, if the decision maker is risk averse or risk neutral

Addressing imperfect maintenance modelling uncertainty in unavailability and cost based optimization

Energy Technology Data Exchange (ETDEWEB)

Sanchez, Ana [Department of Statistics and Operational Research, Polytechnic University of Valencia, Camino de Vera, s/n, 46071 Valencia (Spain); Carlos, Sofia [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera, s/n, 46071 Valencia (Spain); Martorell, Sebastian [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera, s/n, 46071 Valencia (Spain)], E-mail: smartore@iqn.upv.es; Villanueva, Jose F. [Department of Chemical and Nuclear Engineering, Polytechnic University of Valencia, Camino de Vera, s/n, 46071 Valencia (Spain)

2009-01-15

Optimization of testing and maintenance activities performed in the different systems of a complex industrial plant is of great interest as the plant availability and economy strongly depend on the maintenance activities planned. Traditionally, two types of models, i.e. deterministic and probabilistic, have been considered to simulate the impact of testing and maintenance activities on equipment unavailability and the cost involved. Both models present uncertainties that are often categorized as either aleatory or epistemic uncertainties. The second group applies when there is limited knowledge on the proper model to represent a problem, and/or the values associated to the model parameters, so the results of the calculation performed with them incorporate uncertainty. This paper addresses the problem of testing and maintenance optimization based on unavailability and cost criteria and considering epistemic uncertainty in the imperfect maintenance modelling. It is framed as a multiple criteria decision making problem where unavailability and cost act as uncertain and conflicting decision criteria. A tolerance interval based approach is used to address uncertainty with regard to effectiveness parameter and imperfect maintenance model embedded within a multiple-objective genetic algorithm. A case of application for a stand-by safety related system of a nuclear power plant is presented. The results obtained in this application show the importance of considering uncertainties in the modelling of imperfect maintenance, as the optimal solutions found are associated with a large uncertainty that influences the final decision making depending on, for example, if the decision maker is risk averse or risk neutral.

Yeast hnRNP-related proteins contribute to the maintenance of telomeres

Energy Technology Data Exchange (ETDEWEB)

Lee-Soety, Julia Y., E-mail: jlee04@sju.edu [Department of Biology, Saint Joseph' s University, PA 19131 (United States); Jones, Jennifer; MacGibeny, Margaret A.; Remaly, Erin C.; Daniels, Lynsey; Ito, Andrea; Jean, Jessica; Radecki, Hannah; Spencer, Shannon [Department of Biology, Saint Joseph' s University, PA 19131 (United States)

2012-09-14

Highlights: Black-Right-Pointing-Pointer Yeast hnRNP-related proteins are able to prevent faster senescence in telomerase-null cells. Black-Right-Pointing-Pointer The conserved RRMs in Npl3 are important for telomere maintenance. Black-Right-Pointing-Pointer Human hnRNP A1 is unable to complement the lack of NPL3 in yeast. Black-Right-Pointing-Pointer Npl3 and Cbc2 may work as telomere capping proteins. -- Abstract: Telomeres protect the ends of linear chromosomes, which if eroded to a critical length can become uncapped and lead to replicative senescence. Telomerase maintains telomere length in some cells, but inappropriate expression facilitates the immortality of cancer cells. Recently, proteins involved in RNA processing and ribosome assembly, such as hnRNP (heterogeneous nuclear ribonucleoprotein) A1, have been found to participate in telomere maintenance in mammals. The Saccharomyces cerevisiae protein Npl3 shares significant amino acid sequence similarities with hnRNP A1. We found that deleting NPL3 accelerated the senescence of telomerase null cells. The highly conserved RNA recognition motifs (RRM) in Npl3 appear to be important for preventing faster senescence. Npl3 preferentially binds telomere sequences in vitro, suggesting that Npl3 may affect telomeres directly. Despite similarities between the two proteins, human hnRNP A1 is unable to complement the lack of Npl3 to rescue accelerated senescence in tlc1 npl3 cells. Deletion of CBC2, which encodes another hnRNP-related protein that associates with Npl3, also accelerates senescence. Potential mechanisms by which hnRNP-related proteins maintain telomeres are discussed.

Probabilistic methods for maintenance program optimization

International Nuclear Information System (INIS)

Liming, J.K.; Smith, M.J.; Gekler, W.C.

1989-01-01

In today's regulatory and economic environments, it is more important than ever that managers, engineers, and plant staff join together in developing and implementing effective management plans for safety and economic risk. This need applied to both power generating stations and other process facilities. One of the most critical parts of these management plans is the development and continuous enhancement of a maintenance program that optimizes plant or facility safety and profitability. The ultimate objective is to maximize the potential for station or facility success, usually measured in terms of projected financial profitability, while meeting or exceeding meaningful and reasonable safety goals, usually measured in terms of projected damage or consequence frequencies. This paper describes the use of the latest concepts in developing and evaluating maintenance programs to achieve maintenance program optimization (MPO). These concepts are based on significant field experience gained through the integration and application of fundamentals developed for industry and Electric Power Research Institute (EPRI)-sponsored projects on preventive maintenance (PM) program development and reliability-centered maintenance (RCM)

An Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process

Directory of Open Access Journals (Sweden)

Ruifeng Yang

2015-01-01

Full Text Available Nuclear power plants are highly complex systems and the issues related to their safety are of primary importance. Probabilistic safety assessment is regarded as the most widespread methodology for studying the safety of nuclear power plants. As maintenance is one of the most important factors for affecting the reliability and safety, an enhanced preventive maintenance optimization model based on a three-stage failure process is proposed. Preventive maintenance is still a dominant maintenance policy due to its easy implementation. In order to correspond to the three-color scheme commonly used in practice, the lifetime of system before failure is divided into three stages, namely, normal, minor defective, and severe defective stages. When the minor defective stage is identified, two measures are considered for comparison: one is that halving the inspection interval only when the minor defective stage is identified at the first time; the other one is that if only identifying the minor defective stage, the subsequent inspection interval is halved. Maintenance is implemented immediately once the severe defective stage is identified. Minimizing the expected cost per unit time is our objective function to optimize the inspection interval. Finally, a numerical example is presented to illustrate the effectiveness of the proposed models.

Maintenance simulation: Software issues

Energy Technology Data Exchange (ETDEWEB)

Luk, C.H.; Jette, M.A.

1995-07-01

The maintenance of a distributed software system in a production environment involves: (1) maintaining software integrity, (2) maintaining and database integrity, (3) adding new features, and (4) adding new systems. These issues will be discussed in general: what they are and how they are handled. This paper will present our experience with a distributed resource management system that accounts for resources consumed, in real-time, on a network of heterogenous computers. The simulated environments to maintain this system will be presented relate to the four maintenance areas.

The Affordances of Social Networking Sites for Relational Maintenance in a Distrustful Society: The Case of Azerbaijan

Directory of Open Access Journals (Sweden)

Katy E. Pearce

2015-11-01

Full Text Available The Internet and social media afford opportunities for relational maintenance, but most scholarship has focused on relational maintenance in high-trust environments. This study explores relational maintenance online and offline in a distrustful society. In distrustful societies, trust is situated within one’s particularized kin network, and friendships have strategic significance and are characterized by norms of reciprocity. In distrustful societies, relational maintenance behaviors are different from trustful societies and take on greater significance. This preliminary study, based on informant interviews in Azerbaijan, examines both offline relational maintenance and the affordances of social networking sites (SNSs for relational maintenance in such an environment. SNSs do provide for some relational maintenance behaviors through supplementing offline behaviors at a low cost and give some additional benefits like status display, yet SNSs do not replace traditional relational maintenance behaviors in Azerbaijan.

25 CFR 170.804 - How is BIA's Road Maintenance Program related to the IRR Program?

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false How is BIA's Road Maintenance Program related to the IRR... WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.804 How is BIA's Road Maintenance Program related to the IRR Program? The following chart illustrates how BIA's Road Maintenance Program is...

Can we use IEC 61850 for safety related functions?

Directory of Open Access Journals (Sweden)

Luca Rocca

2016-08-01

Full Text Available Safety is an essential issue for processes that present high risk for human beings and environment. An acceptable level of risk is obtained both with actions on the process itself (risk reduction and with the use of special safety systems that switch the process into safe mode when a fault or an abnormal operation mode happens. These safety systems are today based on digital devices that communicate through digital networks. The IEC 61508 series specifies the safety requirements of all the devices that are involved in a safety function, including the communication network. Also electrical generation and distribution systems are processes that may have a significant level of risk, so the criteria stated by the IEC 61508 applies. Starting from this consideration, the paper analyzes the safety requirement for the communication network and compare them with the services of the communication protocol IEC 61850 that represents the most used protocol for automation of electrical plants. The goal of this job is to demonstrate that, from the technical point of view, IEC 61850 can be used for implementing safety-related functions, even if a formal safety certification is still missing.

EURISOL-DS Multi‐MW Target: Radiological Protection, Radiation Safety and Shielding Aspects

CERN Document Server

Y. Romanets and R. Luís (ITN)

The objective of this work was to carry out a detailed study and analysis of all aspects related toradioprotection and radiation safety of the spallation target area and the whole spaces reservedfor the fission targets and spallation target maintenance. Operational and no‐operationalconditions were considered for an evaluation of the radiation safety conditions.An analysis of the proposed shielding dimensions and configuration was performed for thesystem during operation time. Parameters as activation, dose rate, energy deposition, etc. aremore important for the no‐operation period, in order to evaluate the hazard level anddetermine the staff access type to the maintenance areas (direct or remote control).Such elements as the fission targets and the whole structure involved on it were studied in moredetail because of the disposal issues, after operation. Activation, dose rate and residual nuclideswere studied for each element of the assembly. All parameters were analyzed according to their...

Maintenance Issues in Long Term Operation of Nuclear Power Plant

International Nuclear Information System (INIS)

Contri, P.; Bieth, M.; Rieg, C.

2006-01-01

Due to current social and economical framework, in last years many nuclear power plant owners started a program for the Long Term Operation (LTO)/PLEX (Plant Life Extension) of their older nuclear facilities. This process has many nuclear safety implications, other than strategic and political ones. The need for tailoring the available safety assessment tools to such applications has become urgent in recent years and triggered many research actions. The review of regular maintenance and ageing management programs are tools widely used in LTO/PLEX context in many Countries. However, most of these tools are rather general and in many cases they need reshaping in an LTO/PLEX framework before application, with focus to the safety implications of the LTO/PLEX. Many Countries and plants radically modified their maintenance rules towards a condition based approach as a precondition for the implementation of LTO/PLEX programs. In 2004 a network of European Organisations operating Nuclear Power Plants, SENUF, under the coordination of the JRC-IE, carried out an extensive questionnaire on maintenance practice in their facilities aiming at capturing the aspects of the maintenance programs where research is mostly needed. This paper uses some results of the questionnaire, which was not oriented to LTO/PLEX, to draw some conclusions on how the current maintenance programs could support a potential LTO/PLEX, among the other programs running at NPPs. In this sense, it is spin-off of the SENUF WG on maintenance. The paper aims at identifying the technical attributes of the maintenance programs more directly affecting the decision for a long-term safe operation of a nuclear facility, the issues related to their implementation and safety review. The paper includes an analysis of the questionnaire circulated among the SENUF participants and a discussion on the implications of optimised maintenance programs in existing plants. Some examples at WWER plants taken by sources other than

Aging of turbine drives for safety-related pumps in nuclear power plants

International Nuclear Information System (INIS)

Cox, D.F.

1995-06-01

This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented

Budaya Keselamatan di Bengkel Perawatan Pesawat Udara pada Garuda Maintenance Facility (GMF AEROASIA)

OpenAIRE

Minda Mora

2011-01-01

Safety is the most important thing in aviation. Safety level has to improved in highest performance. One way to improve safety is to implement safety culture in organization. In case of aviation safety, safety is affected by many factors. Aircraft maintenance is of the factor. The goal of his research is to asess the aviation safety culture in maintenance facilities, case study: Garuda Maintenance Facilities (GMF) using Safety Culture Indicator Scale Measurement System (SCISMS). The Safety Cu...

Analysis of maintenance strategies

International Nuclear Information System (INIS)

Laakso, K.; Simola, K.

1998-01-01

The main topics of the presentation include: (1) an analysis model and methods to evaluate maintenance action programs and the support decision to make changes in them and (2) to understand the maintenance strategies in a systems perspective as a basis for future developments. The subproject showed how systematic models for maintenance analysis and decision support, utilising computerised and statistical tool packages, can be taken into use for evaluation and optimisation of maintenance of active systems from the safety and economic point of view

Elimination of maintenance outage and cost reduction by development of outage-free maintenance techniques

International Nuclear Information System (INIS)

Jakabe, Hideo; Maruyama, Yoshinaga

1996-01-01

The development program of KEPCO on outage-free maintenance techniques for distribution line work since 1984 is overviewed. It has succeeded in eliminating maintenance outages since 1989. The original aim was to improve customer satisfaction. However, in all, four benefits were realised through the development. These are cost reduction, securing of worker safety, improvement of customer service, and advancement of distribution techniques and morale in KEPCO. The introduction of robotic techniques for maintenance work and manipulator techniques for repair work is planned for further modernization. These new techniques are helping in both work safety and work efficiency improvement. Cost reduction and advancement of distribution line work techniques is also considered. (R.P.)

Safety-related decision making at a nuclear power plant

International Nuclear Information System (INIS)

Vaurio, J.K.

1998-01-01

The decision making environment of an operating nuclear power plant is presented. The organizations involved, their roles and interactions as well as the main influencing factors and decision criteria are described. The focus is on safety-related decisions, and the framework is based on the situation at Loviisa power station. The role of probabilistic safety assessment (PSA) is illustrated with decisions concerning plant modifications, optimization, acceptance of temporary configurations and extended repair times. Suggestions are made for rational and flexible risk-based control of allowed times to operate the plant with some components out of service. (orig.)

Contribution to a quantitative assessment model for reliability-based metrics of electronic and programmable safety-related functions

International Nuclear Information System (INIS)

Hamidi, K.

2005-10-01

The use of fault-tolerant EP architectures has induced growing constraints, whose influence on reliability-based performance metrics is no more negligible. To face up the growing influence of simultaneous failure, this thesis proposes, for safety-related functions, a new-trend assessment method of reliability, based on a better taking into account of time-aspect. This report introduces the concept of information and uses it to interpret the failure modes of safety-related function as the direct result of the initiation and propagation of erroneous information until the actuator-level. The main idea is to distinguish the apparition and disappearance of erroneous states, which could be defined as intrinsically dependent of HW-characteristic and maintenance policies, and their possible activation, constrained through architectural choices, leading to the failure of safety-related function. This approach is based on a low level on deterministic SED models of the architecture and use non homogeneous Markov chains to depict the time-evolution of probabilities of errors. (author)

Advances in operational safety and severe accident research

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [VTT Automation (Finland)

2002-02-01

A project on reactor safety was carried out as a part of the NKS programme during 1999-2001. The objective of the project was to obtain a shared Nordic view of certain key safety issues related to the operating nuclear power plants in Finland and Sweden. The focus of the project was on selected central aspects of nuclear reactor safety that are of common interest for the Nordic nuclear authorities, utilities and research bodies. The project consisted of three sub-projects. One of them concentrated on the problems related to risk-informed deci- sion making, especially on the uncertainties and incompleteness of probabilistic safety assessments and their impact on the possibilities to use the PSA results in decision making. Another sub-project dealt with questions related to maintenance, such as human and organisational factors in maintenance and maintenance management. The focus of the third sub-project was on severe accidents. This sub-project concentrated on phenomenological studies of hydrogen combustion, formation of organic iodine, and core re-criticality due to molten core coolant interaction in the lower head of reactor vessel. Moreover, the current status of severe accident research and management was reviewed. (au)

The maintenance management framework models and methods for complex systems maintenance

CERN Document Server

Crespo Márquez, Adolfo

2010-01-01

“The Maintenance Management Framework” describes and reviews the concept, process and framework of modern maintenance management of complex systems; concentrating specifically on modern modelling tools (deterministic and empirical) for maintenance planning and scheduling. It will be bought by engineers and professionals involved in maintenance management, maintenance engineering, operations management, quality, etc. as well as graduate students and researchers in this field.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition); Bezopasnost' atomnykh ehlektrostantsij: proektirovanie. Konkretnye trebovaniya bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Use of risk importance measures in maintenance prioritization

International Nuclear Information System (INIS)

Dubreil Chambardel, A.; Ardorino, F.; Mauger, P.

1997-01-01

A RCM method has been developed at EDF since 1990 to optimize maintenance through a prioritization of resources for equipment that are important in terms of safety, availability and maintenance costs. In 1994, the Nuclear Power Plant Operations Division decided to apply this method to the most important systems of the French PWRs. About 50 systems are in the scope of the RCM. Those that have a role in safety were ranked depending on their contribution to the risk of core melt provided by PSAs. The RCM studies on the 20 most important to safety systems are performed by the Nuclear Power Plant Operations division, the other 30 systems are studied on sites. The RCM study consists first in the research of equipment and failures modes significant to safety, availability or maintenance costs and the evaluation of the performance of those equipment. Those studies lead to the distinction of equipment and failure modes that are critical or non critical to safety, availability and costs. The last part of the study consists in optimizing maintenance on those equipment. In this process, risk measures are used to help defining equipment and failure modes critical to safety. This is done by calculation of risk importance measures provided by PSAs. We explain in this paper which measures of risk have been defined, how PSAs allow calculation of those measures, and how we used those results in the RCM studies we processed. We give also extensions of the use of those measures in the process of defining optimized maintenance tasks. After having defined a RCM method for the French PWRs, the Nuclear Power plant Operations Division decided to start a generalized program of maintenance optimization for the most important systems. The three criteria on which the method relies are: safety, unit availability and maintenance costs. We present here the safety aspect of the method and more precisely these of risk importance measures in the RCM process. (author)

Reliability centred maintenance of nuclear power plant facilities

International Nuclear Information System (INIS)

Kovacs, Zoltan; Novakova, Helena; Hlavac, Pavol; Janicek, Frantisek

2011-01-01

A method for the optimization of preventive maintenance nuclear power plant equipment, i.e. reliability centred maintenance, is described. The method enables procedures and procedure schedules to be defined such as allow the maintenance cost to be minimized without compromising operational safety or reliability. Also, combinations of facilities which remain available and ensure reliable operation of the reactor unit during the maintenance of other pieces of equipment are identified. The condition-based maintenance concept is used in this process, thereby preventing unnecessary operator interventions into the equipment, which are often associated with human errors. Where probabilistic safety assessment is available, the most important structures, systems and components with the highest maintenance priority can be identified. (orig.)

Auditable safety analysis for the surveillance and maintenance of the 224-B building

International Nuclear Information System (INIS)

Cuneo, V.J.

1997-02-01

The Plutonium Concentration Facility (224-B Building) is an inactive, surplus facility that operated from 1945 until 1976. This document provides the auditable safety analysis (ASA) for the post-deactivation, long-term surveillance and maintenance phase of the abovegrade structures of the 224-B Building. In this ASA, the ability of the existing facilities to withstand the effects of natural phenomena hazard events is evaluated and the support systems used to maintain ventilation and/or prevent the spread of contamination are described. The purpose of the S ampersand M phase is as follows: Maintain confinement of residual inventories of radioactive materials and other contaminants until the facility is ultimately dispositioned; Prevent deterioration of confinement structures; Respond to potential accident conditions requiring response and mitigation; Provide for the safety of workers involved in the S ampersand M phase; and Provide the basis for evaluation and selection of ultimate disposal alternatives. In this ASA, the ability of the existing facilities to withstand the effects of natural phenomena hazard (NPH) events is evaluated and the support systems used to maintain ventilation and/or prevent the spread of contamination are described. This document also evaluates S ampersand M activities that are routinely required (i.e., the S ampersand M of facility barriers, equipment, structures, and postings [including repair and upgrade]; measures to identify, remove, or repair damaged asbestos; measures to identify, remove, or appropriately manage existing containers of hazardous substances; nondestructive assay, waste characterization and sampling; and the performance of spill response measures as needed). The type and nature of the hazards presented by the 224-B Building and specific controls that are required to maintain these hazards to acceptable levels are also identified

Performance-based inspection and maintenance strategies

International Nuclear Information System (INIS)

Vesely, W.E.

1995-01-01

Performance-based inspection and maintenance strategies utilize measures of equipment performance to help guide inspection and maintenance activities. A relevant measure of performance for safety system components is component unavailability. The component unavailability can also be input into a plant risk model such as a Probabilistic Risk Assessment (PRA) to determine the associated plant risk performance. Based on the present and projected unavailability performance, or the present and projected risk performance, the effectiveness of current maintenance activities can be evaluated and this information can be used to plan future maintenance activities. A significant amount of information other than downtimes or failure times is collected or can be collected when an inspection or maintenance is conducted which can be used to estimate the component unavailability. This information generally involves observations on the condition or state of the component or component piecepart. The information can be detailed such as the amount of corrosion buildup or can be general such as the general state of the component described as ' high degradation', ' moderate degradation', or ' low degradation'. Much of the information collected in maintenance logs is qualitative and fuzzy. As part of an NRC Research program on performance-based engineering modeling, approaches have been developed to apply Fuzzy Set Theory to information collected on the state of the component to determine the implied component or component piecepart unavailability. Demonstrations of the applications of Fuzzy Set Theory are presented utilizing information from plant maintenance logs. The demonstrations show the power of Fuzzy Set Theory in translating engineering information to reliability and risk implications

Application of reliability centered maintenance to Embalse NPP

International Nuclear Information System (INIS)

Torres, Antonio; Perdomo, Manuel; Fornero, Damian; Corchera, Roberto

2010-01-01

One of the most recent applications of Probabilistic Safety Analysis to Embalse NPP is the Safety Oriented Maintenance Program developed through the Reliability Centered Maintenance (RCM) methodology. Such an application was carried out by a cooperated effort between the staff of nuclear safety department of NPP and experts from Instituto Superior de Tecnologias y Ciencias Aplicadas of Cuba. So far 6 technological systems have been analyzed with important results regarding the optimization of preventive and predictive maintenance program of those systems. Any tasks of RCM were automated via MOSEG code. The results of this study were focused on the elaboration and modification of the Preventive Program, prioritization of stocks, reorientation of predictive techniques and modification in the time parameters of maintenance. (author)

Involvement of AVN as TSO in the safety analysis of radioactive waste disposal

International Nuclear Information System (INIS)

Gelder, P. de; Nys, V.; Smidts, O.; Boeck, B. de

2004-01-01

In 1998, ONDRAF/NIRAS, the agency responsible for radioactive waste management in Belgium, was requested by the government to involve the nuclear safety authorities in its activities of safety evaluation of site-specific waste disposal options (deep or surface disposal) for the short-lived low-level waste. A working group was created in which ONDRAF/NIRAS, FANC (the Federal Agency for Nuclear Control) and AVN discuss different aspects of the ONDRAF/NIRAS program concerning the long-term management of short-lived low-level radioactive waste disposal. It includes also the review of technical safety assessments performed by ONDRAF/NIRAS or by contractors for ONDRAF/NIRAS. The involvement of AVN (the Belgian TSO) in the pre-project phase appears to be positive for all partners. Indeed, all felt the need for an independent actor, with a strong technical basis. Through this presentation, the experience and the topics discussed since 1998 will be developed. Mainly, the presentation will focus on the approach followed to develop competency in the radioactive waste field, on the discussions about the development of a regulatory framework adapted to final disposal of low-level radioactive waste, and on the technical regulatory positions developed so far. Also the experience related to the interaction with local stakeholders will be described. (orig.)

Improved Nuclear Power Plant maintenance. Application to Cofrentes NPP

International Nuclear Information System (INIS)

Serradell, V.

2002-01-01

The Industrial Safety and Environment Group (MEDASEGI) of the Valencia Polytechnic University (UPV) develops its activities in the fields of environmental radioactivity metrology and risk analysis and management aimed at improving industrial safety. The different lines of research developed by this group include collaboration with Cofrentes NPP. This collaboration began in 1993 and has primarily focused on issues related to improved maintenance and currently on life management. (Author)

The contributions of human factors on human error in Malaysia aviation maintenance industries

Science.gov (United States)

Padil, H.; Said, M. N.; Azizan, A.

2018-05-01

Aviation maintenance is a multitasking activity in which individuals perform varied tasks under constant pressure to meet deadlines as well as challenging work conditions. These situational characteristics combined with human factors can lead to various types of human related errors. The primary objective of this research is to develop a structural relationship model that incorporates human factors, organizational factors, and their impact on human errors in aviation maintenance. Towards that end, a questionnaire was developed which was administered to Malaysian aviation maintenance professionals. Structural Equation Modelling (SEM) approach was used in this study utilizing AMOS software. Results showed that there were a significant relationship of human factors on human errors and were tested in the model. Human factors had a partial effect on organizational factors while organizational factors had a direct and positive impact on human errors. It was also revealed that organizational factors contributed to human errors when coupled with human factors construct. This study has contributed to the advancement of knowledge on human factors effecting safety and has provided guidelines for improving human factors performance relating to aviation maintenance activities and could be used as a reference for improving safety performance in the Malaysian aviation maintenance companies.

Guidelines for implementation of RCM on safety systems

International Nuclear Information System (INIS)

Kim, Tae Woon; Brijendra Singh.

1996-04-01

Reliability Centered Maintenance (RCM) methodology was originally developed by the commercial airlines industry in the early 1960s for identifying applicable and effective preventive maintenance tasks and as currently used in nuclear power industry. Effective maintenance of the systems at a nuclear power plant (NPP) is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program to assure that plant systems remain within an original design criteria and are not adversely affected during the plant life time. The aim of this report is to provide the guidelines to implement the RCM approach on NPP safety systems. Safety systems are usually standby and therefore, we need to periodically detect and repair failures that may have occurred since the previous activation or inspection the equipment. The RCM guidelines are intended to help identify the failure modes and related root causes and then decide the maintenance policies to achieve the high level of safety and reliability. The RCM is intended to improve or maintain high levels of system reliability and plant availability. Since the reliability of plant systems will be improved, the plant safety correspondingly will be increased. Another goal of RCM is to optimize the maintenance and surveillance tasks such that the overall level of resources required to accomplish essential tasks is kept to minimum. RCM also strives to eliminate unnecessary corrective maintenance and to select yet most cost-effective approach to maintenance, testing and inspection for system components. 9 refs. (Author) .new

Maintenance management of railway infrastructures based on reliability analysis

International Nuclear Information System (INIS)

Macchi, Marco; Garetti, Marco; Centrone, Domenico; Fumagalli, Luca; Piero Pavirani, Gian

2012-01-01

Railway infrastructure maintenance plays a crucial role for rail transport. It aims at guaranteeing safety of operations and availability of railway tracks and related equipment for traffic regulation. Moreover, it is one major cost for rail transport operations. Thus, the increased competition in traffic market is asking for maintenance improvement, aiming at the reduction of maintenance expenditures while keeping the safety of operations. This issue is addressed by the methodology presented in the paper. The first step of the methodology consists of a family-based approach for the equipment reliability analysis; its purpose is the identification of families of railway items which can be given the same reliability targets. The second step builds the reliability model of the railway system for identifying the most critical items, given a required service level for the transportation system. The two methods have been implemented and tested in practical case studies, in the context of Rete Ferroviaria Italiana, the Italian public limited company for railway transportation.

Implementation of digital safety related I and C systems at nuclear power plants. A systematic approach to training

International Nuclear Information System (INIS)

Roedig, Peter; Schoenfelder, Christian

2012-01-01

In the past, refurbishment or modernization projects at nuclear power plants (NPP) dealing with the AREVA product for safety related digital instrumentation and control (I and C) systems, i.e. TELEPERM registered XS (TXS), regularly led to the development and implementation of different project specific training courses. They mostly dealt with a basic introduction to TELEPERM registered XS, as well as project specific engineering of TELEPERM registered XS and maintenance of the TELEPERM registered XS system supplied with the project. However, it gradually emerged that diverse training needs of different personnel involved in refurbishment or modernization projects as well as in new build projects had to be considered in more detail. Additionally, each target group, e.g. project managers, project engineers, technical engineers, commissioning engineers, operating and maintenance personnel, will have to work with TELEPERM registered XS at different phases within a project. Consequently, it became necessary to take into account the diverse training and project needs. According to the Systematic Approach to Training (SAT) process as developed and promoted by the International Atomic Energy Agency (IAEA), a job and task analysis was performed. After identification of related training needs and redesigning as well as modification or development of appropriate training material, a comprehensive, standardized TELEPERM registered XS training offer is now available at the AREVA Reactor Training Center. This training offer can be easily adapted to project or customer specific requirements. (orig.)

Fiscal 2000 pioneering research report on the research on advanced safety helicopter; 2000 nendo advanced safety helicopter no chosa kenkyu hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

A survey was conducted concerning helicopter operating environments and the trends of related technologies in Japan and abroad, and the needs and seeds were grasped. Research was made to study technical problems and measures to solve them for the development of a safe, low-noise, and low-cost next-generation advanced safety helicopter (ASH). A market research was conducted on traffic systems in the future, state of aviation-related infrastructures and their future, current state of people's daily life which centers about locomotion, and the effect that ASH would impose on society. A technical research was carried out relative to flight safety, which involved EVS (enhanced vision system), information display system for helicopters, collision avoidance advisory for pilots, air collision prevention system/surveillance system for helicopters, obstacle detection/warning system for helicopters, blade deicing system for helicopters, and so forth. Detailed investigations were also conducted for technologies for reduction in the manufacturing, maintenance, and development costs, and for reduction in noise. (NEDO)

International Aspects of Nuclear Safety

International Nuclear Information System (INIS)

Lash, T.R.

2000-01-01

Even though not all the world's nations have developed a nuclear power industry, nuclear safety is unquestionably an international issue. Perhaps the most compelling proof is the 1986 accident at Chornobyl nuclear power plant in what is now Ukraine. The U.S. Department of Energy conducts a comprehensive, cooperative effort to reduce risks at Soviet-designed nuclear power plants. In the host countries : Armenia, Ukraine, Russia, Bulgaria, the Czech Republic, Hungary, Lithuania, Slovakia, and Kazakhstan joint projects are correcting major safety deficiencies and establishing nuclear safety infrastructures that will be self-sustaining.The U.S. effort has six primary goals: 1. Operational Safety - Implement the basic elements of operational safety consistent with internationally accepted practices. 2. Training - Improve operator training to internationally accepted standards. 3. Safety Maintenance - Help establish technically effective maintenance programs that can ensure the reliability of safety-related equipment. 4. Safety Systems - Implement safety system improvements consistent with remaining plant lifetimes. 5. Safety Evaluations - Transfer the capability to conduct in-depth plant safety evaluations using internationally accepted methods. 6. Legal and Regulatory Capabilities - Facilitate host-country implementation of necessary laws and regulatory policies consistent with their international treaty obligations governing the safe use of nuclear power

Report on safety related occurrences and reactor trips July 1, 1977 - December 31, 1977

International Nuclear Information System (INIS)

Andermo, L.; Sundman, B.

1974-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1977 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 48 safety related occurrences and 49 reactor trips have been reported to the Nuclear Power Inspectorate. Included is also one incident June 21 in Barsebaeck 2 which was not included in the last compilation of occurrences. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips have increased nearly 30% since the last period. Those occurred during power operation however, were less. More than 50% of the reactor trips happened in the shutdown condition. The fact that even small deviations from prescribed operation result in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences withou02068NRM 0000169 450

Involvement of patients with cancer in patient safety: a qualitative study of current practices, potentials and barriers.

Science.gov (United States)

Martin, Helle Max; Navne, Laura Emdal; Lipczak, Henriette

2013-10-01

Patient involvement in patient safety is widely advocated but knowledge regarding implementation of the concept in clinical practice is sparse. To investigate existing practices for patient involvement in patient safety, and opportunities and barriers for further involvement. A qualitative study of patient safety involvement practices in patient trajectories for prostate, uterine and colorectal cancer in Denmark. Observations from four hospital wards and interviews with 25 patients with cancer, 11 hospital doctors, 10 nurses, four general practitioners and two private practicing gynaecologists were conducted using ethnographic methodology. Patient safety was not a topic of attention for patients or dominant in communication between patients and healthcare professionals. The understanding of patient safety in clinical practice is almost exclusively linked to disease management. Involvement of patients is not systematic, but healthcare professionals and patients express willingness to engage. Invitation and encouragement of patients to become involved could be further systematised and developed. Barriers include limited knowledge of patient safety, of specific patient safety involvement techniques and concern regarding potential negative impact on doctor-patient relationship. Involvement of patients in patient safety must take into account that despite stated openness to the idea of involvement, patients and health professionals may not in practice show immediate concern. Lack of systematic involvement can also be attributed to limited knowledge about how to implement involvement beyond the focus of self-monitoring and compliance and a concern about the consequences of patient involvement for treatment outcomes. To realise the potential of patients' and health professionals' shared openness towards involvement, there is a need for more active facilitation and concrete guidance on how involvement can be practiced by both parties.

Risk-informed optimisation of railway tracks inspection and maintenance procedures

International Nuclear Information System (INIS)

Podofillini, Luca; Zio, Enrico; Vatn, Jorn

2006-01-01

Nowadays, efforts are being made by the railway industry for the application of reliability-based and risk-informed approaches to maintenance optimisation of railway infrastructures, with the aim of reducing the operation and maintenance expenditures while still assuring high safety standards. In particular, in this paper, we address the use of ultrasonic inspection cars and develop a methodology for the determination of an optimal strategy for their use. A model is developed to calculate the risks and costs associated with an inspection strategy, giving credit to the realistic issues of the rail failure process and including the actual inspection and maintenance procedures followed by the railway company. A multi-objective optimisation viewpoint is adopted in an effort to optimise inspection and maintenance procedures with respect to both economical and safety-related aspects. More precisely, the objective functions here considered are such to drive the search towards solutions characterized by low expenditures and low derailment probability. The optimisation is performed by means of a genetic algorithm. The work has been carried out within a study of the Norwegian National Rail Administration (Jernbaneverket)

The Implementation and Maintenance of a Behavioral Safety Process in a Petroleum Refinery

Science.gov (United States)

Myers, Wanda V.; McSween, Terry E.; Medina, Rixio E.; Rost, Kristen; Alvero, Alicia M.

2010-01-01

A values-centered and team-based behavioral safety process was implemented in a petroleum oil refinery. Employee teams defined the refinery's safety values and related practices, which were used to guide the process design and implementation. The process included (a) a safety assessment; (b) the clarification of safety-related values and related…

Experience in the implementation of quality assurance program and safety culture assessment of research reactor operation and maintenance

International Nuclear Information System (INIS)

Syarip; Suryopratomo, K.

2001-01-01

The implementation of quality assurance program and safety culture for research reactor operation are of importance to assure its safety status. It comprises an assessment of the quality of both technical and organizational aspects involved in safety. The method for the assessment is based on judging the quality of fulfillment of a number of essential issues for safety i.e. through audit, interview and/or discussions with personnel and management in plant. However, special consideration should be given to the data processing regarding the fuzzy nature of the data i.e. in answering the questionnaire. To accommodate this situation, the SCAP, a computer program based on fuzzy logic for assessing plant safety status, has been developed. As a case study, the experience in the assessment of Kartini research reactor safety status shows that it is strongly related to the implementation of quality assurance program in reactor operation and awareness of reactor operation staffs to safety culture practice. It is also shown that the application of the fuzzy rule in assessing reactor safety status gives a more realistic result than the traditional approach. (author)

Evaluation of the adequacy of maintenance tasks using the failure consequences of railroad vehicles

International Nuclear Information System (INIS)

Kim, Jaehoon; Jeong, Hyun- Yong

2013-01-01

The purpose of this study is to improve the efficiency, reliability and safety related to railroad maintenance tasks through an evaluation of the consequences of failures. The brake system was selected based on the failure data obtained from railroad vehicles in operation as one of the safety systems in railroad vehicles. The failure causes, failure effects, and the criticality of the failure mode were drawn for 62 failure modes of the braking system through the use of an FMECA for the 30 sub-devices having primary functions. The various maintenance tasks for the braking system were categorized into the 62 failure modes and failure consequences using the FMECA and the logic of maintenance decisions. Braking systems manufactured by the same manufacturer and operated by two different operators were studied in an effort to analyze preventive maintenance and to evaluate the adequacy of preventive maintenance tasks for the 62 failure modes. Based on results of the evaluation of these preventive maintenance tasks, new maintenance tasks were proposed, and concrete cost-cutting effects were determined from the calculation of the maintenance time and expected costs, using a preventive maintenance template developed specifically for railroad vehicles

Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

Science.gov (United States)

Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

2014-01-01

Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

Safety concerns related to modular/prefabricated building construction.

Science.gov (United States)

Fard, Maryam Mirhadi; Terouhid, Seyyed Amin; Kibert, Charles J; Hakim, Hamed

2017-03-01

The US construction industry annually experiences a relatively high rate of fatalities and injuries; therefore, improving safety practices should be considered a top priority for this industry. Modular/prefabricated building construction is a construction strategy that involves manufacturing of the whole building or some of its components off-site. This research focuses on the safety performance of the modular/prefabricated building construction sector during both manufacturing and on-site processes. This safety evaluation can serve as the starting point for improving the safety performance of this sector. Research was conducted based on Occupational Safety and Health Administration investigated accidents. The study found 125 accidents related to modular/prefabricated building construction. The details of each accident were closely examined to identify the types of injury and underlying causes. Out of 125 accidents, there were 48 fatalities (38.4%), 63 hospitalized injuries (50.4%), and 14 non-hospitalized injuries (11.2%). It was found that, the most common type of injury in modular/prefabricated construction was 'fracture', and the most common cause of accidents was 'fall'. The most frequent cause of cause (underlying and root cause) was 'unstable structure'. In this research, the accidents were also examined in terms of corresponding location, occupation, equipment as well as activities during which the accidents occurred. For improving safety records of the modular/prefabricated construction sector, this study recommends that future research be conducted on stabilizing structures during their lifting, storing, and permanent installation, securing fall protection systems during on-site assembly of components while working from heights, and developing training programmes and standards focused on modular/prefabricated construction.

Systematization of Angra-1 operation attendance - Maintenance and periodic testings

International Nuclear Information System (INIS)

Furieri, E.B.; Carvalho Bruno, N. de; Salaverry, N.A.

1988-01-01

A maintenance analysis, their types and their functions for the safety of nuclear power plants is done. Programs and present trends in the reactor maintenance, as well as the maintenance program and periodic tests of Angra I, are analysed. The necessities of safety analysis and a systematization for maintenance attendance are discussed and the periodic testing as well as the attendance of international experience. (M.C.K.) [pt

Interval of Routine Maintenance and Maintenance Performance: A Literature Review

Directory of Open Access Journals (Sweden)

Au-Yong Cheong Peng

2016-01-01

Full Text Available In high-rise residential buildings, the quality of facilities management services is significant to the normal operation of the facilities. Unfortunately, lack of concern towards building maintenance, especially preventive maintenance, happens in domestic housing industry in Malaysia. Majority of the maintenance operations of condominiums suffer from lack of planning, lack of proactive maintenance plan, and lack of proper implementation. Thus, this paper reviews the implementation of preventive maintenance strategy, routine maintenance in specific. An extensive review of literature published in 1987 to 2014 is performed for the purpose of this research. The publications are sourced from journal articles, conference proceedings and books. The literature analysis confirms that the routine maintenance of facilities and building services is vital and it can be influential towards the maintenance performance. Subsequently, a theoretical framework is developed, which shows the relationship between routine maintenance of building facilities & services and maintenance performance. The building facilities & services are divided into two categories. They are essential facilities & services that ensure the safety, health, habitability, and operability of buildings; while value-added facilities & services deal with property value, return on investment, and quality living of buildings. Based on the findings, a future research is proposed, which aims to identify the appropriate routine of maintenance for the facilities and services in high-rise residential buildings to improve the maintenance performance.

Asbestos exposure of building maintenance personnel.

Science.gov (United States)

Mlynarek, S; Corn, M; Blake, C

1996-06-01

The exposures of building maintenance personnel and occupants to airborne asbestos fibers, and the effects of operations and maintenance programs on those exposures, continue to be an important public health issue. The subject of this investigation was a large metropolitan county with numerous public buildings which routinely conducted air sampling for asbestos. A total of 302 personal air samples in nine task categories collected during maintenance worker activities in proximity to asbestos-containing materials were analyzed; 102 environmental air samples in four task categories were also analyzed. The arithmetic means of the 8-hr time weighted average exposures for personal sampling for each task category were all below the Occupational Safety and Health Administration permissible exposure level of 0.1 fibers (f)/cc > 5 microm. The highest mean 8-hr time weighted average exposure was 0.030 f/cc > 5 microm for ceiling tile replacement. The maximum asbestos concentration during sample collection for environmental samples was 0.027 f/cc > 5 microm. All asbestos-related maintenance work was done within the framework of an Operations and Maintenance Program (OMP) which utilized both personal protective equipment and controls against fiber release/dispersion. Results are presented in association with specific OMP procedures or controls. These results support the effectiveness of using Operations and Maintenance Programs to manage asbestos in buildings without incurring unacceptable risk to maintenance workers performing maintenance tasks.

Development of a Reliability Program approach to assuring operational nuclear safety

International Nuclear Information System (INIS)

Mueller, C.J.; Bezella, W.A.

1985-01-01

A Reliability Program (RP) model based on proven reliability techniques used in other high technology industries is being formulated for potential application in the nuclear power industry. Research findings are discussed. The reliability methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed with several reliability concepts (e.g., quantitative reliability goals, reliability centered maintenance) appearing to be directly transferable. Other tasks in the RP development effort involved the benchmarking and evaluation of the existing nuclear regulations and practices relevant to safety/reliability integration. A review of current risk-dominant issues was also conducted using results from existing probabilistic risk assessment studies. The ongoing RP development tasks have concentrated on defining a RP for the operating phase of a nuclear plant's lifecycle. The RP approach incorporates safety systems risk/reliability analysis and performance monitoring activities with dedicated tasks that integrate these activities with operating, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the RP

Accident characteristics at construction and maintenance zones in urban areas.

Science.gov (United States)

1990-01-01

Work zone safety is currently a major concern to transportation and highway engineers because of the relatively higher rates of accidents in these areas. There is a strong indication that during the next decade, emphasis will be placed on maintenance...

Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care

NARCIS (Netherlands)

Trier, H.; Valderas, J.M.; Wensing, M.; Martin, H.M.; Egebart, J.

2015-01-01

BACKGROUND: Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. OBJECTIVE: To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based

Effects of organizational safety practices and perceived safety climate on PPE usage, engineering controls, and adverse events involving liquid antineoplastic drugs among nurses.

Science.gov (United States)

DeJoy, David M; Smith, Todd D; Woldu, Henok; Dyal, Mari-Amanda; Steege, Andrea L; Boiano, James M

2017-07-01

Antineoplastic drugs pose risks to the healthcare workers who handle them. This fact notwithstanding, adherence to safe handling guidelines remains inconsistent and often poor. This study examined the effects of pertinent organizational safety practices and perceived safety climate on the use of personal protective equipment, engineering controls, and adverse events (spill/leak or skin contact) involving liquid antineoplastic drugs. Data for this study came from the 2011 National Institute for Occupational Safety and Health (NIOSH) Health and Safety Practices Survey of Healthcare Workers which included a sample of approximately 1,800 nurses who had administered liquid antineoplastic drugs during the past seven days. Regression modeling was used to examine predictors of personal protective equipment use, engineering controls, and adverse events involving antineoplastic drugs. Approximately 14% of nurses reported experiencing an adverse event while administering antineoplastic drugs during the previous week. Usage of recommended engineering controls and personal protective equipment was quite variable. Usage of both was better in non-profit and government settings, when workers were more familiar with safe handling guidelines, and when perceived management commitment to safety was higher. Usage was poorer in the absence of specific safety handling procedures. The odds of adverse events increased with number of antineoplastic drugs treatments and when antineoplastic drugs were administered more days of the week. The odds of such events were significantly lower when the use of engineering controls and personal protective equipment was greater and when more precautionary measures were in place. Greater levels of management commitment to safety and perceived risk were also related to lower odds of adverse events. These results point to the value of implementing a comprehensive health and safety program that utilizes available hazard controls and effectively communicates

Identifying Human Factors Issues in Aircraft Maintenance Operations

Science.gov (United States)

Veinott, Elizabeth S.; Kanki, Barbara G.; Shafto, Michael G. (Technical Monitor)

1995-01-01

Maintenance operations incidents submitted to the Aviation Safety Reporting System (ASRS) between 1986-1992 were systematically analyzed in order to identify issues relevant to human factors and crew coordination. This exploratory analysis involved 95 ASRS reports which represented a wide range of maintenance incidents. The reports were coded and analyzed according to the type of error (e.g, wrong part, procedural error, non-procedural error), contributing factors (e.g., individual, within-team, cross-team, procedure, tools), result of the error (e.g., aircraft damage or not) as well as the operational impact (e.g., aircraft flown to destination, air return, delay at gate). The main findings indicate that procedural errors were most common (48.4%) and that individual and team actions contributed to the errors in more than 50% of the cases. As for operational results, most errors were either corrected after landing at the destination (51.6%) or required the flight crew to stop enroute (29.5%). Interactions among these variables are also discussed. This analysis is a first step toward developing a taxonomy of crew coordination problems in maintenance. By understanding what variables are important and how they are interrelated, we may develop intervention strategies that are better tailored to the human factor issues involved.

Hardware and software maintenance strategies for upgrading vintage computers

International Nuclear Information System (INIS)

Wang, B.C.; Buijs, W.J.; Banting, R.D.

1992-01-01

The paper focuses on the maintenance of the computer hardware and software for digital control computers (DCC). Specific design and problems related to various maintenance strategies are reviewed. A foundation was required for a reliable computer maintenance and upgrading program to provide operation of the DCC with high availability and reliability for 40 years. This involved a carefully planned and executed maintenance and upgrading program, involving complementary hardware and software strategies. The computer system was designed on a modular basis, with large sections easily replaceable, to facilitate maintenance and improve availability of the system. Advances in computer hardware have made it possible to replace DCC peripheral devices with reliable, inexpensive, and widely available components from PC-based systems (PC = personal computer). By providing a high speed link from the DCC to a PC, it is now possible to use many commercial software packages to process data from the plant. 1 fig

Use of probabilistic risk assessment in maintenance activities at Palo Verde

International Nuclear Information System (INIS)

Lindquist, R.C.; Pobst, D.S.

1993-01-01

Probabilistic risk assessment (PRA) is an important tool in addressing various maintenance activities. At the Palo Verde nuclear generating station (PVNGS), the PRA has been used in a variety of ways to support a wide and diverse selection of maintenance-related activities. For on-line or at-power maintenance, the PRA was used to evaluate combinations of maintenance activities possible with the 12-week or floating maintenance schedule. The maintenance schedule was evaluated to identify any higher risk, undesirable combinations of equipment outages, such as the sole steam-driven auxiliary feedwater pump and the same train emergency diesel generator. Table I is a sampling of the results from the maintenance schedule evaluation in terms of increase in conditional core damage frequency (CDF) above the base- line value due to maintenance on some important key safety systems and combinations thereof. The baseline CDF is 7.4 x 10 -7 per 72 h

Two Different Maintenance Strategies in the Hospital Environment: Preventive Maintenance for Older Technology Devices and Predictive Maintenance for Newer High-Tech Devices.

Science.gov (United States)

Sezdi, Mana

2016-01-01

A maintenance program generated through the consideration of characteristics and failures of medical equipment is an important component of technology management. However, older technology devices and newer high-tech devices cannot be efficiently managed using the same strategies because of their different characteristics. This study aimed to generate a maintenance program comprising two different strategies to increase the efficiency of device management: preventive maintenance for older technology devices and predictive maintenance for newer high-tech devices. For preventive maintenance development, 589 older technology devices were subjected to performance verification and safety testing (PVST). For predictive maintenance development, the manufacturers' recommendations were used for 134 high-tech devices. These strategies were evaluated in terms of device reliability. This study recommends the use of two different maintenance strategies for old and new devices at hospitals in developing countries. Thus, older technology devices that applied only corrective maintenance will be included in maintenance like high-tech devices.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition); Seguridad de las centrales nucleares: Diseno. Requisitos de seguridad especificos

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Regulatory control of maintenance activities in Argentine nuclear power plants

International Nuclear Information System (INIS)

Calvo, J.C.; Caruso, G.

2000-01-01

The main maintenance objective is to assure that the safety features of structures, components and systems of nuclear power plants are kept as designed. Therefore, there is a direct relationship between safety and maintenance. Owing to the above mentioned, maintenance activities are considered a relevant regulatory issue for the Argentine Nuclear Regulatory Authority (ARN). This paper describes the regulatory control to maintenance activities of Argentine nuclear power plants. It also addresses essential elements for maintenance control, routine inspections, special inspections during planned outages, audits and license conditions and requirements. (author)

PSA Model Improvement Using Maintenance Rule Function Mapping

Energy Technology Data Exchange (ETDEWEB)

Seo, Mi Ro [KHNP-CRI, Nuclear Safety Laboratory, Daejeon (Korea, Republic of)

2011-10-15

The Maintenance Rule (MR) program, in nature, is a performance-based program. Therefore, the risk information derived from the Probabilistic Safety Assessment model is introduced into the MR program during the Safety Significance determination and Performance Criteria selection processes. However, this process also facilitates the determination of the vulnerabilities in currently utilized PSA models and offers means of improving them. To find vulnerabilities in an existing PSA model, an initial review determines whether the safety-related MR functions are included in the PSA model. Because safety-related MR functions are related to accident prevention and mitigation, it is generally necessary for them to be included in the PSA model. In the process of determining the safety significance of each functions, quantitative risk importance levels are determined through a process known as PSA model basic event mapping to MR functions. During this process, it is common for some inadequate and overlooked models to be uncovered. In this paper, the PSA model and the MR program of Wolsong Unit 1 were used as references

Long-period maintenance program of JRR-3M

International Nuclear Information System (INIS)

Murayama, Yoji; Onozaki, Michio; Kakefuda, Kazuhiro

1999-01-01

The JRR-3M is a swimming pool type research reactor with maximum thermal output of 20 MW, classed in a large-scale research reactor and composed of numerous facilities. An operation cycle consists of 4 weeks of continuously reactor operation and 1 week of shutdown work such as fuel exchange and irradiation sample handling. The temporary and small-scale maintenance is also carried out during the shutdown period. Systematic maintenance period through a year usually follows 2 stages. The former stage of about 4 weeks is prepared to maintain the general facilities related to the overall reactor system such as computer system. The latter stage of about 9 weeks is prepared to maintain the other individual facilities such as cooling facilities and control facilities that are to be inspected by the regulatory body. Since preventive maintenance is required in order to achieve an improvement of safety, reliability and availability throughout the life cycle of the reactor, a long-period maintenance program should be prepared properly in consideration of an ageing degradation of the facilities. The long-period maintenance program of JRR-3M, which determines not only the replacement frequency but also the maintenance frequency of the facilities, is made on the basis of an ageing degradation of the facilities, irradiation effects of the materials, recommendations from the manufacturer and JRR-3M maintenance records. The replacement frequency recommended by the manufacturer is examined from the viewpoint of the safety significance of the facilities and availability of the components. The program is arranged so that it may not concentrate the replacement of the facilities in the specific fiscal year and smooth the budget and maintenance period throughout the life cycle of the reactor. There have been two unanticipated failures of the facilities, which required rearranging the program. (author)

Maintenance of records for radioactive waste disposal

International Nuclear Information System (INIS)

1999-07-01

The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

49 CFR 214.355 - Training and qualification in on-track safety for operators of roadway maintenance machines.

Science.gov (United States)

2010-10-01

... operators of roadway maintenance machines. 214.355 Section 214.355 Transportation Other Regulations Relating... operators of roadway maintenance machines. (a) The training and qualification of roadway workers who operate roadway maintenance machines shall include, as a minimum: (1) Procedures to prevent a person from being...

Impact of mechanical- and maintenance-induced failures of main reactor coolant pump seals on plant safety

International Nuclear Information System (INIS)

Azarm, M.A.; Boccio, J.L.; Mitra, S.

1985-12-01

This document presents an investigation of the safety impact resulting from mechanical- and maintenance-induced reactor coolant pump (RCP) seal failures in nuclear power plants. A data survey of the pump seal failures for existing nuclear power plants in the US from several available sources was performed. The annual frequency of pump seal failures in a nuclear power plant was estimated based on the concept of hazard rate and dependency evaluation. The conditional probability of various sizes of leak rates given seal failures was then evaluated. The safety impact of RCP seal failures, in terms of contribution to plant core-melt frequency, was also evaluated for three nuclear power plants. For leak rates below the normal makeup capacity and the impact of plant safety were discussed qualitatively, whereas for leak rates beyond the normal make up capacity, formal PRA methodologies were applied. 22 refs., 17 figs., 19 tabs

Using naturalistic driving data to explore the association between traffic safety-related events and crash risk at driver level.

Science.gov (United States)

Wu, Kun-Feng; Aguero-Valverde, Jonathan; Jovanis, Paul P

2014-11-01

There has been considerable research conducted over the last 40 years using traffic safety-related events to support road safety analyses. Dating back to traffic conflict studies from the 1960s these observational studies of driver behavior have been criticized due to: poor quality data; lack of available and useful exposure measures linked to the observations; the incomparability of self-reported safety-related events; and, the difficulty in assessing culpability for safety-related events. This study seeks to explore the relationships between driver characteristics and traffic safety-related events, and between traffic safety-related events and crash involvement while mitigating some of those limitations. The Virginia Tech Transportation Institute 100-Car Naturalistic Driving Study dataset, in which the participants' vehicles were instrumented with various cameras and sensors during the study period, was used for this study. The study data set includes 90 drivers observed for 12-13 months driving. This study focuses on single vehicle run-off-road safety-related events only, including 14 crashes and 182 safety-related events (30 near crashes, and 152 crash-relevant incidents). Among the findings are: (1) drivers under age 25 are significantly more likely to be involved in safety-related events and crashes; and (2) significantly positive correlations exist between crashes, near crashes, and crash-relevant incidents. Although there is still much to learn about the factors affecting the positive correlation between safety-related events and crashes, a Bayesian multivariate Poisson log-normal model is shown to be useful to quantify the associations between safety-related events and crash risk while controlling for driver characteristics. Copyright © 2014 Elsevier Ltd. All rights reserved.

Environmental problems related to winter traffic safety conditions

OpenAIRE

Hääl, Maire-Liis; Sürje, Peep

2006-01-01

The changeable Nordic climate has added problems to road maintenance and the environment to ensure traffic safety under winter conditions. The widespread use of salt (NaCl) for snow and ice removal from roads has resulted in environmental impacts in many areas. Some of the problems associated with the use of NaCl are the corrosion of bridges, road surfaces and vehicles and damage to roadside vegetation and aquatic system that are affected by water from de-iced roads. Accumulation of hard meta...

Quality assurance requirements for the computer software and safety analyses

International Nuclear Information System (INIS)

Husarecek, J.

1992-01-01

The requirements are given as placed on the development, procurement, maintenance, and application of software for the creation or processing of data during the design, construction, operation, repair, maintenance and safety-related upgrading of nuclear power plants. The verification and validation processes are highlighted, and the requirements put on the software documentation are outlined. The general quality assurance principles applied to safety analyses are characterized. (J.B.). 1 ref

An evaluation system of the setting up of predictive maintenance programmes

International Nuclear Information System (INIS)

Carnero, MaCarmen

2006-01-01

Predictive Maintenance can provide an increase in safety, quality and availability in industrial plants. However, the setting up of a Predictive Maintenance Programme is a strategic decision that until now has lacked analysis of questions related to its setting up, management and control. In this paper, an evaluation system is proposed that carries out the decision making in relation to the feasibility of the setting up. The evaluation system uses a combination of tools belonging to operational research such as: Analytic Hierarchy Process, decision rules and Bayesian tools. This system is a help tool available to the managers of Predictive Maintenance Programmes which can both increase the number of Predictive Maintenance Programmes set up and avoid the failure of these programmes. The Evaluation System has been tested in a petrochemical plant and in a food industry

Optimization and maintenance tests considering multiple failure modes, aging and imperfect maintenance

International Nuclear Information System (INIS)

Martorell, S.; Marton, I.; Sanchez, A.; Carlos, S.

2014-01-01

The paper focuses on the optimization of the test and maintenance intervals under the criteria of unavailability or cost including the effect of the aging of the components and models of imperfect maintenance. The results obtained in the case of application, which focuses on a system of safety of a nuclear power station, show differences, mainly in the outage when you consider the aging. (Author)

Maintenance policy of the nuclear park

International Nuclear Information System (INIS)

Teisset, J.M.

1995-01-01

The nuclear installations maintenance policy of Electricite de France (EDF) follows three axes: first, controlling the aging of the production tool to warrant the safety and the functional reliability during the 40 years of installations service life. Second: optimizing the maintenance activities taking into account the safety goals, costs, security, dosimetry, duration of outages, and intervention conditions in the decisions. Third: developing a real partnership with contractors. EDF has decided to decentralize its maintenance operations towards each unit which is in charge of the organization of its own project. A better management of the contractor personnel has allowed to increase the performances of maintenance operations. The development of long-term agreements with contractors has permitted to reinforce the qualification, the responsibility and the efficiency of the personnel and to improve their means and tools. (J.S.). 1 photo

PROCESS OF CHANGES OF MAINTENANCE-FREE ONBOARD SYSTEM OPERATIONAL STATUS BETWEEN SCHEDULED MAINTENANCES

Directory of Open Access Journals (Sweden)

Andrey Mikhaylovich Bronnikov

2017-01-01

Full Text Available In this article the authors consider the problem of simulating the process of a maintenance-free between scheduled maintenance aircraft system operational status changes, which failure during the flight leads to the disaster. On-board equipment with automatic self-repair between routine maintenance in the event the components fail is called maintenance-free. During operation, onboard equipment accumulates failures maintaining its functions with a safety level not lower than the required minimum. Trouble shooting is carried out either at the end of between-maintenance period (as a rule, or after the failure, which led to the functions disorder or to the decrease below the target level of flight safety (as an exception. The system contains both redundant and nonredundant units and elements with the known failure rates. The system can be in one of the three states: operable, extreme, failed. The excessive redundant elements allow the system to accumulate failures which are repaired during the routine maintenance. The process of system operational status changes is described with the discrete-continuous model in the flight time. Basing on the information about the probabilities of the on-board equipment being in an operable, extreme or failed state, it is possible to calculate such complex efficiency indicators as the average loss of sorties, the average operating costs, the expected number of emergency recovery operations and others. Numerical studies have been conducted to validate the proposed model. It is believed that maintenance work completely updates the system. The analysis of these indicators will allow to evaluate the maintenance-free aircraft equipment operation efficiency, as well as to make an effectiveness comparison with other methods of technical operation. The model can be also used to assess the technical operation systems performance. The model can be used to optimize the period between maintenance.

A Study to Estimate the Effectiveness of Visual Testing Training for Aviation Maintenance Management

Science.gov (United States)

Law, Lewis Lyle

2007-01-01

The Air Commerce Act of 1926 set the beginning for standards in aviation maintenance. Even after deregulation in the late l970s, maintenance standards and requirements still have not changed far from their initial criteria. After a potential candidate completes Federal Aviation Administration training prerequisites, they may test for their Airframe and Powerplant (A&P) certificate. Performing maintenance in the aviation industry for a minimum of three years, the technician may then test for their Inspection Authorization (IA). After receiving their Airframe and Powerplant certificate, a technician is said to have a license to perform. At no time within the three years to eligibility for Inspection Authorization are they required to attend higher-level inspection training. What a technician learns in the aviation maintenance industry is handed down from a seasoned technician to the new hire or is developed from lessons learned on the job. Only in Europe has the Joint Aviation Authorities (JAA) required higher-level training for their aviation maintenance technicians in order to control maintenance related accidents (Lu, 2005). Throughout the 1990s both the General Accounting Office (GAO) and the National Transportation Safety Board (NTSB) made public that the FAA is historically understaffed (GAO, 1996). In a safety recommendation the NTSB stated "The Safety Board continues to lack confidence in the FAA's commitment to provide effective quality assurance and safety oversight of the ATC system (NTSB, 1990)." The Federal Aviation Administration (FAA) has been known to be proactive in creating safer skies. With such reports you would suspect the FAA to also be proactive in developing more stringent inspection training for aviation maintenance technicians. The purpose of this study is to estimate the effectiveness of higher-level inspection training, such as Visual Testing (VT) for aviation maintenance technicians, to improve the safety of aircraft and to make

DOE-EM-45 Packaging Operations And Maintenance Course

International Nuclear Information System (INIS)

Watkins, R.; England, J.

2010-01-01

Savannah River National Laboratory - Savannah River Packaging Technology (SRNL-SRPT) delivered the inaugural offering of the Packaging Operations and Maintenance Course for DOE-EM-45's Packaging Certification Program (PCP) at the University of South Carolina Aiken on September 1 and 2, 2009. Twenty-nine students registered, attended, and completed this training. The DOE-EM-45 Packaging Certification Program (PCP) sponsored the presentation of a new training course, Packaging Maintenance and Operations, on September 1-2, 2009 at the University of South Carolina Aiken (USC-Aiken) campus in Aiken, SC. The premier offering of the course was developed and presented by the Savannah River National Laboratory, and attended by twenty-nine students across the DOE, NNSA and private industry. This training informed package users of the requirements associated with handling shipping containers at a facility (user) level and provided a basic overview of the requirements typically outlined in Safety Analysis Report for Packaging (SARP) Chapters 1, 7, and 8. The course taught packaging personnel about the regulatory nature of SARPs to help reduce associated and often costly packaging errors. Some of the topics covered were package contents, loading, unloading, storage, torque requirements, maintaining records, how to handle abnormal conditions, lessons learned, leakage testing (including demonstration), and replacement parts. The target audience for this course was facility operations personnel, facility maintenance personnel, and field quality assurance personnel who are directly involved in the handling of shipping containers. The training also aimed at writers of SARP Chapters 1, 7, and 8, package designers, and anyone else involved in radioactive material packaging and transportation safety. Student feedback and critiques of the training were very positive. SRNL will offer the course again at USC Aiken in September 2010.

Maintenance planning for nuclear power plants

International Nuclear Information System (INIS)

Mattu, R.K.; Cooper, S.E.; Lauderdale, J.R.

2004-01-01

Maintenance planning for nuclear power plants is similar to that in other industrial plants but it is heavily influenced by regulatory rules, with consequent costs of compliance. Steps by the nuclear industry and the Nuclear Regulatory Commission to address that problem include development of guidelines for maintenance of risk-critical equipment, using PRA-based techniques to select a set of equipment that requires maintenance and reliability-centered maintenance (RCM) approaches for determining what maintenance is required. The result of the process is a program designed to ensure effective maintenance of the equipment most critical to plant safety. (author)

Ageing model considering effects of maintenance and working conditions

International Nuclear Information System (INIS)

Martorell, S.; Sanchez, A.; Serradell, V.

1998-01-01

Nowadays, there is some doubt about building new Nuclear Power Plants (NPPs). Instead, there is a growing interest in analyzing the possibility to extend current NPP operation where life management programs play an important role. The evolution of the NPP safety depends on the evolution of the reliability of its safety components as a function of their age along the NPP operational life. In this paper, a new age-dependent reliability model is presented, which includes parameters related to surveillance and maintenance effectiveness and working conditions, both environmental and operational, of the equipment. This model may be used to support NPP life management and life extension programs by improving or optimizing surveillance and maintenance tasks using risk and cost models based on such an age-dependent reliability model. The results of the sensitivity study in the application show that the selection of the most appropriate maintenance strategy would directly depend on the previous parameters and very important differences are expected to appear under certain circumstance. (Author) 7 refs

Nuclear Power Plant Preventive Maintenance Scheduling Problem with Fuzziness

International Nuclear Information System (INIS)

Abass, S.A.; Abdallah, A.S.

2013-01-01

Maintenance activity is regarded as the most important key factor for the safety, reliability and economy of a nuclear power plant. Preventive maintenance refers to set of planned activities which include nondestructive testing and periodic inspection as well as maintenance. In this paper, we address the problem of nuclear power plant preventive maintenance scheduling with uncertainty. The uncertainty will be represented by fuzzy parameters. The problem is how to determine the period for which generating units of an electric system should be taken off line for planned preventive maintenance over specific time horizon. Preventive maintenance activity of a nuclear power plant is an important issue as it designed to extend the plant life . It is more required to review the maintenance not only from the view point of safety and reliability but also economy. Preventive maintenance program exists to ensure that nuclear safety significant equipment will function when it is supposed to. Also this problem is extremely important because a failure in a power plant may cause a general breakdown in an electric network. In this paper a mixed integer programming model is used to express this problem. In proposed model power demand is taken as fuzzy parameters. A case study is provided to demonstrate the efficiency of the proposed model.

Safety reassessment of the old installations involved in fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Guillard, M

2003-01-01

Since the early 1990's, CEA (French atomic energy commission) has been preparing a plan for the renovation of a laboratory situated at Cadarache and dedicated to the study of irradiated materials and fuels. The main aim of this renovation was the improvement of the seismic behaviour of the laboratory since it was not built according to the para-seismic rules now in force. The solution chosen, given the different projects studied, the provisional unavailability of the plant and the related costs, was a partial reinforcement of the building in association with a limited plant life time and the reduction of activities in the oldest part of the installation. Another aim of this renovation was a global upgrading of the safety concerning: -) radioactive material containment (upgrade of the first static barrier by reinforcing cell leak-proofing, installation of a second level of very high efficiency filtration at the cell outputs, and separation of cell and general building ventilation networks; -) fire protection (fire sectoring with the isolation of the premises involving safety-important equipment, replacement of the automatic fire detection system, and definition of a new piloting of ventilation in case of fire); -) power cut risks (installation of permanent sources for the power supply of safety-important equipment); and -) earthquake behaviour (addition of reinforced connections between the 3 parts of the building, strengthening of peripheral walls, widening of joints between cells and building, and reinforcement of the foundation of the concrete cells). (A.C.)

Safety reassessment of the old installations involved in fuel cycle

International Nuclear Information System (INIS)

Guillard, M.

2003-01-01

Since the early 1990's, CEA (French atomic energy commission) has been preparing a plan for the renovation of a laboratory situated at Cadarache and dedicated to the study of irradiated materials and fuels. The main aim of this renovation was the improvement of the seismic behaviour of the laboratory since it was not built according to the para-seismic rules now in force. The solution chosen, given the different projects studied, the provisional unavailability of the plant and the related costs, was a partial reinforcement of the building in association with a limited plant life time and the reduction of activities in the oldest part of the installation. Another aim of this renovation was a global upgrading of the safety concerning: -) radioactive material containment (upgrade of the first static barrier by reinforcing cell leak-proofing, installation of a second level of very high efficiency filtration at the cell outputs, and separation of cell and general building ventilation networks; -) fire protection (fire sectoring with the isolation of the premises involving safety-important equipment, replacement of the automatic fire detection system, and definition of a new piloting of ventilation in case of fire); -) power cut risks (installation of permanent sources for the power supply of safety-important equipment); and -) earthquake behaviour (addition of reinforced connections between the 3 parts of the building, strengthening of peripheral walls, widening of joints between cells and building, and reinforcement of the foundation of the concrete cells). (A.C.)

Postharvest quality and safety maintenance of the physical ...

African Journals Online (AJOL)

Biodegradable edible coatings from Moringa oil(MO) and Neem oil (NO) was applied to carrot fruits in order to provide environmentally friendly, healthy treatments (with which to better preserve fresh fruit quality) and safety during postharvest storage at ambient temperature of 27± 3oC and relative humidity of 50-60% .

Maintenance program guidelines for programmatic equipment

International Nuclear Information System (INIS)

1994-11-01

The Division Directors at Lawrence Berkeley Laboratory are responsible for implementing a maintenance program for research equipment (also referred to as programmatic equipment) assigned to them. The program must allow maintenance to be accomplished in a manner that promotes operational safety, environmental protection and compliance, and cost effectiveness; that preserves the intended functions of the facilities and equipment; and that supports the programmatic mission of the Laboratory. Programmatic equipment -- such as accelerators, lasers, radiation detection equipment, and glove boxes -- is dedicated specifically to research. Installed equipment, by contrast, includes the mechanical and electrical systems installed as part of basic building construction, equipment essential to the normal functioning of the facility and its intended use. Examples of installed equipment are heating, ventilating, and air conditioning systems; elevators; and communications systems. The LBL Operating and Assurance Program Plan (PUB-3111, Revision 4) requires that a maintenance program be prepared for programmatic equipment and defines the basic maintenance program elements. Such a program of regular, documented maintenance is vital to the safety and quality of research activities. As a part of that support, this document offers guidance to Laboratory organizations for developing their maintenance programs. It clarifies the maintenance requirements of the Operating and Assurance Program (OAP) and presents an approach that, while not the only possibility, can be expected to produce an effective maintenance program for research equipment belonging to the Laboratory's organizations

Interactive effects of relay and circuit breaker aging in a safety-related system

International Nuclear Information System (INIS)

Toman, G.J.; Bacanskas, V.P.; Shook, T.A.; Ladlow, C.C.; Gunther, W.

1987-01-01

This paper provides an overview of the results of a program to evaluate the aging of circuit breakers and relays and the effects of that aging on the function of a safety system used in nuclear power plants. The program was performed under the Nuclear Plant Aging Research (NPAR) Program of the US Nuclear Regulatory Commission under subcontract to Brookhaven National Laboratory. There were two primary aspects to the program. In the first, the aging and failure modes of relays and circuit breakers were determined by evaluating the construction, design, and materials and the failure data related to nuclear power plant service. In the second, the interactions between a safety system and its relays and circuit breakers were evaluated to determine the effects of relay and circuit breaker aging on the function of the safety system. The aging of relays and circuit breakers was assessed through evaluation of failure data bases, discussions with utility personnel, and evaluation of equipment operating and maintenance manuals. The interaction study was based on an analysis of the safety injection system of a pressurized water reactor. The effects of stresses from the system were analyzed for the tendency to cause deterioration of the relays and circuit breakers in the system. Then the effect of the deterioration of relays and circuit breakers on the functional capability of the safety system was evaluated

Predictive maintenance primer

International Nuclear Information System (INIS)

Flude, J.W.; Nicholas, J.R.

1991-04-01

This Predictive Maintenance Primer provides utility plant personnel with a single-source reference to predictive maintenance analysis methods and technologies used successfully by utilities and other industries. It is intended to be a ready reference to personnel considering starting, expanding or improving a predictive maintenance program. This Primer includes a discussion of various analysis methods and how they overlap and interrelate. Additionally, eighteen predictive maintenance technologies are discussed in sufficient detail for the user to evaluate the potential of each technology for specific applications. This document is designed to allow inclusion of additional technologies in the future. To gather the information necessary to create this initial Primer the Nuclear Maintenance Applications Center (NMAC) collected experience data from eighteen utilities plus other industry and government sources. NMAC also contacted equipment manufacturers for information pertaining to equipment utilization, maintenance, and technical specifications. The Primer includes a discussion of six methods used by analysts to study predictive maintenance data. These are: trend analysis; pattern recognition; correlation; test against limits or ranges; relative comparison data; and statistical process analysis. Following the analysis methods discussions are detailed descriptions for eighteen technologies analysts have found useful for predictive maintenance programs at power plants and other industrial facilities. Each technology subchapter has a description of the operating principles involved in the technology, a listing of plant equipment where the technology can be applied, and a general description of the monitoring equipment. Additionally, these descriptions include a discussion of results obtained from actual equipment users and preferred analysis techniques to be used on data obtained from the technology. 5 refs., 30 figs

Enhanced human performance of utility maintenance programs

International Nuclear Information System (INIS)

Fresco, A.; Haber, S.; O'Brien, J.

1993-01-01

Assuring the safe operation of a nuclear power plant depends, to a large extent, on how effectively one understands and manages the aging-related degradation that occurs in structures, systems, and components (SSCs). Aging-related degradation is typically managed through a nuclear plant's maintenance program. A review of 44 Maintenance Team Inspection (MTI) Reports indicated that while some plant organizations appeared to assume a proactive mode in preventing aging-related failures of their SSCs important to safety, others seemed to be taking a passive or reactive mode. Across all plants, what is clearly needed, is a strong recognition of the importance of aging-related degradation and the use of existing organizational assets to effectively detect and mitigate those effects. Many of those assets can be enhanced by the consideration of organizational and management factors necessary for the implementation of an effective aging management program. This report provides a discussion of this program

TECHNICAL MAINTENANCE EFFICIENCY OF THE AIRCRAFT MAINTENANCE-FREE ON-BOARD SYSTEM BETWEEN SCHEDULED MAINTENANCES

Directory of Open Access Journals (Sweden)

A. M. Bronnikov

2017-01-01

Full Text Available The avionics concept of the maintenance-free on-board equipment implies the absence of necessity to maintain onboard systems between scheduled maintenance, preserving the required operational and technical characteristics; it should be achieved by automatic diagnosis of the technical condition and the application of active means of ensuring a failsafe design, allowing to change the structure of the system to maintain its functions in case of failure. It is supposed that such equipment will reduce substantially and in the limit eliminate traditional maintenance of aircraft between scheduled maintenance, ensuring maximum readiness for use, along with improving safety. The paper proposes a methodology for evaluating the efficiency of maintenance-free between scheduled maintenance aircraft system with homogeneous redundancy. The excessive redundant elements allow the system to accumulate failures which are repaired during the routine maintenance. If the number of failures of any reserve is approaching a critical value, the recovery of the on-board system (elimination of all failures is carried out between scheduled maintenance by conducting rescue and recovery operations. It is believed that service work leads to the elimination of all failures and completely updates the on-board system. The process of system operational status changes is described with the discrete-continuous model in the flight time. The average losses in the sorties and the average cost of operation are used as integrated efficiency indicators of system operation. For example, the evaluation of the operation efficiency of formalized on-board system with homogeneous redundancy demonstrates the efficiency of the proposed methodology and the possibility of its use while analyzing the efficiency of the maintenance-free operation equipment between scheduled periods. As well as a comparative analysis of maintenance-free operation efficiency of the on-board system with excessive

Modification and backfitting at the Oskarshamn Nuclear Power Plant Unit 2 in safety related systems

International Nuclear Information System (INIS)

Karlsson, Leif; Nilsson, Ove; Lidh, B.

1995-05-01

This report is intended for use by the Swedish Nuclear Power Inspectorate. It has been published to enable comparison of modification and backfitting implemented at Oskarshamn-2, with those implemented at other plants, both domestic and abroad. The report summarizes the more notable modifications and backfitting carried out on any safety-related equipment, or software, at Barsebaeck, and covers the decade 1984 to 1994. Modifications to hardware, and to some extent to software, are catalogued, but not described in any detail. No general procedures (operational or maintenance) are dealt with. 3 refs

Reducing costs with optimized maintenance strategies. Energie AG Oberoesterreich's practical experience with computer-aided maintenance planning and order processing; Kostensenkung durch optimale Instandhaltungsstrategien. Einsatzerfahrungen der Energie AG Oberoesterreich mit EDV-gestuetzter IH-Planung und Auftragsabwicklung

Energy Technology Data Exchange (ETDEWEB)

Lechner, K.D.; Raffelsberger, K.; Steininger, W. [Energie AG Oberoesterreich (Austria); Roeben, U. [Siemens Power Generation AG, Erlangen (Germany)

2004-07-01

With the increasing competition, application of the optimal maintenance strategy is gaining importance. Apart from optimizing direct maintenance costs, the effects on profit (e.g. due to loss of production), follow-up costs in plant operation as well as safety-related aspects and the environmental impact are important factors. Without state-of-the-art plant management and maintenance software, efficiently meeting the resulting requirements is quite impossible. (orig.)

Understanding aging - A key to ensuring safety

International Nuclear Information System (INIS)

Arlotto, G.A.

1985-01-01

The nuclear community has entered a period during which issues related to the advancing age of nuclear power plants will play an ever-increasing role in the decision making process for the continued safe operation of these plants, including extended safe operation beyond the presently authorized forty years. Although progress has been made toward understanding and managing this aging phenomenon, much remains to be done. This paper describes research needs directed toward: (a) systematically identifying those aging effects which could impair safety; (b) assessment of inspection and monitoring methods for detecting aging prior to loss of safety function; and (c) evaluation of effectiveness of maintenance in mitigation aging. To be successful, this research, and its ultimate application, must involve the entire nuclear community - the regulator and the regulated. It must take the advantage of operating experience, include the assessment and tests of aged equipment, and involve coordination of related activities conducted by individual utilities, reactor manufacturers, architect-engineers, equipment suppliers, utility groups that have been (or might be) established, standards-writing bodies, foreign countries, the NRC, other Government agencies, and other knowledgeable organization and persons. The implementation of this research would best be accomplished by obtaining consensus in an open forum of all interested organizations and persons

Roadside infrastructure for safer European roads: D08 European best practice for roadside design: guidelines for maintenance and operations of roadside infrastructure. Project RISER, European Community

NARCIS (Netherlands)

Andersson, J.; Lanner, G.; Wink, W.; Halleman, B.; Naing, C.L.; Thomson, R.; Fagerlind, H.; Dupre, G.; Bisson, O.; Carcia, J.M.; Lopez, F.; Papi, J.; Martinez, A.V.; Amengual, A.; Valtonen, J.; Kelkka, M.; Goose, U.; Klootwijk, C.W.; Hoogvelt, B.; Horst, A.R.A. van der; Ridder, S. de; Hoschopf, H.; Hill, J.

2006-01-01

Maintenance and operations of road safety equipment and infrastructure ensure that all safety related elements of the road system are operating as they were designed, tested, and approved. Maintenance of road equipment should not only be considered as the repair of broken or damaged equipment, but

The impact of masculinity on safety oversights, safety priority and safety violations in two male-dominated occupations

DEFF Research Database (Denmark)

Nielsen, Kent; Hansen, Claus D.; Bloksgaard, Lotte

2015-01-01

Background Although men have a higher risk of occupational injuries than women the role of masculinity for organizational safety outcomes has only rarely been the object of research. Aim The current study investigated the association between masculinity and safety oversights, safety priority......-related context factors (safety leadership, commitment of the safety representative, and safety involvement) and three safety-related outcome factors (safety violations, safety oversights and safety priority) were administered twice 12 months apart to Danish ambulance workers (n = 1157) and slaughterhouse workers...

Probabilistic approach to rationalization of plants maintenance

International Nuclear Information System (INIS)

Kasai, Masao; Notoya, Junichi; Uchimoto, Tetsuya; Miya, Kenzo

2001-01-01

Since there are a lot of equipments in large plants, their safety and reliability cannot be kept as high level as designed without maintenance activities. Then preventive maintenance is intensively executed in some large plants. However, it will be inefficient to perform the preventive maintenance blindly. To make maintenance activities effective, it is essential to identify the critical equipments influencing plant safety and/or reliability and carry out the maintenance by focusing attentions on these equipments. It needs quantitative analyses to identify the critical equipments based on the data of failure rates. However, complete data set of failure rates cannot necessarily be available for some plants such as nuclear power plants. In this study, we carry out the reliability analysis for generic LNG plant and calculate various quantitative risk importance measures for each equipment. We propose rather qualitative representations for some quantitative measures, considering the situation without complete data set and conclude that it is possible to rationalize maintenance procedure by using these rather qualitative measures, though the level of rationalization is of course limited. (author)

The problem of maintenance of strength, lifetime and safety of the structural components operational NPP from items of a system approach

International Nuclear Information System (INIS)

Getman, A.F.

2005-01-01

The strength of the structural components and pipelines NPP determines largely their lifetime, radiation and nuclear safety. As shows world experience of operation NPP, in a series of cases during operation the local damages, breaks and destructions of elements of the equipment and pipelines emerge. These cases force maintaining organizations to execute on NPP large volumes of the control, repair and modernizing of the equipment and pipelines. These activities require large material inputs (net less than 50% of the cost of operation NPP), however not always are effective and in a series of cases do not allow to reach required of level reliability and safety. The reason of such condition of a problem is that the measures executed on NPP, developed on stretch of long time and under influence of the diverse factors. Besides until now there is no unified scientific methodology of a case study of maintenance of strength, lifetime and safety of the operational equipment and pipelines NPP. The application of a system approach to a problem of maintenance of strength, lifetime and safety of the equipment and pipelines operational NPP allows to consider a problem as a whole, from unified items, to define the most fast and effective paths it of the solution and to decide problems in as much as possible short times at minimum material inputs. The experience of practical application of a system approach at the solution of separate problems of operation NPP has allowed to develop a lot of effective new techniques, technologies and means, which application allows essentially to increase reliability and gamma percentage lifetime of elements NPP, to which they were applied. As an example in the report the outcomes of application of a system approach for maintenance of SG tubes integrity of reactors of a type WWER are adduced. The application of a system approach for all elements of the equipment and pipelines NPP will allow to increase it reliability and safety not less, than on 10

Maintenance program decision-making utilizing crash data.

Science.gov (United States)

2013-07-01

This document describes methods that may be used by UDOT Maintenance personnel to improve highway safety. Four programs have been recommended using crash data to make more informed decisions concerning maintenance programs as follows: : Snow & Ic...

Safety design guide for safety related systems for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new

Safety design guide for safety related systems for CANDU 9

Energy Technology Data Exchange (ETDEWEB)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A.C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new.

Conceptualization of an intellectual maintenance management system

International Nuclear Information System (INIS)

Suda, Kazunori; Yonekawa, Tsuyoshi; Yoshikawa, Shinji; Ozawa, Kenji

1997-04-01

It is studied in many research institute to enhance availability and safety of nuclear power plants operation and maintenance. On this account, development of autonomous plants has been carried out to replace the role of operators with artificial intelligence and autonomous robots. We have been developing an intellectual maintenance management system since 1994. As the first step, concept of an intellectual maintenance management system was constructed. The intellectual maintenance managerial system is in charge of maintenance function of an autonomous plant. The intellectual maintenance managerial system has three functions which is monitoring state and judging abnormal machine and deciding maintenance plan by autonomy. This system has an important role of indication and communication of the result to an autonomous operation system and autonomous robot. In this examination, we adopted the distributed and cooperative system technique by multi-agent of AI technology and examined a method to enforce problem solving by cooperation of sensor and actuator. In this report, we examined trouble detection and troubleshooting evaluation and maintenance plan decision function by the distributed and cooperative system technology, the distributed and cooperative system communication-function that these information releases functions was taken on. In conceptualization of the intellectual maintenance managerial system, we clarified of major functions to constitute this system and relation between autonomous operation system and autonomous robots. We clarified the information exchange scheme between this system and an outside system furthermore. In future, we will prototype each function and inspect the total system. (author)

Development and Present Situation Analysis of Power Transformer State Maintenance

Science.gov (United States)

Lv, Sen; Li, Biao; Li, Huan

2018-02-01

The pivotal status of power transformer in the power system is one of the most important equipment. The safety and reliability of its operation is directly related to the safety and stability of power system. Based on the analysis of the present situation of power transformer state maintenance in home and abroad. The paper points out the deficiency of the current method and provides a theoretical basis for further research, which has a certain guiding significance.

Paranal maintenance and CMMS experience

Science.gov (United States)

Montano, Nelson

2004-10-01

During the last four years of operations, low technical downtime has been one of the relevant records of the Paranal Observatory. From the beginning of the Very Large Telescope (VLT) project, European Southern Observatory (ESO) has considered the implementation of a proper maintenance strategy a fundamental point in order to ensure low technical down time and preserve the Observatory's assets. The implementation of the maintenance strategy was based on the following aspects: - Strong maintenance sense during the design stage. Line Replacement Unit (LRU) concept, standardization and modularity of the Observatory equipment - Creation of a dedicated team for Maintenance - The implementation of a Computerized Maintenance Management System After four operational years, the result of these aspects has exceeded the expectations; the Observatory has been operating with high availability under a sustainable strategy. The strengths of the maintenance strategy have been based on modern maintenance concepts applied by regular production companies, where any minute of down time involves high cost. The operation of the actual Paranal Maintenance System is based mainly on proactive activities, such as regular inspections, preventive maintenance (PM) and predictive maintenance (PdM) plans. Nevertheless, it has been necessary to implement a strong plan for corrective maintenance (CM). The Spare Parts Strategy has also been an important point linked to the Maintenance Strategy and CMMS implementation. At present, almost 4,000 items related to the Observatory spare parts are loaded into the CMMS database. Currently, we are studying the implementation of a Reliability Centered Maintenance (RCM) project in one of our critical systems The following document presents the actual status of the Paranal Maintenance Strategy and which have been the motivations to implement the established strategy.

Operating and maintenance experience with computer-based systems in nuclear power plants - A report by the PWG-1 Task Group on Computer-based Systems Important to Safety

International Nuclear Information System (INIS)

1998-01-01

This report was prepared by the Task Group on Computer-based Systems Important to Safety of the Principal Working Group No. 1. Canada had a leading role in this study. Operating and Maintenance Experience with Computer-based Systems in nuclear power plants is essential for improving and upgrading against potential failures. The present report summarises the observations and findings related to the use of digital technology in nuclear power plants. It also makes recommendations for future activities in Member Countries. Continued expansion of digital technology in nuclear power reactor has resulted in new safety and licensing issues, since the existing licensing review criteria were mainly based on the analogue devices used when the plants were designed. On the industry side, a consensus approach is needed to help stabilise and standardise the treatment of digital installations and upgrades while ensuring safety and reliability. On the regulatory side, new guidelines and regulatory requirements are needed to assess digital upgrades. Upgrades or new installation issues always involve potential for system failures. They are addressed specifically in the 'hazard' or 'failure' analysis, and it is in this context that they ultimately are resolved in the design and addressed in licensing. Failure Analysis is normally performed in parallel with the design, verification and validation (V and V), and implementation activities of the upgrades. Current standards and guidelines in France, U.S. and Canada recognise the importance of failure analysis in computer-based system design. Thus failure analysis is an integral part of the design and implementation process and is aimed at evaluating potential failure modes and cause of system failures. In this context, it is essential to define 'System' as the plant system affected by the upgrade, not the 'Computer' system. The identified failures would provide input to the design process in the form of design requirements or design

(Hydro-Quebec) Illustrated vocabulary representing power line transmission and distribution of electric power. 4, maintenance. (Hydro-Quebec) Vocabulaire illustre des lignes aeriennes de transport et de distribution d'electricite. Fascicule 4, entretien

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

This dictionary is intended to help standardize the terminology used among Hydro-Quebec personnel involved with power lines. This volume is concerned with words applicable to power line maintenance, and is arranged in six parts: poles and link sticks, adapters and related tools, safety devices, safety clothing and climbing equipment, measurement and control devices, and techniques. Virtually all of the terms are illustrated. English language equivalents are given, but these are not standardized terms and are included for informative purposes only. English and French indexes are included. 184 refs., 256 figs.

Design of the randomized, Phase III, QUAZAR AML Maintenance trial of CC-486 (oral azacitidine) maintenance therapy in acute myeloid leukemia.

Science.gov (United States)

Roboz, Gail J; Montesinos, Pau; Selleslag, Dominik; Wei, Andrew; Jang, Jun-Ho; Falantes, Jose; Voso, Maria T; Sayar, Hamid; Porkka, Kimmo; Marlton, Paula; Almeida, Antonio; Mohan, Sanjay; Ravandi, Farhad; Garcia-Manero, Guillermo; Skikne, Barry; Kantarjian, Hagop

2016-02-01

Older patients with acute myeloid leukemia (AML) have worse rates of complete remission and shorter overall survival than younger patients. The epigenetic modifier CC-486 is an oral formulation of azacitidine with promising clinical activity in patients with AML in Phase I studies. The Phase III, randomized, double-blind, placebo-controlled QUAZAR AML Maintenance trial (CC-486-AML-001) examines CC-486 maintenance therapy (300 mg/day for 14 days of 28-day treatment cycles) for patients aged ≥55 years with AML in first complete remission. The primary end point is overall survival. Secondary end points include relapse-free survival, safety, health-related quality of life and healthcare resource utilization. This trial will investigate whether CC-486 maintenance can prolong remission and improve survival for older patients with AML.

On-Line Maintenance Methodology Development

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyo Won; Kim, Jae Ho; Jae, Moo Sung [Hanyang University, Seoul (Korea, Republic of)

2012-05-15

Most of domestic maintenance activities for nuclear power plants are performed while overhaul. Therefore, On-Line Maintenance (OLM) is one of the proper risks informed application techniques for diffusing maintenance burden during overhaul with safety of the plant is secured. The NUMARC 93-01 (Rev.3) presents the OLM state of the art and it provides methodology. This study adopts NUMARC 93-01 (Rev.3) and present OLM. The reference component is Emergency Diesel Generator (EDG) of Ulchin 3, 4

Regulatory oversight of maintenance activities at nuclear power plants

International Nuclear Information System (INIS)

Pape, M.

1997-01-01

Regulation of nuclear safety in the UK is based on monitoring of compliance with licence conditions. This paper discusses legislation aspects, license conditions, license requirements for maintenance and maintenance activities in the UK. It also addresses the regulator utility interaction, the regulatory inspection of maintenance and the trends in maintenance. (author)

High-precision relative position and attitude measurement for on-orbit maintenance of spacecraft

Science.gov (United States)

Zhu, Bing; Chen, Feng; Li, Dongdong; Wang, Ying

2018-02-01

In order to realize long-term on-orbit running of satellites, space stations, etc spacecrafts, in addition to the long life design of devices, The life of the spacecraft can also be extended by the on-orbit servicing and maintenance. Therefore, it is necessary to keep precise and detailed maintenance of key components. In this paper, a high-precision relative position and attitude measurement method used in the maintenance of key components is given. This method mainly considers the design of the passive cooperative marker, light-emitting device and high resolution camera in the presence of spatial stray light and noise. By using a series of algorithms, such as background elimination, feature extraction, position and attitude calculation, and so on, the high precision relative pose parameters as the input to the control system between key operation parts and maintenance equipment are obtained. The simulation results show that the algorithm is accurate and effective, satisfying the requirements of the precision operation technique.

Significant advantages of the safety-first concept in construction, operation, and maintenance of the Westinghosue AP1000 reactor

International Nuclear Information System (INIS)

Cummins, E.; Benitz, K.

2004-01-01

In June 2003, the U.S. Nuclear Regulatory Commission (USNRC) published a draft opinion about safety of the AP1000 Westinghouse pressurized water reactor with 'passive safety' features. The report constitutes an important milestone in the development of the next generation of safe and cost-efficient nuclear power plants. A new AP1000 can be absolutely competitive with fossil fired power plants and may be able to revive the construction of new nuclear power plants worldwide. The reason for designing the AP1000 were safety considerations. The use of passive safety systems at the same time entails a considerable reduction in the costs of design, maintenance, and operation of an AP1000 plant. Independent experts confirmed that an AP1000 can be erected within three years or even less. The estimated electricity generating costs of an AP1000 plant in the United States amount to US Cent 3.2 to 3.6 per kilowatthour. (orig.)

Interface management: Effective communication to improve process safety

International Nuclear Information System (INIS)

Kelly, Brian; Berger, Scott

2006-01-01

Failure to successfully communicate maintenance activities, abnormal conditions, emergency response procedures, process hazards, and hundreds of other items of critical information can lead to disaster, regardless of the thoroughness of the process safety management system. Therefore, a well-functioning process safety program depends on maintaining successful communication interfaces between each involved employee or stakeholder and the many other employees or stakeholders that person must interact with. The authors discuss a process to identify the critical 'Interfaces' between the many participants in a process safety management system, and then to establish a protocol for each critical interface

Hualong One's nuclear reactor core design and relative safety issues research

Energy Technology Data Exchange (ETDEWEB)

Yu, H., E-mail: yuhong_xing@126.com [Nuclear Power Inst. of China, Design and Research Sub-Inst., Chengdu, Sichuan (China)

2015-07-01

'Full text:' Hualong One, a third generation 1000MWe-class pressurized water reactor, is developed by China National Nuclear Cooperation (CNNC), based on the self-reliant technologies and experiences from China 40 years designing, construction, operation and maintenance of NPPs. In China, it has been approved to construct at Fuqing 5&6 and Fangchenggang 3&4. The Hualong One adopts advanced design features to dramatically enhance plant safety, economic efficiency and convenience of operation and maintenance. It consists of three loops with nominal thermal power output 3060 MWt and a 60-year design life. Its reactor core has 177 fuel assemblies, 18 month refueling interval (after initial cycle), and more than 15% thermal margin. It adopts low leakage loading pattern which can achieve better economy of the neutron, higher reactivity and lower radiation damage of pressure vessel. For the safety design, incorporating the feedback of Fukushima accident, the Hualong One has a combination of active and passive safety systems, a single station layout, double containment structure, and comprehensive implementation of defence-in-depth design principles. The new design features has been successfully evaluated to ensure that they enhance the performance and safety of Hualong One. Several experimental activates have been conducted, such as cavity injection and cooling system testing, passive containment heat removal system testing, and passive residual heat removal system of secondary side testing. The future improvements of Hualong reactor will focus on better economic core design and more reliable safety system. (author)

49 CFR 244.13 - Subjects to be addressed in a Safety Integration Plan involving an amalgamation of operations.

Science.gov (United States)

2010-10-01

... transaction: (a) Corporate culture. Each applicant shall: (1) Identify and describe differences for each safety-related area between the corporate cultures of the railroads involved in the transaction; (2... step-by-step measures, the integration of these corporate cultures and the manner in which it will...

AREVA NP products and services for NPP operation and maintenance improvement

International Nuclear Information System (INIS)

Dechelette, Anne; Rat, Guy Le

2009-01-01

AREVA supplies customized services throughout the reactor improvement process according to clients' requirements: safety, performance, availability, obsolescence, operating and maintenance conditions, environment and technical assistance. Form design studies to on site modification and implementation including requalification tests, AREVA, as OEM*, has various products and services in the field of Engineering and Upgrading to satisfy client demands. In keeping with Inpo's AP913 approach, AREVA is particularly skilled in this methodology to help utilities improve availability factor and maintenance programs. AREVA has customized its services to many utilities in cooperating with local partners, suppliers, and engineering service providers through partnerships, consortiums, joint ventures, etc. AREVA's knowledge of the fleet's operation and maintenance experience helps NPP clients to identify the most cost effective improvements and approaches. Different examples of modifications of modifications and improvements performed in France and abroad illustrate AREVA's involvement in the NPP continuous upgrade process

RCM [reliability-centered maintenance] at Ginna: Preventive maintenance program optimization at year 20

International Nuclear Information System (INIS)

Edgar, E.C.

1989-01-01

The reliability-centered maintenance (RCM) program at Rochester Gas ampersand Electric Company's Ginna station is entering its second year. Of the 20 systems originally selected for evaluation, 10 are in various stages of completion, and recommendations resulting from the earliest systems studied are now being implemented. As expected, few major discoveries have been made in terms of preventive maintenance program failings or excesses. The performance of the now 20-yr-old plant has been excellent in recent years, and objectives focus more on ensuring continued high standards of safety, reliability, and economy than on maintenance program cost reduction

Age-dependent reliability model considering effects of maintenance and working conditions

International Nuclear Information System (INIS)

Martorell, Sebastian; Sanchez, Ana; Serradell, Vicente

1999-01-01

Nowadays, there is some doubt about building new nuclear power plants (NPPs). Instead, there is a growing interest in analyzing the possibility to extend current NPP operation, where life management programs play an important role. The evolution of the NPP safety depends on the evolution of the reliability of its safety components, which, in turn, is a function of their age along the NPP operational life. In this paper, a new age-dependent reliability model is presented, which includes parameters related to surveillance and maintenance effectiveness and working conditions of the equipment, both environmental and operational. This model may be used to support NPP life management and life extension programs, by improving or optimizing surveillance and maintenance tasks using risk and cost models based on such an age-dependent reliability model. The results of the sensitivity study in the example application show that the selection of the most appropriate maintenance strategy would directly depend on the previous parameters. Then, very important differences are expected to appear under certain circumstances, particularly, in comparison with other models that do not consider maintenance effectiveness and working conditions simultaneously

Development of safety related technology and infrastructure for safety assessment

International Nuclear Information System (INIS)

Venkat Raj, V.

1997-01-01

Development and optimum utilisation of any technology calls for the building up of the necessary infrastructure and backup facilities. This is particularly true for a developing country like India and more so for an advanced technology like nuclear technology. Right from the inception of its nuclear power programme, the Indian approach has been to develop adequate infrastructure in various areas such as design, construction, manufacture, installation, commissioning and safety assessment of nuclear plants. This paper deals with the development of safety related technology and the relevant infrastructure for safety assessment. A number of computer codes for safety assessment have been developed or adapted in the areas of thermal hydraulics, structural dynamics etc. These codes have undergone extensive validation through data generated in the experimental facilities set up in India as well as participation in international standard problem exercises. Side by side with the development of the tools for safety assessment, the development of safety related technology was also given equal importance. Many of the technologies required for the inspection, ageing assessment and estimation of the residual life of various components and equipment, particularly those having a bearing on safety, were developed. This paper highlights, briefly, the work carried out in some of the areas mentioned above. (author)

Risk based maintenance: Resource requirements and organizational challenges

International Nuclear Information System (INIS)

Weerakkody, S.D.

2000-01-01

10CFR50.65 'Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants' required licensees to monitor the performance or condition of structures, systems, or components (SSCs) against licensee established goals, in a manner sufficient to provide reasonable assurance that such SSCs are capable of fulfilling their intended functions. The goals were required to be commensurate with safety significance and operating experience. Northeast Utilities relied upon PRAs to implement 10CFR50.65, which is also referred to as the 'Maintenance Rule'. The Maintenance Rule changed some aspects of maintenance of structures, systems, and components (SSC) at nuclear power plants. One objective of the rule was to focus the maintenance resources based on risk significance of components. This paper will discuss the organizational challenges and resource requirements associated with implementation of the Maintenance Rule at nuclear facilities that are supported by the Northeast Utilities Services Company (NUSCo). The paper will discuss (a) how these challenges were addressed, (b) the resources required for ongoing efforts to support the Maintenance Rule, and (c) several key safety benefits derived from the implementation of the Maintenance Rule. (author)

Architecture and Key Techniques of Augmented Reality Maintenance Guiding System for Civil Aircrafts

Science.gov (United States)

hong, Zhou; Wenhua, Lu

2017-01-01

Augmented reality technology is introduced into the maintenance related field for strengthened information in real-world scenarios through integration of virtual assistant maintenance information with real-world scenarios. This can lower the difficulty of maintenance, reduce maintenance errors, and improve the maintenance efficiency and quality of civil aviation crews. Architecture of augmented reality virtual maintenance guiding system is proposed on the basis of introducing the definition of augmented reality and analyzing the characteristics of augmented reality virtual maintenance. Key techniques involved, such as standardization and organization of maintenance data, 3D registration, modeling of maintenance guidance information and virtual maintenance man-machine interaction, are elaborated emphatically, and solutions are given.

Embracing Safe Ground Test Facility Operations and Maintenance

Science.gov (United States)

Dunn, Steven C.; Green, Donald R.

2010-01-01

Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

Pooling knowledge and improving safety for contracted works at a large industrial park.

Science.gov (United States)

Agnello, Patrizia; Ansaldi, Silvia; Bragatto, Paolo

2015-01-01

At a large chemical park maintenance is contracted by the major companies operating the plants to many small firms. The cultural and psychological isolation of contractor workers was recognized a root cause of severe accidents in the recent years. That problem is common in chemical industry. The knowledge sharing has been assumed a good key to involve contractors and sub contractors in safety culture and contributing to injuries prevention. The selection of personal protective equipment PPE for the maintenance works has been taken as benchmark to demonstrate the adequateness of the proposed approach. To support plant operators, contractors and subcontractors in PPE discussion, a method has been developed. Its core is a knowledge-base, organized in an Ontology, as suitable for inferring decisions. By means of this tool all stakeholders have merged experience and information and find out the right PPE, to be provided, with adequate training and information package. PPE selection requires sound competencies about process and environmental hazards, including major accident, preventive and protective measures, maintenance activities. These pieces of knowledge previously fragmented among plant operators and contractors, have to be pooled, and used to find out the adequate PPE for a number of maintenance works. The PPE selection is per se important, but it is also a good chance to break the contractors' isolation and involve them in safety objectives. Thus by pooling experience and practical knowledge, the common understanding of safety issues has been strengthened.

Challenges in the management of gas voids in safety related systems

International Nuclear Information System (INIS)

Ezekoye, L.I.; Turkowski, W.M.; Ferraraccio, F.P.; Swartz, M.M.

2009-01-01

of mechanisms, such as maintenance, gas desorption, vortex activities, cavitation, etc. This paper discusses the sources of gas into safety related systems and the challenges associated with management of gas voids in these systems. Various issues such as gas monitoring, gas purging, gas transport characterization in piping, gas ingestion in safety related pumps, water hammer in discharge piping, and gas impact on the core cooling during design basis accidents are discussed. Industry efforts to support the management of gases in these systems are also presented

Challenges in the management of gas voids in safety related systems

Energy Technology Data Exchange (ETDEWEB)

Ezekoye, L.I.; Turkowski, W.M.; Ferraraccio, F.P.; Swartz, M.M. [Westinghouse Electric Company LLC, Pittsburgh (United States)

2009-04-15

a number of mechanisms, such as maintenance, gas desorption, vortex activities, cavitation, etc. This paper discusses the sources of gas into safety related systems and the challenges associated with management of gas voids in these systems. Various issues such as gas monitoring, gas purging, gas transport characterization in piping, gas ingestion in safety related pumps, water hammer in discharge piping, and gas impact on the core cooling during design basis accidents are discussed. Industry efforts to support the management of gases in these systems are also presented.

Bayesian hypothesis testing and the maintenance rule

International Nuclear Information System (INIS)

Kelly, D.L.

1997-01-01

The Maintenance Rule (10 CFR 50.65) went into effect in the United States in July 1996. It requires commercial nuclear utilities to monitor system performance (system reliability and maintenance unavailability) for systems that are determined by the utility to be important to plant safety. Utilities must set performance goals for such systems and monitor system performance against these goals. In addition, these performance goals are intended to be commensurate with the safety significance of the system, which can be established by a probabilistic safety assessment of the plant. The author examines the frequents approach to monitoring performance, which is being used by several utilities, and proposes an alternative Bayesian approach. The Bayesian approach makes more complete use of the information in the probabilistic safety assessment, is consistent philosophically with the subjective interpretation given to probability in most probabilistic safety assessments, overcomes several pitfalls in the frequents approach, provides results which are easily interpretable, and is straightforward to implement using the information in the probabilistic safety assessment

Optimism about safety and group-serving interpretations of safety among pedestrians and cyclists in relation to road use in general and under low light conditions.

Science.gov (United States)

King, M J; Wood, J M; Lacherez, P F; Marszalek, R P

2012-01-01

Drivers are known to be optimistic about their risk of crash involvement, believing that they are less likely to be involved in a crash than other drivers. However, little comparative research has been conducted among other road users. In addition, optimism about crash risk is conceptualised as applying only to an individual's assessment of his or her personal risk of crash involvement. The possibility that the self-serving nature of optimism about safety might be generalised to the group-level as a cyclist or a pedestrian, i.e., becoming group-serving rather than self-serving, has been overlooked in relation to road safety. This study analysed a subset of data collected as part of a larger research project on the visibility of pedestrians, cyclists and road workers, focusing on a set of questionnaire items administered to 406 pedestrians, 838 cyclists and 622 drivers. The items related to safety in various scenarios involving drivers, pedestrians and cyclists, allowing predictions to be derived about group differences in agreement with items based on the assumption that the results would exhibit group-serving bias. Analysis of the responses indicated that specific hypotheses about group-serving interpretations of safety and responsibility were supported in 22 of the 26 comparisons. When the nine comparisons relevant to low lighting conditions were considered separately, seven were found to be supported. The findings of the research have implications for public education and for the likely acceptance of messages which are inconsistent with current assumptions and expectations of pedestrians and cyclists. They also suggest that research into group-serving interpretations of safety, even for temporary roles rather than enduring groups, could be fruitful. Further, there is an implication that gains in safety can be made by better educating road users about the limitations of their visibility and the ramifications of this for their own road safety, particularly in low

Paper number: ID 576... Monitoring and maintenance of pumps in LWR

International Nuclear Information System (INIS)

Heller, M.; Einzmann, K.

2001-01-01

Due to the liberalization of the European Market for electrical power nuclear power plants are progressively subjected to high pressure in respect of reducing the overall costs including for maintenance actions. This concerns also the maintenance of active components as pumps or valves. Siemens Nuclear Power (SNP) has developed a concept for the transition to an integrated condition based maintenance especially for pumps which shall be presented below. It is proposed to make up future decisions on maintenance of pumps only depending on condition data of the component. The concept must be supported by modern monitoring systems, which shall be installed at pumps which are relevant for the safety and availability of the plants. The main technical features of the SNP monitoring system DIROM are presented in detail as an example. First results of acquiring condition related data of a nuclear feed water pump are reported too. The new maintenance concept promises attractive cost benefits in comparison to a former preventive maintenance concept. (author)

Involvement of DNA mismatch repair in the maintenance of heterochromatic DNA stability in Saccharomyces cerevisiae.

Directory of Open Access Journals (Sweden)

Basanta K Dahal

2017-10-01

Full Text Available Heterochromatin contains a significant part of nuclear DNA. Little is known about the mechanisms that govern heterochromatic DNA stability. We show here that in the yeast Saccharomyces cerevisiae (i DNA mismatch repair (MMR is required for the maintenance of heterochromatic DNA stability, (ii MutLα (Mlh1-Pms1 heterodimer, MutSα (Msh2-Msh6 heterodimer, MutSβ (Msh2-Msh3 heterodimer, and Exo1 are involved in MMR at heterochromatin, (iii Exo1-independent MMR at heterochromatin frequently leads to the formation of Pol ζ-dependent mutations, (iv MMR cooperates with the proofreading activity of Pol ε and the histone acetyltransferase Rtt109 in the maintenance of heterochromatic DNA stability, (v repair of base-base mismatches at heterochromatin is less efficient than repair of base-base mismatches at euchromatin, and (vi the efficiency of repair of 1-nt insertion/deletion loops at heterochromatin is similar to the efficiency of repair of 1-nt insertion/deletion loops at euchromatin.

THE NATIONAL AUTHORITY FOR ANIMAL HEALTH AND FOOD SAFETY, THE MAIN BODY INVOLVED IN FOOD SAFETY IN ROMANIA

Directory of Open Access Journals (Sweden)

PETRUTA-ELENA ISPAS

2012-05-01

Full Text Available This paper is intended to present the role, functions and responsibilities of the National Authority for Animal Health and Food Safety as the main body involved in food safety in Romania. It will be also exposed the Regulation 178/2002 of the European Parliament and the Council, the general food ”law” in Europe, and Law 150/2004, which transposed into Romanian legislation Regulation 178/2002.

Software quality assurance for safety analysis and risk management at the Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.; Toffer, H.; Crowe, R.D.

1991-01-01

As part of its Reactor Operations Improvement Program at the Savannah River Site (SRS), Westinghouse Savannah River Company (WSRC), in cooperation with the Westinghouse Hanford Company, has developed and implemented quality assurance for safety-related software for technical programs essential to the safety and reliability of reactor operations. More specifically, the quality assurance process involved the development and implementation of quality standards and attendant procedures based on industry software quality standards. These procedures were then applied to computer codes in reactor safety and probabilistic risk assessment analyses. This paper provides a review of the major aspects of the WSRC safety-related software quality assurance. In particular, quality assurance procedures are described for the different life cycle phases of the software that include the Requirements, Software Design and Implementation, Testing and Installation, Operation and Maintenance, and Retirement Phases. For each phase, specific provisions are made to categorize the range of activities, the level of responsibilities, and the documentation needed to assure the control of the software. The software quality assurance procedures developed and implemented are evolutionary in nature, and thus, prone to further refinements. These procedures, nevertheless, represent an effective controlling tool for the development, production, and operation of safety-related software applicable to reactor safety and probabilistic risk assessment analyses

Nuclear power plant maintenance scheduling dilemma: a genetic algorithm approach

International Nuclear Information System (INIS)

Mahdavi, M.H.; Modarres, M.

2004-01-01

There are huge numbers of components scheduled for maintenance when a nuclear power plant is shut down. Among these components, a number of them are safety related which their operability as well as reliability when plant becomes up is main concerns. Not performing proper maintenance on this class of components/system would impose substantial risk on operating the NPP. In this paper a new approach based on genetic algorithms is presented to optimize the NPP maintenance schedule during shutdown. following this approach the cost incurred by maintenance activities for each schedule is balanced with the risk imposed by the maintenance scheduling plan to the plant operation status when it is up. The risk model implemented in the GA scheduler as its evaluation function is developed on the basis of the probabilistic risk assessment methodology. the Ga optimizers itself is shown to be superior compared to other optimization methods such as the monte carlo technique

PSO Based Optimization of Testing and Maintenance Cost in NPPs

Directory of Open Access Journals (Sweden)

Qiang Chou

2014-01-01

Full Text Available Testing and maintenance activities of safety equipment have drawn much attention in Nuclear Power Plant (NPP to risk and cost control. The testing and maintenance activities are often implemented in compliance with the technical specification and maintenance requirements. Technical specification and maintenance-related parameters, that is, allowed outage time (AOT, maintenance period and duration, and so forth, in NPP are associated with controlling risk level and operating cost which need to be minimized. The above problems can be formulated by a constrained multiobjective optimization model, which is widely used in many other engineering problems. Particle swarm optimizations (PSOs have proved their capability to solve these kinds of problems. In this paper, we adopt PSO as an optimizer to optimize the multiobjective optimization problem by iteratively trying to improve a candidate solution with regard to a given measure of quality. Numerical results have demonstrated the efficiency of our proposed algorithm.

Safety assessment of ammonia as a transport fuel

Energy Technology Data Exchange (ETDEWEB)

Duijm, N.J.; Markert, F.; Lundtang paulsen, Jette

2005-02-01

This report describes the safety study performed as part of the EU supported project 'Ammonia Cracking for Clean Electric Power Technology' The study addresses the following activities: safety of operation of the ammonia-powered vehicle under normal and accident (collision) conditions, safety of transport of ammonia to the refuelling stations and safety of the activities at the refuelling station (unloading and refuelling). Comparisons are made between the safety of using ammonia and the safety of other existing or alternative fuels. The conclusion is that the hazards in relation to ammonia need to be controlled by a combination of technical and regulatory measures. The most important requirements are: - Advanced safety systems in the vehicle - Additional technical measures and regulations are required to avoid releases in maintenance workshops and unauthorised maintenance on the fuel system - Road transport of ammonia to refuelling stations in refrigerated form - Sufficient safety zones between refuelling stations and residential or otherwise public areas. When these measures are applied, the use of ammonia as a transport fuel wouldnt cause more risks than currently used fuels (using current practice). (au)

Probabilistic analysis of free ways for maintenance

International Nuclear Information System (INIS)

Torres V, A.; Rivero O, J.J.

2004-01-01

The safety during the maintenance interventions is treated in limited manner and in general independent of the systems of management of the maintenance. This variable is affected by multiple technical or human factors many times subjective and difficult to quantifying, what limits the design of preventive plans. However, some factors constitute common points: the isolation configurations during the free ways (bank drafts in the oil industry) and the human errors associated to their violation. This characteristic allowed to develop the analysis of such situations through the methodology of fault trees that it links faults of teams and human errors cohesively. The methodology has been automated inside the MOSEG Win Ver 1.0 code and the same one can embrace from the analysis of a particular situation of free way until that of a complete strategy of maintenance from the point of view of the safety of the maintenance personal. (Author)

Maintenance of radiation monitoring systems

International Nuclear Information System (INIS)

Aoyama, Kei

2001-01-01

As the safety and quality of atomic power facilities are more strongly required, the reliability improvement and preventive maintenance of radiation monitoring systems are important. This paper describes the maintenance of radiation monitoring systems delivered by Fuji Electric and the present status of preventive maintenance technology. Also it introduces the case that we developed a fault diagnosis function adopting a statistics technique and artificial intelligence (AI) and delivered a radiation monitoring system including this function. This system can output a fault analysis result and a countermeasure from the computer in real time. (author)

Ventilation: Exploitation and maintenance. Ten years of experience

International Nuclear Information System (INIS)

Letertre, J.

1990-01-01

The evolution and the maintenance operations performed during the last ten years on the ventilation-air-conditioning system at the Hague plant are presented. The modifications operated in the ventilation-air-conditioning system were carried out in order to answer the safety requirements evolution due to the increase of the plant productivity. The choice and the results of the maintenance policies, defined as a function of the safety, quality and cost requirements, are presented [fr

The Influence Paths of Emotion on the Occupational Safety of Rescuers Involved in Environmental Emergencies- Systematic Review Article.

Science.gov (United States)

Lu, Jintao; Yang, Naiding; Ye, Jinfu; Wu, Haoran

2014-11-01

A detailed study and analysis of previous research has been carried out to illustrate the relationships between a range of environmental emergencies, and their effects on the emotional state of the rescuers involved in responding to them, by employing Pub Med, Science Direct, Web of Science, Google Scholar, CNKI and Scopus for required information with the several keywords "emergency rescue", "occupational safety", "natural disaster", "emotional management". The effect of the rescuers' emotion on their occupational safety and immediate and long-term emotional behavior is then considered. From these considerations, we suggested four research propositions related to the emotional effects at both individual and group levels, and to the responsibilities of emergency response agencies in respect of ensuring the psychological and physical occupational safety of rescuers during and after environmental emergencies. An analysis framework is proposed which could be used to study the influence paths of these different aspects of emotional impact on a range of occupational safety issues for rescue workers. The authors believe that the conclusions drawn in this paper can provide a useful theoretical reference for decision-making related to the management and protection of the occupational safety of rescuers responding to natural disasters and environmental emergencies.

Radiation safety and control

International Nuclear Information System (INIS)

Kim, Jang Hee; Kim, Gi Sub.

1996-12-01

The principal objective of radiological safety control is intended for achievement and maintenance of appropriately safe condition in environmental control for activities involving exposure from the use of radiation. In order to establish these objective, we should be to prevent deterministic effects and to limit the occurrence stochastic effects to level deemed to be acceptable by the application of general principles of radiation protection and systems of dose limitation based on ICRP recommendations. (author). 22 tabs., 13 figs., 11 refs

Radiological safety and control

International Nuclear Information System (INIS)

Kim, Jang Hee; Kim, Ki Sub

1995-01-01

The practical objective of radiological safety control is intended for achievement and maintenance of appropreately safe condition in environmental control for activities involving exposure from the use of radiation. In order to establish these objectives, we should be to prevent deterministic effects and to limit the occurrence stochastic effects to level deemed to be acceptable by the application of general principles of radiation protection and systems of dose limitation based on ICRP recommendations. 34 tabs., 19 figs., 11 refs. (Author) .new

Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

International Nuclear Information System (INIS)

Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

2012-01-01

Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

Quantitative techniques for medical equipment maintenance management

NARCIS (Netherlands)

Ben Houria, Zeineb; Masmoudi, Malek; Al Hanbali, Ahmad; Khatrouch, Ikram; Masmoudi, Faouzi

2016-01-01

The maintenance department in a hospital is responsible for ensuring the safety of medical equipment and their availability while keeping the operation costs minimal. The selection of the best maintenance strategy is a key decision to reduce the equipment downtime, increase the availability, and

Seismic qualification of multiple interconnected safety-related cabinets in a high seismic zone

International Nuclear Information System (INIS)

Khan, M.R.; Chen, W.H.W.; Wang, T.Y.

1993-01-01

Certain safety-related multiple, interconnected electrical cabinets and the devices contained therein are required to perform their intended safety functions during and after a design basis seismic event. In general, seismic testing is performed to ensure the structural integrity of the cabinets and the functionality of their associated devices. Constrained by the shake table capacity, seismic testing is usually performed only for a limited number of interconnected cabinets. Also, original shake table tests performed usually did not provide detailed response information at various locations inside the cabinets. For operational and maintenance purposes, doors and panels of some cabinets may need to be opened while the adjacent cabinets are required to remain functional. In addition, in-cabinet response spectra need to be generated for the seismic qualification of new devices and the replacement parts. Consequently, seismic analysis of safety-related multiple, interconnected cabinets is frequently required for configurations which are different from the original tested conditions. This paper presents results of seismic tests of three interconnected safety-related cabinets and finite element analyses performed to compare the analytical results with those obtained from the cabinet seismic tests. Parametric analyses are performed to determine how many panels and doors can be opened while the adjacent cabinets still remain functional. The study indicates that for cabinets located in a high seismic zone, the critical damping of the cabinet is significantly higher than 5% to 7% typically used in qualifying electrical equipment. For devices mounted on the cabinet doors to performed their intended safety function, it requires stiffening of doors and that these doors be properly bolted to the cabinet frame. It also shows that even though doors and panels bolted to the cabinet frame are the primary seismic resistant element of the cabinet, opening of a limited number of them

Standard practice for qualification of journeyman painters for application of coatings to steel surfaces of safety-related areas in nuclear facilities

International Nuclear Information System (INIS)

Anon.

1984-01-01

This practice provides a standard qualifying method for journeyman painters to verify their proficiency and ability to attain the required quality for application of specified coatings to steel surfaces in safety-related areas in a nuclear facility. Variations or simplifications of the practice set forth herein may be appropriate for special coating work such as maintenance or qualifications of equipment suppliers shop personnel. It is not the intent of this practice to mandate a singular basis for all qualifications. Evaluation of the journeyman painter being qualified in accordance with this practice, shall be by qualified agents as specified in 4.1. Reports shall be prepared as specified in Section 5, and certification as specified in Section 6. It is the intent of this practice to judge only the ability of the journeyman painter to apply specified coatings with the proper tools and equipment. This standard may involve hazardous materials, operations, and equipment

Qualification of safety-related valve actuators

International Nuclear Information System (INIS)

Anon.

1981-01-01

This Standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. It may also be used to separately qualify actuator components. This Standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of all safety-related functions of power-driven valve actuators

Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

Feasibility study of component risk ranking for plant maintenance

International Nuclear Information System (INIS)

Ushijima, Koji; Yonebayashi, Kenji; Narumiya, Yoshiyuki; Sakata, Kaoru; Kumano, Tetsuji

1999-01-01

Nuclear power is the base load electricity source in Japan, and reduction of operation and maintenance cost maintaining or improving plant safety is one of the major issues. Recently, Risk Informed Management (RIM) is focused as a solution. In this paper, the outline regarding feasibility study of component risk ranking for plant maintenance for a typical Japanese PWR plant is described. A feasibility study of component risk raking for plant maintenance optimization is performed on check valves and motor-operated valves. Risk ranking is performed in two steps using probabilistic analysis (quantitative method) for risk ranking of components, and deterministic examination (qualitative method) for component review. In this study, plant components are ranked from the viewpoint of plant safety / reliability, and the applicability for maintenance is assessed. As a result, distribution of maintenance resources using risk ranking is considered effective. (author)

Integrated Design and Approach of Building Maintenance Management in the Built Environment

Directory of Open Access Journals (Sweden)

Md Azree Othuman Mydin

2017-12-01

Full Text Available Building maintenance is such a crucial aspect in the construction industry. The construction industry is characterized as a project-based industry that delivers one of a kind products and services. Thus, building maintenance can guarantee the safety of buildings including human health and property. To some extent, it plays as a guard to supervise the buildings protecting them being suffered collapse and deterioration. The most importantly, preparing for maintenance carried out on buildings is complex and it is related to procurement system dramatically, such as design-and-build, design-build-finance operate, and the private finance initiative and public/private partnerships, all of them need to give much consideration of operational and maintenance needs and costs which are ongoing.. This paper will focus on design and approach of building maintenance management in the construction industry.

Double-stranded DNA-dependent ATPase Irc3p is directly involved in mitochondrial genome maintenance.

Science.gov (United States)

Sedman, Tiina; Gaidutšik, Ilja; Villemson, Karin; Hou, YingJian; Sedman, Juhan

2014-12-01

Nucleic acid-dependent ATPases are involved in nearly all aspects of DNA and RNA metabolism. Previous studies have described a number of mitochondrial helicases. However, double-stranded DNA-dependent ATPases, including translocases or enzymes remodeling DNA-protein complexes, have not been identified in mitochondria of the yeast Saccharomyces cerevisae. Here, we demonstrate that Irc3p is a mitochondrial double-stranded DNA-dependent ATPase of the Superfamily II. In contrast to the other mitochondrial Superfamily II enzymes Mss116p, Suv3p and Mrh4p, which are RNA helicases, Irc3p has a direct role in mitochondrial DNA (mtDNA) maintenance. Specific Irc3p-dependent mtDNA metabolic intermediates can be detected, including high levels of double-stranded DNA breaks that accumulate in irc3Δ mutants. irc3Δ-related topology changes in rho- mtDNA can be reversed by the deletion of mitochondrial RNA polymerase RPO41, suggesting that Irc3p counterbalances adverse effects of transcription on mitochondrial genome stability. © The Author(s) 2014. Published by Oxford University Press on behalf of Nucleic Acids Research.

Reliability Analysis on NPP's Safety-Related Control Module with Field Data

International Nuclear Information System (INIS)

Lee, Sang Yong; Jung, Jae Hyun; Kim, Seong Hun

2006-01-01

The automatic control systems used in nuclear power plant (NPP) consists of numerous control modules that can be considered to be a network of components various complex ways. The control modules require relatively high reliability than industrial electronic products. Reliability prediction provides the rational basis of system designs and also provides the safety significance of system operations. The aim of this paper is to minimize the deficiencies of the traditional reliability prediction method calculation using the available field return data. This way is possible to do more realistic reliability assessment. SAMCHANG Enterprise Company (SEC) has established database containing high quality data at the module and component level from module maintenance in NPP. On the basis of these, this paper compares results that add failure record (field data) to Telcordia-SR-332 reliability prediction model with MIL-HDBK-217F prediction results

Subcontracting Railway Maintenance

DEFF Research Database (Denmark)

Thommesen, Jacob

2010-01-01

railway infrastructure manager (InfraMan), whichis subcontracting maintenance tasks to other companies. InfraMan has implemented various central elements in managing their subcontractors. The latter are required to present a safety plan as part of their bid, they must be approved if they are to be awarded...

Dr. Mainte. Integrated simulator of maintenance optimization of LWRs

International Nuclear Information System (INIS)

Isobe, Yoshihiro; Sagisaka, Mitsuyuki; Etoh, Junji; Matsunaga, Takashi; Kosaka, Toru; Matsumoto, Satoshi; Yoshimura, Shinobu

2014-01-01

Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for representative components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement of the safety and availability, the effect of human error and its reduction on the optimization of plant maintenance activities and approaches of reducing it have been studied. (author)

New activities in nuclear power plants maintenance

International Nuclear Information System (INIS)

Mico, F.; Specht, J.

2006-01-01

This article addresses the consequences of the progressive deregulation of the electricity market of several key countries on the maintenance practices and techniques face to the growing pressures on O and M costs. The responses of the nuclear maintenance industry to make maintenance activities more efficient maintaining if not enhancing the safety of NPP's are briefly described. The article also analyses the potential impact of shortage of experience maintenance personnel to serve the NPP's in the future as some countries are already experiencing. (Author)

Explaining variations in state foster care maintenance rates and the implications for implementing new evidence-based programs

Science.gov (United States)

Goldhaber-Fiebert, Jeremy D.; Babiarz, Kimberly S.; Garfield, Rachel L.; Wulczyn, Fred; Landsverk, John; Horwitz, Sarah M.

2013-01-01

Background U.S. Child Welfare systems are involved in the lives of millions of children, and total spending exceeds $26 billion annually. Out-of-home foster care is a critical and expensive Child Welfare service, a major component of which is the maintenance rate paid to support housing and caring for a foster child. Maintenance rates vary widely across states and over time, but reasons for this variation are not well understood. As evidence-based programs are disseminated to state Child Welfare systems, it is important to understand what may be the important drivers in the uptake of these practices including state spending on core system areas. Data and methods We assembled a unique, longitudinal, state-level panel dataset (1990–2008) for all 50 states with annual data on foster care maintenance rates and measures of child population in need, poverty, employment, urbanicity, proportion minority, political party control of the state legislature and governorship, federal funding, and lawsuits involving state foster care systems. All monetary values were expressed in per-capita terms and inflation adjusted to 2008 dollars. We used longitudinal panel regressions with robust standard errors and state and year fixed effects to estimate the relationship between state foster care maintenance rates and the other factors in our dataset, lagging all factors by one year to mitigate the possibility that maintenance rates influenced their predictors. Exploratory analyses related maintenance rates to Child Welfare outcomes. Findings State foster care maintenance rates have increased in nominal terms, but in many states, have not kept pace with inflation, leading to lower real rates in 2008 compared to those in 1991 for 54% of states for 2 year-olds, 58% for 9 year-olds, and 65% for 16 year-olds. In multivariate analyses including socioeconomic, demographic, and political factors, monthly foster care maintenance rates declined $15 for each 1% increase in state unemployment and

A holistic framework of degradation modeling for reliability analysis and maintenance optimization of nuclear safety systems

International Nuclear Information System (INIS)

Lin, Yanhui

2016-01-01

Components of nuclear safety systems are in general highly reliable, which leads to a difficulty in modeling their degradation and failure behaviors due to the limited amount of data available. Besides, the complexity of such modeling task is increased by the fact that these systems are often subject to multiple competing degradation processes and that these can be dependent under certain circumstances, and influenced by a number of external factors (e.g. temperature, stress, mechanical shocks, etc.). In this complicated problem setting, this PhD work aims to develop a holistic framework of models and computational methods for the reliability-based analysis and maintenance optimization of nuclear safety systems taking into account the available knowledge on the systems, degradation and failure behaviors, their dependencies, the external influencing factors and the associated uncertainties.The original scientific contributions of the work are: (1) For single components, we integrate random shocks into multi-state physics models for component reliability analysis, considering general dependencies between the degradation and two types of random shocks. (2) For multi-component systems (with a limited number of components):(a) a piecewise-deterministic Markov process modeling framework is developed to treat degradation dependency in a system whose degradation processes are modeled by physics-based models and multi-state models; (b) epistemic uncertainty due to incomplete or imprecise knowledge is considered and a finite-volume scheme is extended to assess the (fuzzy) system reliability; (c) the mean absolute deviation importance measures are extended for components with multiple dependent competing degradation processes and subject to maintenance; (d) the optimal maintenance policy considering epistemic uncertainty and degradation dependency is derived by combining finite-volume scheme, differential evolution and non-dominated sorting differential evolution; (e) the

Maintenance Process Strategic Analysis

Science.gov (United States)

Jasiulewicz-Kaczmarek, M.; Stachowiak, A.

2016-08-01

The performance and competitiveness of manufacturing companies is dependent on the availability, reliability and productivity of their production facilities. Low productivity, downtime, and poor machine performance is often linked to inadequate plant maintenance, which in turn can lead to reduced production levels, increasing costs, lost market opportunities, and lower profits. These pressures have given firms worldwide the motivation to explore and embrace proactive maintenance strategies over the traditional reactive firefighting methods. The traditional view of maintenance has shifted into one of an overall view that encompasses Overall Equipment Efficiency, Stakeholders Management and Life Cycle assessment. From practical point of view it requires changes in approach to maintenance represented by managers and changes in actions performed within maintenance area. Managers have to understand that maintenance is not only about repairs and conservations of machines and devices, but also actions striving for more efficient resources management and care for safety and health of employees. The purpose of the work is to present strategic analysis based on SWOT analysis to identify the opportunities and strengths of maintenance process, to benefit from them as much as possible, as well as to identify weaknesses and threats, so that they could be eliminated or minimized.

Maintenance management for nuclear power plant 'Integrated valve maintenance'

International Nuclear Information System (INIS)

Gerner, P.; Zanner, G.

2001-01-01

The deregulation of Europe's power market does force many utilities, and especially nuclear power plant operators, to introduce extensive cost-cutting measures in order to be able to compete within this new environment. The optimization of plant outages provides considerable potential for raising plant availability but can also lower operating costs by reducing e.g. expenditure on maintenance. Siemens Nuclear Power GmbH, in cooperation with plant operators, is currently implementing new and improved service concepts which can have a major effect on the way in which maintenance will be performed in the future. Innovative service packages for maintenance in nuclear power plants are available which can be used to perform a time- and cost-effective maintenance. The concepts encompass optimization of the overall sequence from planning in advance to the individual measures including reduction of the scope of maintenance activities, identification of cost cutting potential and bundling of maintenance activities. The main features of these maintenance activities are illustrated here using the examples of outage planning and integrated valve maintenance. In nuclear power plants approx. 5000 valves are periodically preventively, condition-based or breakdown-based maintained. Because of this large number of valves to be maintained a high potential of improvements and cost reductions can be achieved by performing an optimized, cost-effective maintenance based on innovative methods and tools. Siemens Nuclear Power GmbH has developed and qualified such tools which allow to reduce service costs while maintaining high standards of safety and availability. By changing from preventive to predictive (condition-based) maintenance - the number of valves to be maintained may be reduced considerably. The predictive maintenance is based on the Siemens Nuclear Power GmbH diagnostic and evaluation method (ADAM). ADAM is used to monitor the operability of valves by analytical verification of

Ageing Management Based Maintenance at ETRR-II

Energy Technology Data Exchange (ETDEWEB)

Kamoon, A.; Ali, A., E-mail: akamoun2004@yahoo.com [Inshas Nuclear Research Centre, Egyptian Atomic Energy Authority (EAEA), Cairo (Egypt)

2014-08-15

The second research reactor of Egypt, ETRR-II, is an open pool type multi-purpose reactor of 22 MW that has been in operation since 1998. The main purposes of ETRR-II are the production of radioisotopes, personnel training, research and development. Ageing management of ETRR-II is based on the maintenance programme. This programme was planned to have a proactive maintenance strategy that mainly depends on adequate preventive and predictive maintenance. Screening of SSCs is based on safety classes, needs and quality levels. The operation condition and maintenance history are the basis to assess the level of degradation. The ultimate aim of the maintenance team is to perform adequate maintenance work only when it is really necessary. The objectives of the ageing management based maintenance are to maintain and improve equipment availability, confirm compliance with operational limits and conditions, and detect and correct any abnormal condition that might affect reactor safety. The programme also helps to detect trends in ageing so that a plan for mitigating ageing effects can be prepared and implemented. Reactor service conditions are monitored through many parameters and conditions such as conductivity and pH of coolant water, water radiochemical analysis, thermal and hydraulic parameters, a leak detection system, corrosion rate of piping, vibration level of rotating equipment and control rod drop time.