BALTICA IV. Plant maintenance for managing life and performance

Energy Technology Data Exchange (ETDEWEB)

Hietanen, S.; Auerkari, P. [eds.] [VTT Manufacturing Technology, Espoo (Finland). Operational Reliability

1998-12-31

BALTICA IV International Conference on Plant Maintenance Managing Life and performance held on September 7-9, 1998 on board M/S Silja Symphony on its cruise between Helsinki-Stockholm and at Aavaranta in Kirkkonummi. The BALTICA IV conference provides a forum for the transfer of technology from applied research to practice. This is one of the two volumes of the proceedings of the BALTICA IV International Conference on Plant Maintenance Managing Life and Performance. The BALTICA IV conference focuses on new technology, recent experience and applications of condition and life management, and on improvements in maintenance strategies for safe and economical operation of power plants. (orig.)

Life Cycle Management Managing the Aging of Critical Nuclear Plant Components

International Nuclear Information System (INIS)

Meyer, Theodore A.; Elder, G. Gary; Llovet, Ricardo

2002-01-01

Life Cycle Management is a structured process to manage equipment aging and long-term equipment reliability for nuclear plant Systems, Structures and Components (SSCs). The process enables the identification of effective repair, replace, inspect, test and maintenance activities and the optimal timing of the activities to maximize the economic value to the nuclear plant. This paper will provide an overview of the process and some of the tools that can be used to implement the process for the SSCs deemed critical to plant safety and performance objectives. As nuclear plants strive to reduce costs, extend life and maximize revenue, the LCM process and the supporting tools summarized in this paper can enable development of a long term, cost efficient plan to manage the aging of the plant SSCs. (authors)

Integrated plant life management (PLiM)-the IAEA contribution

International Nuclear Information System (INIS)

Kang, K.-S.; Clark, C.R.; Omoto, A.; )

2005-01-01

For the past couple of decades there has been a change of emphasis in the world nuclear power from that of building new Nuclear Power Plants (NPP) to that of taking measures to optimize the life cycle of operational plants. National approaches in many countries showed an increase of interest in Plant Life Management (PLiM), both in terms of plant service life assurance and in optimizing the service or operational life of NPP. A strong convergence of views is emerging from different National approaches, particularly in the area of the economic aspects of NPP operation and in the evolution in the scope of NPP PLIM. The latter can directly affect the cost of electricity from NPP in an increasingly competitive environment. The safety considerations of a NPP are paramount and those requirements have to be met to obtain and to extend/renew the operating license. To achieve the goal of the long term safe, economic and reliable operation of the plant an integrated Plant Life Management Programme (PLiM) is necessary. Some countries already have advanced PLiM Programmes while others still have none. The PLiM objective is to identify all that factors and requirements for the overall plant life cycle. The optimization of these requirements would allow for the minimum period of the investment return and maximum of the revenue from the sell of the produced electricity. Recognizing the importance of this issue and in response to the requests of the Member States the IAEA Division of Nuclear Power implements the Sub-programme on 'Engineering and Management Support for Competitive Nuclear Power'. Four projects within this sub-programme deal with different aspects of the NPP life cycle management with the aim to increase the capabilities of interested Member States in implementing and maintenance of the competitive and sustainable nuclear power. Although all four projects contain certain issues of PLiM there is one specific project on guidance on engineering and management practices

Nuclear power plant life management. Proceedings of a symposium

International Nuclear Information System (INIS)

2003-01-01

Presently, an area of major interest of the IAEA is the management of the nuclear power plant (NPP) life cycle from concept development to decommissioning and disposal, with the primary objective of maximising the return on investment in nuclear facilities through efficient operation of NPPs. 441 NPPs, with a capacity of about 350GW(e) supplied 16% of global electricity in 2002. Of these, about 300 NPPs have been in operation for 15 years or more and these older units with partially or fully amortized capital costs have proven to be the most profitable. Moreover, there are no significant safety or economic reasons not to continue the operation of well managed NPPs over a longer period and consequently the issues of plant life management and license extension are receiving increasing emphasis in many countries. Forecasts of nuclear power growth over the next two decades range from 350GW(e) in the worst case to 500GW(e) in the best case. This will need additional personnel and expansion of the infrastructure in the developing countries, particularly as much of the new demand growth is forecast to take place outside the countries where most of the existing infrastructure resides. All aspects of NPP life cycle management are addressed by the IAEA and are briefly described in these proceedings. The IAEA Technical Working Group on Life Management of Nuclear Power Plants (TWG-LMNPP) recommended, during its regular meeting in February 1999, that the IAEA should consider holding a symposium on this subject area in 2002. This TWG-LMNPP Proposal was approved and, this symposium was held, attended by 138 participants from 32 Member States and 2 international organizations. The objectives of the symposium were as follows: Emphasise the role of NPP life management programmes in assuring a safe and reliable NPP operating cycle; Identify progress in methodological and technological developments for managing ageing processes and understanding ageing mechanisms; Provide a forum for

Plant life management of the ACR-1000 Concrete containment structure

International Nuclear Information System (INIS)

Abrishami, H.H.; Ricciuti, R.; Elgohary, M.

2009-01-01

The Ageing of reinforced concrete structures due to service conditions, aggressive environments, or accidents may cause their strength, serviceability and durability to decrease over time. For a new plant, a Plant Life Management (PLiM) program should start in the design process and then continues through the plant operation and decommissioning. Hence, PLiM must provide not only Ageing Management program (AMP) but also provide requirements on material characteristic and design criteria as well. The purpose of this paper is to present the Plant Life Management (PLiM) strategy for the concrete containment structure of the ACR-10001 (Advanced CANDU Reactor) designed by AECL. The ACR-1000 is designed for a 100-year plant life including 60-year operating life and an additional 40-year decommissioning period. The approach adopted for the PLiM strategy of the concrete containment structure is a preventive one, key areas being: 1) design methodology, 2) material performance and 3) ageing management program. During the design phase, in addition to strength and serviceability, durability, throughout the service life and decommissioning phase of the ACR-1000 structure, is a major consideration. Factors affecting durability design include: a) concrete performance, b) structural application, and c) consideration of environmental conditions. In addition to addressing the design methodology and material performance requirements, a systematic approach for the ageing management program for the concrete containment structure is presented. (authors)

Role of organizational leadership in plant life management

International Nuclear Information System (INIS)

Mohindra, R.K.; Chou, Q.B.

2007-01-01

The nuclear power plant (NPP) operational trend shows that the plants of the same design and brought to service about the same time demonstrate a wide range of life time operational performance. Based on years of performance assessment experience from various types of industry audits, it can be seen that there is a strong relationship between organizational leadership and the good performing plants. A review based on this relationship is provided to suggest important characteristics needed in management and leadership team for an organization to have a successful life management program in a NPP. The required characteristics and attributes are discussed in the following three important organizational elements: Environment, People and Process

CANDU plant life management - An integrated approach

International Nuclear Information System (INIS)

Charlebois, P.; Hart, R.S.; Hopkins, J.R.

1998-01-01

Commercial versions of CANDU reactors were put into service starting more than 25 years ago. The first unit of Ontario Hydro's Pickering A station was put into service in 1971, and Bruce A in 1977. Most CANDU reactors, however, are only now approaching their mid-life of 15 to 20 years of operation. In particular, the first series of CANDU 6 plants which entered service in the early 1980's were designed for a 30 year life and are now approaching mid life. The current CANDU 6 design is based on a 40 year life as a result of advancement in design and materials through research and development. In order to assure safe and economic operation of these reactors, a comprehensive CANDU Plant Life Management (PLIM) program is being developed from the knowledge gained during the operation of Ontario Hydro's Pickering, Bruce, and Darlington stations, worldwide information from CANDU 6 stations, CANDU research and development programs, and other national and international sources. This integration began its first phase in 1994, with the identification of most of the critical systems structures and components in these stations, and a preliminary assessment of degradation and mechanisms that could affect their fitness for service for their planned life. Most of these preliminary assessments are now complete, together with the production of the first iteration of Life Management Plans for several of the systems and components. The Generic CANDU 6 PLIM program is now reaching its maturity, with formal processes to systematically identify and evaluate the major CSSCs in the station, and a plan to ensure that the plant surveillance, operation, and maintenance programs monitor and control component degradation well within the original design specifications essential for the plant life attainment. A Technology Watch program is being established to ensure that degradation mechanisms which could impact on plant life are promptly investigated and mitigating programs established. The

Life management plants at nuclear power plants PWR; Planes de gestion de vida en centrales nucleares PWR

Energy Technology Data Exchange (ETDEWEB)

Esteban, G.

2014-10-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

Plant Life Management of the EC6 Concrete Containment Structure

Energy Technology Data Exchange (ETDEWEB)

Abrishami, Homayoun; Ricciuti, Rick; Khan, Azhar [CANDU Energy Inc., Mississauga (Canada)

2012-03-15

Aging of reinforced concrete structures due to service conditions, aggressive environments, or accidents may cause their strength, serviceability and durability to decrease over time. Due to the complex nature of safety-related structures in nuclear power plants in comparison to other structures, they possess a number of characteristics that make them comparison to other structures, they possess a number of characteristics that make them unique. These characteristics are: thick concrete cross-sections, heavy reinforcement, often one-side access only, subjected to such ageing stresses as irradiation and elevated temperature, in addition to other typical ageing mechanisms (i. e., exposure to freeze/thaw cycles, aggressive chemicals, etc.) that typically affects other types of non-nuclear structures. For a new plant, the Plant Life Management Program (PLiM) should start in the design process and then continues through construction, plant operation and decommissioning. Hence PLiM must provide not only Ageing Management program (AMP) but also provide requirements on material characteristic and the design criteria as well. The purpose of this paper is to present the Plant Life Management (PLiM) strategy for the concrete containment structure of EC6 (Enhanced CANDU 6) Nuclear Power Plant designed by CANDU Energy Inc. The EC6 is designed for 100-year plant life including a 60-year operating life and an additional 40-year decommissioning period of time. The approach adopted for the PLiM strategy of the concrete containment structure is a preventive one, key areas being: 1) design methodology, 2) material performance and 3) life cycle management and ageing management program. In addition to strength and serviceability, durability is a major consideration during the design phase, service life and up to the completion of decommissioning. Factors affecting durability design include: a) concrete performance, b) structural application, and c) consideration of environmental

Plant Life Management of the EC6 Concrete Containment Structure

International Nuclear Information System (INIS)

Abrishami, Homayoun; Ricciuti, Rick; Khan, Azhar

2012-01-01

Aging of reinforced concrete structures due to service conditions, aggressive environments, or accidents may cause their strength, serviceability and durability to decrease over time. Due to the complex nature of safety-related structures in nuclear power plants in comparison to other structures, they possess a number of characteristics that make them comparison to other structures, they possess a number of characteristics that make them unique. These characteristics are: thick concrete cross-sections, heavy reinforcement, often one-side access only, subjected to such ageing stresses as irradiation and elevated temperature, in addition to other typical ageing mechanisms (i. e., exposure to freeze/thaw cycles, aggressive chemicals, etc.) that typically affects other types of non-nuclear structures. For a new plant, the Plant Life Management Program (PLiM) should start in the design process and then continues through construction, plant operation and decommissioning. Hence PLiM must provide not only Ageing Management program (AMP) but also provide requirements on material characteristic and the design criteria as well. The purpose of this paper is to present the Plant Life Management (PLiM) strategy for the concrete containment structure of EC6 (Enhanced CANDU 6) Nuclear Power Plant designed by CANDU Energy Inc. The EC6 is designed for 100-year plant life including a 60-year operating life and an additional 40-year decommissioning period of time. The approach adopted for the PLiM strategy of the concrete containment structure is a preventive one, key areas being: 1) design methodology, 2) material performance and 3) life cycle management and ageing management program. In addition to strength and serviceability, durability is a major consideration during the design phase, service life and up to the completion of decommissioning. Factors affecting durability design include: a) concrete performance, b) structural application, and c) consideration of environmental

Framatome ANP worldwide experience in ageing and plant life management

International Nuclear Information System (INIS)

Daeuwel, W.; Kastner, B.; Nopper, H.

2004-01-01

The deregulation of the power generation industry has resulted in increased competitive pressure and is forcing operators to improve plant operating economy while maintaining high levels of plant safety. A key factor to meet this challenge is to apply a comprehensive plant life management (PLIM) approach which addresses all relevant ageing and degradation mechanisms regarding the safety concept, plant components and documentation, plant personnel, consumables, operations management system and administrative controls. For this reason, Framatome ANP has developed an integrated PLIM concept focussing on the safety concept, plant components and documentation. Representative examples for plant wide analyses are described in the following. The results of the analyses support the plant owner for taking the strategic decisions, involved in plant life extension (PLEX). (orig.)

FANP concept for plant life management and recent experience

International Nuclear Information System (INIS)

Nopper, H.; Daeuwel, W.; Waas, U.

2002-01-01

The deregulation of the power generation industry has resulted in increased competitive pressure and is forcing operators to improve plant operating economy while maintaining high levels of plant safety. A key factor to meet this challenge is to apply a comprehensive plant life management (PLIM) approach. The PLIM strategy addresses all relevant ageing and degradation mechanisms, the safety concept and the plant component documentation. In addition, it affects the management of plant personnel, consumables, operations management systems and administrative control procedures. Framatome ANP GmbH has developed an integrated PLIM concept and associated software tools applicable for both new and operating plants. The concept includes procedures and strategies regarding mechanical, electrical and I and C components as well as civil structures. The majority of e.g. mechanical components in a well-kept power plant will experience a technical service life, which is far above the intended design life. In most cases, only a small percentage of mechanical components is subject to significant degradation which may effect the integrity or the function of the component. The intention of an effective PLIM concept is to select safety and availability relevant components, were relevant degradation can not be ruled out. The PLIM concept utilizes a combination of strategies to identify components in a power plant: which are relevant to life management. An integrated safety review identifies components essential to safety, providing a classification of the associated safety levels. Assessment concerning the availability relevance of components is conduced. Components identified to be important to safety and availability are subject to a screening process for further grouping with respect to degradation potential. The selection process provides reasonable prioritisation of ageing relevant components and ensures that efforts are devoted to elements, where ageing is a relevant concern

Engineering support for plant life management: the IAEA contribution

International Nuclear Information System (INIS)

Kang, K.; Hezoucky, F.; Clark, R. C.; )

2007-01-01

For the past couple of decades there has been a change of emphasis in the world nuclear power from that of building new Nuclear Power Plants (NPP) to that of taking measures to optimize the life cycle of operational plants. National approaches in many countries showed an increase of interest in Plant Life Management (PLiM), both in terms of plant service life assurance and in optimizing the service or operational life of NPP. The safety considerations of a NPP are paramount and those requirements have to be met to obtain and to extend/renew the operating license. To achieve the goal of the long term safe, economic and reliable operation of the plant, PLiM programme is essential. Some countries already have advanced PLiM programmes while others still have none. The PLiM objective is to identify all that factors and requirements for the overall plant life cycle. The optimization of these requirements would allow for the minimum period of the investment return and maximum of the revenue from the sell of the produced electricity. Recognizing the importance of this issue and in response to the requests of the Member States the IAEA Division of Nuclear Power implements the Sub-programme on 'Engineering and Management Support for Competitive Nuclear Power'. Three projects within this sub-programme deal with different aspects of the NPP life cycle management with the aim to increase the capabilities of interested Member States in implementing and maintenance of the competitive and sustainable nuclear power. Although all three projects contain certain issues of PLiM, there is one specific project on guidance on engineering and management practices for optimization of NPP service life. This particular project deals with different specific issues of PLiM including aspects of ageing phenomena and their monitoring, issues of control and instrumentation, maintenance and operation issues, economic evaluation of PLiM including guidance on its earlier shut down and decommissioning

Aging management review for license renewal and plant life management

International Nuclear Information System (INIS)

Rinckel, M.A.; Young, G.G.

2002-01-01

license renewal for 25 nuclear units by 2005. It is anticipated that over 90% of the 103 operating nuclear plants in the United States will pursue license renewal and seek an additional 20 years of operation. Some plants may pursue operation to 80 years or longer since the license renewal rule does not limit the operating life of a nuclear power plant. The estimated cost to prepare and process a license renewal application is approximately $10M to $15M, which includes NRC review fees. The NRC review for license renewal is strictly a safety review and plant economics is not a consideration. However, economics will drive the decision to pursue license renewal for U.S. nuclear power plants. For nuclear units with strong performance records, license renewal is a good business decision when compared to the cost of building new generating capacity. The license renewal rule focuses on ageing of passive long-lived components and ageing management programs that manage those structures and components. Ninety to ninety-five percent of the ageing management programs credited in a plant license renewal application are existing programs (e.g., ASME Section XI, Chemistry Control Program, and Steam Generator Integrity). Typical examples of new programs required to manage ageing include reactor vessel internals, small bore Class 1 piping, Alloy 600, buried piping, and buried high voltage cable exposed to wetted environments. At present, there have been no commitments by any utility to replace components as a result of license renewal. After the NRC has approved a license renewal application, the credited ageing management programs (i.e., existing and new) become commitments for the remaining plant life. These commitments typically form the bases for a comprehensive plant life management program (PLIM). PLIM differs from license renewal in that it considers active and passive components as well as economics of plant operation and maintenance. Plants that have recently received renewed

Safe and effective nuclear power plant life cycle management towards decommissioning

International Nuclear Information System (INIS)

2002-08-01

The objective of this publication is to promote and communicate the need for a longer-term perspective among senior managers and policy or strategy makers for decisions that have the potential to affect the life cycle management of a nuclear power plant including decommissioning. The following sections provide practical guidance in the subject areas that might have the potential to have such an impact. The publication should be used as an aid to help strategic planning take place in an informed way through the proper consideration of any longer-term decisions to enforce recognition of the point that decommissioning is a part of the whole life cycle of a nuclear power plant. The guidance contained in this publication is relevant to all life cycle stages of a nuclear power plant, with particular emphasis on how these decisions have the potential to impact effective decommissioning. The intended users of this publication are: Strategic decision makers within a Utility through all the various life cycle stages; The senior representatives of the owners of a nuclear power plant. This publication is divided into two basic sections. Section 2 provides guidance on the topics considered generic inputs to plant life cycle management and Section 3 provides guidance on the topics that contribute to effective decommissioning

Plant life management in Belgium: an integrated project

International Nuclear Information System (INIS)

Wacquier, W.; Smet, M. de; Hennart, J.C.; Greer, J.L.; Breesch, Ch.; Havard, P.

2001-01-01

In Belgium, a specific plant life management project, named ''Continuous Operation of Belgian NPPs'' is currently developing. Its final objective is to centralize all safety and economic aspects of plant life management in order to determine, for each NPP unit, the optimal actions required to maintain their safe and reliable operation. As the lifetime of safety-related active components is permanently controlled by the current maintenance programs, the project focuses only on passive safety-related components and on non-safety components important for the availability of the plants. These structures and components were evaluated and compared on the basis of a set of weighted criteria in order to measure their criticality and to identify those which must be considered in the project. The selection and the ranking of those components is based on the KBM TM methodology (Knowledge Based Maintenance). This methodology facilitates the collection, formalization and exchange of know-how and gives immediate results thanks to a sequential and systematic step by step analysis. (author)

Comparison of Plant Life Management Approaches for Long Term Operations

International Nuclear Information System (INIS)

Kang, Kisig

2012-01-01

Plant life management can be defined as the integration of ageing and economic planning to maintain a high level of safety and optimize operations. Many Member States have given high priority to long term operation of nuclear power plants beyond the time frame originally anticipated (e. g. 30 or 40 years). Out of a total of 445 (369 GWe) operating nuclear power plants, 349 units (297 GWe) have been in operation for more than 20 years (as of November 2011). The need for engineering support to operation, maintenance, safety review and life management for long term operation as well as education and training in the field is increasingly evident. In addition the Fukushima accident has rendered all stake holders even more attentive to safety concerns and to the provision of beyond safety measures in the preparation and scrutiny of applications for operational design life extensions. In many countries, the safety performance of NPPs is periodically followed and characterized via the periodic safety review (PSR) approach. The regulatory The regulatory review and acceptance of the PSR gives the licensee the permission to operate the plant for up to the end of the next PSR cycle (usually 10 years). In the USA and other countries operating US designed plants, the license renewal application is based on the five pre-requisite requirements and ageing management programme for passive long life system structure and components(SSCs) and active systems is adequately addressed by the maintenance rule (MR) requirements and other established regulatory processes. Other Member States have adopted a combined approach that incorporates elements of both PSR and additional LRA specific requirements primarily focused on time limited ageing analysis. Taking into account this variety of approaches, the international atomic energy agency (IAEA) initiated work for collecting and sharing information among Member States about good practices on plant life management for long term operation in

COMSY - A Software Tool for Aging and Plant Life Management

International Nuclear Information System (INIS)

Zander, Andre; Nopper, Helmut

2012-01-01

A Plant-wide and systematic Aging and Plant Life Management is essential for the safe operation and/or availability of nuclear power plants. The Aging Management (AM) has the objective to monitor and control degradation effects for safety relevant Systems, Structures and Components (SSCs) which may compromise safety functions of the plant. The Plant Life Management (PLM) methodology also includes aging surveillance for availability relevant SSCs. AM and PLM cover mechanical components, electrical and I and C systems and civil structures All Aging and Plant Life Management rules call for a comprehensive approach, requiring the systematic collection of various aging and safety relevant data on a plant-wide basis. This data needs to be serviced and periodically evaluated. Due to the complexity of the process, this activity needs to be supported by a qualified software tool for the management of aging relevant data and associated documents (approx. 30 000 SSCs). In order to support the power plant operators AREVA NP has developed the software tool COMSY. The COMSY software with its integrated AM modules enables the design and setup of a knowledge-based power plant model compatible to the requirements of international and national rules (e.g. IAEA Safety Guide NS-G-2.12, KTA 1403). In this process, a key task is to identify and monitor degradation mechanisms. For this purpose the COMSY tool provides prognosis and trending functions, which are based on more than 30 years of experience in the evaluation of degradation effects and numerous experimental studies. Since 1998 COMSY has been applied successfully in more than fifty reactor units in this field. The current version 3.0 was revised completely and offers additional AM functions. All aging-relevant component data are compiled and allocated via an integrated power plant model. Owing to existing interfaces to other software solutions and flexible import functions, COMSY is highly compatible with already existing data

Considerations related to plant life management for Cernavoda-1

International Nuclear Information System (INIS)

Cojan, Mihail

2002-01-01

Cernavoda-1 NPP, the first CANDU 6 Unit in Eastern Europe, is one of the original five CANDU 6 plants and the first CANDU 6 producing over 700 MWe. CANDU Pressurized Heavy Water Reactors (PHWR) continues to play a significant role in electricity supply both in Canada and some offshore countries (Korea, Argentina, Romania). The commercial versions of CANDU reactors were put into service more than 30 years ago. While the first series of CANDU 6 plants (which entered service in the early 1980's) have now reached the middle portion of their 30 years design life, the Cernavoda-1 was put into service on 2 December 1996. However, the Cernavoda-1 Plant Life Management should be an increasingly important program to Utility ('CNE-Prod') in order to protect the investment and the continued success of plant operation. Over the past three years, INR (Institute for Nuclear Research - Romania) has been working with AECL-Canada on R and D Programs to support a comprehensive and integrated Cernavoda-1 Plant Life Management (PLiM) program that will see the Cernavoda-1 NPP successfully and reliably through to design life and beyond. The PLiM program has a focus on critical systems, structures, and components (CSSCs) and will be applied in three phases: Phase 1 - Planning (assessment and recommendations); Phase 2 - Life attainment implementation, and; Phase 3 - Plant Life Extension (PLEx), also known as plant extended operation. The key activities during each phase are shown. The schedule of each Phase are shown using the in service date of 1983 as the basis. This schedule applies to three original CANDU 6 plants with an in-service date of 1983: Point Lepreau, Gentilly-2, Wolsong-1 and shortly thereafter (1984) the 4th original CANDU 6 Embalse NPP was declared in service. Cernavoda-1 is the 5th original CANDU 6 plant and was put into service on 2 December 1996 (on site activities were started in 1980). The paper will describe the elements of an integrated program, the multiphase

Nuclear power plant life management in a changing business world

International Nuclear Information System (INIS)

2000-01-01

At the end of 1999, there were 348 nuclear power plants connected to the grid in OECD Member countries, representing a total capacity of 296 GWe and generating some 24% of their electricity. One third of these nuclear power plants had been in operation for over 20 years. The demand for electricity throughout OECD countries is increasing steadily but the construction of new nuclear power plants has become increasingly difficult. Many utilities would like to keep existing nuclear power plants operating for as long as they can continue to function safely and economically because. extending the lifetime of nuclear power plants is a substitute to constructing new plants. Therefore, nuclear plant life management (PLIM) has been carried out in many OECD Member countries and has played a very important role in the nuclear generation field. Nuclear power plant owners seek to economically optimise the output from their plants, taking into consideration internal and external influences, as well as equipment reliability and maintenance workload. Nuclear power plant life management and extension is generally an attractive option for utilities supplying electricity because of its low marginal cost and low investment risk. PLIM has become an important issue in the context of changing business circumstances caused by regulatory reform of the electricity market. Specifically, the economic aspect of PLIM has become an important focus in the competitive electricity market. The international workshop on 'Plant Life Management in a Changing Business World' was hosted by the United States Department of Energy (USDOE) in co-operation with the Electric Power Research Institute (EPRI) and the Nuclear Energy Institute (NEI) in Washington, DC, on 26-27 June 2000. Some 50 senior utility executives and policy makers from 12 Member countries, the International Energy Agency (IEA) and the European Commission (EC) attended the meeting. The objective of the workshop was to examine the status of

Framatome ANP GmbH concept of Plant Life Management (PLIM)

International Nuclear Information System (INIS)

Daeuwel, W.; Biemann, W.; Danisch, R.; Kastner, B.; Meyer, W.; Nopper, H.; Waas, U.; Warnken, L.

2002-01-01

The deregulation of the power generation industry has resulted in increased competitive pressure and is forcing operators to improve plant operating economy while maintaining high levels of plant safety. A key factor to meeting this challenge is to apply a comprehensive plant life management (PLIM) approach which addresses all relevant ageing and degradation mechanisms regarding the safety concept, plant component structures and documentation, plant personnel, consumables, operations management system and administrative controls. For this reason, Framatome ANP GmbH has developed an integrated PLIM concept applicable for both new and operating plants and focusing on the safety concept, plant component structures and documentation. (orig.)

Plant life management processes and practices for heavy water reactors

International Nuclear Information System (INIS)

Kang, K.-S.; Cleveland, J.; Clark, C.R.

2006-01-01

In general, heavy water reactor (HWR) nuclear power plant (NPP) owners would like to keep their NPPs in service as long as they can be operated safely and economically. Their decisions are depending on essentially business model. They involve the consideration of a number of factors, such as the material condition of the plant, comparison with current safety standards, the socio-political climate and asset management/ business planning considerations. Continued plant operation, including operation beyond design life, called 'long term operation, depends, among other things, on the material condition of the plant. This is influenced significantly by the effectiveness of ageing management. Key attributes of an effective plant life management program include a focus on important systems, structure and components (SSCs) which are susceptible to ageing degradation, a balance of proactive and reactive ageing management programmes, and a team approach that ensures the co-ordination of and communication between all relevant nuclear power plant and external programmes. Most HWR NPP owners/operators use a mix of maintenance, surveillance and inspection (MSI) programs as the primary means of managing ageing. Often these programs are experienced-based and/or time-based and may not be optimised for detecting and/or managing ageing effects. From time-to-time, operational history has shown that this practice can be too reactive, as it leads to dealing with ageing effects (degradation of SSCs) after they have been detected. In many cases premature and/or undetected ageing cannot be traced back to one specific reason or an explicit error. The root cause is often a lack of communication, documentation and/or co-ordination between design, commissioning, operation or maintenance organizations. This lack of effective communication and interfacing frequently arises because, with the exception of major SSCs, such as the fuel channels or steam generators, there is a lack of explicit

Aging and Plant Life Management with the Software Tool COMSY

International Nuclear Information System (INIS)

Nopper, Helmut; Rossner, Roland; Zander, Andre

2006-01-01

Within the scope of PLEX, a systematic and efficient ageing and plant life management system is becoming more and more important to ensure a safe and economical power plant operation in spite of continuous plant ageing. For the methodical implementation of PLIM and PLEX strategies, AREVA NP has developed the software tool COMSY. This knowledge-based program integrates degradation analysis tools with an inspection data management system. COMSY provides the capability to establish a program guided technical documentation by utilizing a virtual plant model which includes information regarding thermal hydraulic operation, water chemical conditions and materials applied for mechanical components. It provides the option to perform a plant-wide screening for identifying system areas, which are sensitive for degradation mechanisms typically experienced in nuclear power plants (FAC, corrosion fatigue, IGSCC, Pitting, etc.). If a system area is identified as being susceptible to degradation, a detailed analysis function enables the condition-oriented service life evaluation of vessels and piping systems in order to localize and conservatively quantify the effect of degradation. Based on these forecasts with COMSY, specific strategies can be developed to mitigate the effect of degradation and inspection activities can be focused on degradation sensitive areas. In addition, a risk-informed assessment tool serves to optimize inspection activities in respect to degradation potential and the associated damage consequence. After an in-service inspection is performed for a distinct location, the inspection data is to be evaluated according to generally accepted procedures. For this purpose an integrated inspection data management system module provides standardized, interactively operated evaluation functions. The key inspection results are transmitted as feedback in respect to the as-is condition of the component. Subsequently, all further life evaluations of the associated

Plant life management for long term operation of light water reactors. Principles and guidelines

International Nuclear Information System (INIS)

2006-01-01

The subject of this report was originally suggested by the IAEA Technical Working Group on Life Management of Nuclear Power Plants. It was then approved by the IAEA for work to begin in 2004. The participants in the group felt that it was time to address plant life management and ageing issues from the point of view of long term operation and licence renewal. It is believed that the nuclear power industry will only be able to survive if plant economics are favourable and safety is maintained. Therefore, the issue of ageing and obsolescence has to be addressed from an operational and safety standpoint, but also in the context of plant economics in terms of the cost of electricity production, including initial and recurring capital costs. Use of new technologies, such as advanced in-service inspection and condition based maintenance, should be considered, not only to predict the consequences of ageing and guard against them, but also to monitor equipment performance throughout the lifetime of the plant and to help establish replacement schedules for critical systems, structures and components, and to better estimate the optimum end of the operating licence, which means the end of the nuclear power plant's lifetime. The importance of nuclear power plant life management in facilitating the technical and economic goals of long term operation is presented in this report in terms of the requirement to ensure safe long term supplies of electricity in the most economically competitive way. Safe and reliable operation is discussed in terms of the overall economic benefits when plant life management is implemented. Preconditions for plant life management for long term operation are identified and approaches are reviewed. Plant life management should not be associated only with the extension of the operational lifetime of the nuclear power plant, but with an owner's attitude and a rational approach of the operating company towards running the business economically and safely

Report on countermeasure to plant life management of the nuclear power plants at three electric power companies

International Nuclear Information System (INIS)

1999-01-01

Three nuclear power reactors of the Fukushima-1 nuclear power plant, the Mihama-1 power plant and the Tsuruga-1 power plant were investigated according to the estimation plan shown in the Fundamental Concept on Plant Life Management of Agency of Natural Resources and Energy, Ministry of International Trade and Industry on April, 1996. Their reports contained the technical evaluation against, the responsive items to and the future examinations of the plant life management. In special, in the responsive items, some items to be added to the present maintenance process and some technical developmental problems are described in details and concretely. (G.K.)

Integration of plant life management in operation and maintenance

International Nuclear Information System (INIS)

Hutin, Jean-Pierre

2002-01-01

Full text: 1 - INTRODUCTION. Electricite de France is now operating 58 PWR nuclear power plants which produce 75% of french electricity. Besides maintaining safety and availability on a routine basis, it is outmost important to protect the investment. Indeed, such an asset is a tremendous advantage just as the company is going to face the new european electricity market. That is the reason why EDF is devoting important effort to implement ageing management as an integral part of operation and maintenance programs. But it must be recognized that NPP lifetime is not threatened only by component-related problems: other less technical issues must be seriously considered like industrial support, information system, skilled people, public acceptance, etc. 2 - LIFE MANAGEMENT POLICY. In France, there is no limited licensing period for NPPs. The life management policy of nuclear power plants is based on three principles: - safe and cost-effective operation, looking for excellence in daily activities, with an effective experience feedback organisation taking advantage of the high level of standardization of the units, - every ten years, a new set of safety standards, a complete review of each facility and an upgrading of its safety level through appropriate modifications while maintaining unit standardization in all the fleet, - a Life Management Program, at corporate level, which permanently scrutinizes operation and maintenance activities to identify decisions which could impair plant lifetime and which surveys research and development programs related to ageing phenomenon understanding. 3 - INTEGRATION OF LIFETIME CONCERN IN O and M ACTIVITIES. It is outmost important to take in account lifetime concern in daily operation and maintenance activities and this must be done as early as possible in plant life. Even though sophisticated assessments require engineering capacity, many good ideas may arise from plant staff. For that reason, increasing lifetime awareness of plant

South African Regulatory Framework for Nuclear Power Plant Life Management

International Nuclear Information System (INIS)

Mbebe, B.Z.

2012-01-01

The paper presents the regulatory approach to plant life management (PLiM) adopted by the National Nuclear Regulator (NNR) in South Africa, the licensing basis and regulatory requirements for Koeberg Nuclear Power Station (KNPS),operational programmes ensuring continued safe operation, issues related to the ageing of the plant, and the requirements for spent fuel as well as radioactive waste management. The paper will further present insights from the Periodic Safety Review (PSR) and Long Term Asset Management. (author)

Practical standard for nuclear power plant life management programs: 2007

International Nuclear Information System (INIS)

2006-03-01

The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

CANDU steam generator life management: laboratory data and plant experience

International Nuclear Information System (INIS)

Tapping, R.L.; Nickerson, J.H.; Subash, N.; Wright, M.D.

2001-10-01

As CANDU reactors enter middle age, and the potential value of the plants in a deregulated market is realized, life management and life extension issues become increasingly important. An accurate assessment of critical components, such as the CANDU 6 steam generators (SGs), is crucial for successful life extension, and in this context, material issues are a key factor. For example, service experience with Alloy 900 tubing indicates very low levels of degradation within CANDU SGs; the same is also noted worldwide. With little field data for extrapolation, life management and life extension decisions for the tube bundles rely heavily on laboratory data. Similarly, other components of the SGs, in particular the secondary side internals, have only limited inspection data upon which to base a condition assessment. However, in this case there are also relatively little laboratory data. Decisions on life management and life extension are further complicated--not only is inspection access often restricted, but repair or replacement options for internal components are, by definition, also limited. The application of CANDU SG life management and life extension requires a judicious blend of in-service data, laboratory research and development (R and D) and materials and engineering judgment. For instance, the available laboratory corrosion and fretting wear data for Alloy 800 SG tubing have been compared with plant experience (with all types of tubing), and with crevice chemistry simulations, in order to provide an appropriate inspection guide for a 50-year SG life. A similar approach has been taken with other SG components, where the emphasis has been on known degradation mechanisms worldwide. This paper provides an outline of the CANDU SG life management program, including the results to date, a summary of the supporting R and D program showing the integration with condition assessment and life management activities, and the approach taken to life extension for a typical

Ageing and plant life management software Comsy

Energy Technology Data Exchange (ETDEWEB)

Nopper, H.; Daeuwel, W.; Kastner, W. [Siemens Nuclear Power GmbH (SNP), Erlangen (Germany)

2001-07-01

Cost-effective power generation is becoming more important as the prices charged by power producers in the energy market continue to fall. To ease the cost situation there is a growing demand for innovative maintenance management methods which allow power plants to be economically operated over their entire lifetime. The purpose of a systematic ageing and plant life management program is to allow the lifetime of plant components to be planned, and to indicate when a component has reached the end of its effective lifetime before it fails. Another important function of such programs is to increase the availability of power plants as they age, and to enable implementation of a targeted maintenance strategy in terms of its economic and technical effect. Implementation of such programs requires the existence of detailed information concerning the status of the components as well as their operating conditions. Based on this information, an understanding of how the relevant ageing and degradation mechanisms work enables a prediction to be made concerning component lifetime. Advanced software programs provide such predictions at reasonable cost across all systems. (author)

Ageing and plant life management software Comsy

International Nuclear Information System (INIS)

Nopper, H.; Daeuwel, W.; Kastner, W.

2001-01-01

Cost-effective power generation is becoming more important as the prices charged by power producers in the energy market continue to fall. To ease the cost situation there is a growing demand for innovative maintenance management methods which allow power plants to be economically operated over their entire lifetime. The purpose of a systematic ageing and plant life management program is to allow the lifetime of plant components to be planned, and to indicate when a component has reached the end of its effective lifetime before it fails. Another important function of such programs is to increase the availability of power plants as they age, and to enable implementation of a targeted maintenance strategy in terms of its economic and technical effect. Implementation of such programs requires the existence of detailed information concerning the status of the components as well as their operating conditions. Based on this information, an understanding of how the relevant ageing and degradation mechanisms work enables a prediction to be made concerning component lifetime. Advanced software programs provide such predictions at reasonable cost across all systems. (author)

Plant life management for long term operation of nuclear power plants

International Nuclear Information System (INIS)

2005-01-01

The world's fleet of Nuclear Power Plants (NPPs) is approximately 20 years old on average, and most plants are believed to be able to operate for 60 years or more. The design life of a NPP is typically 30 to 40 years. This may be extended by 10 to 20 years, or more, provided that the plant can demonstrate by analysis, trending, equipment and system upgrades, increased vigilance, testing, ageing management, and other means that license renewal presents no threat to public health and safety. The basic goal of Plant Life Management (PLiM) is to satisfy requirements for safe long-term supplies of electricity in an economically competitive way. The basic goal of the operating company and the owners to operate as long as economically reasonable and possible from safety point of view. PLiM is a management tool for doing that. PLiM is a system of programmes and procedures to satisfy safety requirements for safe operation and for power production in a competitive way and for time which is rational from technical and economical point of view. PLiM is not only a technical system, it is also an attitude of the operational company to keep the plant in operation as long as possible from safety and business point of view. The common objectives of PLiM assessment is to help and review the pre-conditions for PLiM and long-term operation approaches. PLiM should not be associated with extension of operational life-time of the NPP only. It is an owner's attitude and rational approach of the operating company to run the business economically and safely. The effectiveness of PLiM Programme can be assessed by three complementary kinds of assessment: self-assessment, peer review and comprehensive programme review by the plant owner/ operator. IAEA will provide the assessment service for peer review of PLiM. Preparation for a PLiM Assessment service will be initiated only after the IAEA has been formally approached by a MS and funding (e.g. an existing Technical cooperation project) has

Plant life management study of Japanese nuclear power plants

International Nuclear Information System (INIS)

Fukuda, Toshihiko

1999-01-01

Already more than twenty-five years have passed since the first commercial LWR plant went into operation in Japan. In this situation, MITI and 3 electric utilities (Tokyo Electric Power Company, Kansai Electric Power Co., Inc, Japan Atomic Power Company) have started a plant life management (PLM) study from 1994 to evaluate the long-term integrity of major systems, structures and components of aged LWR plants and ensure the safe, steady and highly reliable long-term operation. It consists of two phases: part 1 study and part 2 study. The part 1 study started in 1994 and focused on seven typical safety-related components. The part 1 study reports were made public in 1996. The part 2 study started in 1997. In this study we reviewed not only safety-related components but also plant reliability related components. The part 2 study reports were opened to the public in February 1999. This paper shows a summary of the part 2 study and our future PLM program. (author)

Strategies and policies for nuclear power plant life management. Proceedings of the IAEA specialists meeting. Working document

International Nuclear Information System (INIS)

1998-01-01

The purpose of the Specialists Meeting organized by the IAEA was to provide an international forum for discussing of recent results in national and utility experience in development of nuclear power plant life management programmes and their technical, regulatory and economic assessments. Plant life management requires detailed knowledge of ageing degradation of the components and the results of mitigation technologies. The basic conclusion includes the need of Guide on NPP Life management which should encompass: plant safety; plant availability; plant operating life extension; human resources policy; research and development needs

An approach to nuclear-power-plant life management

International Nuclear Information System (INIS)

Vojvodic Tuma, J.; Celin, R.; Udovc, M.; Bundara, B.; Zabric, I.

2007-01-01

The plant life of a nuclear power plant (NPP) depends on degradation processes and ageing. Degradation is a deterioration phenomenon that can lead to component failure or limit the life of a component or the NPP itself. Ageing describes a continuous time or operational degradation of materials due to operational conditions, which include both normal and operating conditions. As a result of ageing degradation the state of the NPP or component can vary throughout the operating life. The degradation mechanisms for metallic components are general and local corrosion, erosion/corrosion, fatigue, corrosion fatigue, material changes due to irradiation and temperature, creep and wear. All the components of an NPP are subject to ageing, which may lead to the degradation of the physical barriers and redundant components, resulting in an increased probability of common-cause failures. The aims of NPP ageing management are to ensure that the necessary safety margins, adequate reliability and unforeseen and uncontrolled ageing of critical components do not shorten the NPP's lifetime. For the reasons stated above, plans are necessary to maintain the NPP in a state of high reliability. These are plans for an assessment of the life of the components that cannot be readily replaced, plans for operating life assessment or the planned replacement of major components where economic considerations will largely condition whether replacement or decommissioning should be pursued and plans for maintenance and replacements so that outages and delays can be minimised. In this paper some aspects of the process of NPP life management will be presented. (author)

Reactor pressure vessel life cycle management at the Calvert Cliffs Nuclear Power Plant

International Nuclear Information System (INIS)

Doroshuk, B.W.; Bowman, M.E.; Henry, S.A.; Pavinich, W.A.; Lapides, M.E.

1993-01-01

Life Cycle Management (LCM) seeks to manage the aging process of important systems, structures, and components during licensed operation. The goal of Baltimore Gas and Electric Company's (BG and E) Life Cycle Management Program is to assure attainment of 40 years of operation and to preserve the option of an additional 20 years of operation for the Calvert Cliffs Nuclear Power Plant (CCNPP). Since the reactor pressure vessel (RPV) has been identified as one of the most critical components with regard to long-term operation of a nuclear power plant, BG and E initiated actions to manage life limiting or aging issues for the CCNPP RPVs. To achieve long-term operation, technical RPV issues must be effectively managed. This paper describes methods BG and E uses for managing RPV age-related degradation. (author)

R and D in support of CANDU plant life management

International Nuclear Information System (INIS)

Tapping, R.L.; Holt, R.A.

1999-01-01

One of the keys to the long-term success of CANDUs is a high capacity factor over the station design life. Considerable R and D in underway at AECL to develop technologies for assessing, monitoring and mitigating the effect of plant ageing and for improving plant performance and extending plant life. To achieve longer service life and to realize high capacity factor from CANDU stations, AECL is developing new technologies to enhance fuel channel and steam generator inspection capabilities, to monitor system health, and to allow preventive maintenance and cleaning (e.g., on-line chemical cleaning processes that produce small volumes of wastes). The life management strategy for fuel channels and steam generators requires a program to inspect components on a routine basis to identify mechanisms that could potentially affect fitness-for-service. In the case of fuel channels, the strategy includes inspections for dimensional changes, flaw detection, and deuterium concentration. New techniques are been developed to enhance these inspection capabilities; examples include accurate measurement of the gap between a pressure tube and its calandria tube and rapid full-length inspections of steam generator tubes for all known flaw types. Central to life management of components are Fitness-for-Service Guidelines (FFSG) that have been developed with the CANDU Owners Group (COG) that provide a standardized method to assess the potential for propagation of flaws detected during in-service inspections, and assessment of any change in fracture characteristics of the material. FFSG continue to be improved with the development of new technologies such as the capability to credit relaxation of stresses due to creep and non-rejectable flaws in pressure tubes. Effective management of plant systems throughout their lifetime requires much more than data acquisition and display - it requires that system health is continually monitored and managed. AECL has developed a system Health Monitor

CANDU plant life management - An integrated approach

International Nuclear Information System (INIS)

Hopkins, J.R.

1998-01-01

An integrated approach to plant life management has been developed for CANDU reactors. Strategies, methods, and procedures have been developed for assessment of critical systems structures and components and for implementing a reliability centred maintenance program. A Technology Watch program is being implemented to eliminate 'surprises'. Specific work has been identified for 1998. AECL is working on the integrated program with CANDU owners and seeks participation from other CANDU owners

Considering plant life management influences on new plant design

International Nuclear Information System (INIS)

Dam, R.F.; Choy, E.; Soulard, M.; Nickerson, J.H.; Hopwood, J.

2003-01-01

After operating successfully for more than half their design life, owners of CANDU reactors are now engaging in Plant Life Management (PLiM) activities to ensure not only life attainment, but also life extension. For several years, Atomic Energy of Canada Ltd. (AECL) has been working with domestic and offshore CANDU utilities on a comprehensive and integrated CANDU PLiM program that will see existing CANDU plants successfully and reliably operate through their design life and beyond. To support the PLiM program development, a significant level of infrastructure has been, and continues to be, developed at AECL. This includes the development of databases that document relevant knowledge and background to allow for a more accessible and complete understanding of degradation issues and the strategies needed to deal with these issues. As the level of integration with various project, services and R and D activities in AECL increases, this infrastructure is growing to encompass a wider range of design, operations and maintenance details to support comprehensive and quantitative assessment of CANDU stations. With the maturation of the PLiM program, these processes were adapted for application to newer plants. In particular, a fully integrated program was developed that interrelates the design basis, operations, safety, and reliability and maintenance strategies, as applied to meet plant design goals. This has led to the development of the maintenance-based design concept. The various PLiM technologies, developed and applied in the above programs with operating stations, are being modified and tailored to assist with the new plant design processes to assure that ACR- Advanced CANDU Reactor meets its targets for operation, maintenance, and lifetime performance. Currently, the ACR, developed by Atomic Energy of Canada Ltd. (AECL), is being designed with features to increase capacity factors, to reduce the risk of major equipment failures, to improve access to key components

Life management of SG for WWER plants

International Nuclear Information System (INIS)

Trunov, N. B.; Dragunov, Yu. G.; Banyuk, G. F.

2004-01-01

Nowadays, 252 steam generators (SG) of horizontal type are in operation at WWER plants constructed by the Russian designs. In connection with end of the specified service life of the reactor plant equal to 30 years the activities are performed on service life extension of the main equipment including the SG. At some Units, throughout the design service life of SG there were problems resulting in necessity of SG replacement. At the same time the SGs at some Units are in successful operation above the design service life. This report deals with the peculiarities of operation of the horizontal SGs and the problems to be highlighted as the most important for service life extension. The main component to determine possibility for SG service life extension is the SG tubing. As the operating experience shows it is water chemistry of the secondary circuit that is the main factor influencing operability of the SG tubing. Therefore, differences in water chemistry organization leads to significant differences in operability of the SG tubing at various Units and in some cases within one Unit. Owing to the fact that the cases of water chemistry disturbance and the process of tubes fouling with the corrosion products of the main condensate system are not excluded, the damages continue to occur. Tube integrity shall be inspected by eddy current method using the various instrument complexes. This method has certain disadvantages but allows to estimate the degree and direction of degradation processes. The results of eddy current test (ECT) can be used to determine the plugging criterion for defective tubes. The significant number of defective tubes at some Units makes a choice of the plugging criterion to be an important problem, on which solution the SG safety, reliability and service life depends. The report deals with directions of activities in service life management for the SG at WWER plants. Main activities are improvement of water chemistry and non-destructive tests.(author)

Advanced maintenance strategies for power plant operators--introducing inter-plant life cycle management

International Nuclear Information System (INIS)

Graeber, Ulrich

2004-01-01

One of the most important goals of competing power plant operators is to ensure safe operation of their plants, characterized by maximum availability throughout the entire life cycle and minimized specific generating costs. One parameter crucial to the total price of electricity--and one that can be actively influenced by the power plant operators--is maintenance. Up to 30% of all electricity generating costs accrue from maintenance. In the past years maintenance measures have been optimized particularly by the application and continuing development of testing and diagnostic techniques, by the increased level of system and component automation as well as more efficient organization structures. Despite the considerable success of these efforts, the potential for further cost reductions is still far from exhausted. But the risks connected to reliability, availability and safety need to be analyzed in greater detail in order to ensure the sustainability of the savings already achieved as well as those yet to be realized. The systematic application of condition-based maintenance and the implementation of structured life cycle management are essential requirements. An inter-plant approach is recommended to make a quick implementation of maintenance optimization potentials possible. Plant-specific improvement potentials can be established with the help of a best-practice comparison, and measures and priorities can be defined for realizing them. Creating an inter-plant database will allow experience and findings to be analyzed quickly and efficiently by experts and made available to all participants on a neutral platform. Despite--or maybe owing to--the increasingly competitive marketplace, a sustained reduction in the maintenance costs of power plant operators can only be achieved through a structured, inter-plant exchange of experience. The ZES offers the industry a suitable platform for cooperation with its 'Condition-Based Maintenance' research focus. The introduction

International symposium on nuclear power plant life management. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

A number of nuclear power plants in operation are meeting the problems of aging. Besides maintaining safety and reliability many NPP owners are concerned with service life extension, life management policy, and reactor maintenance procedures. The topics covered in this report are devoted to: NPP life management, economics and technical aspects of service life extension, reactor licensing procedures; aging of reactor components; physical radiation effects on reactor materials; corrosion; mechanical properties of reactor materials; reactor control systems; reactor safety systems.

International symposium on nuclear power plant life management. Book of extended synopses

International Nuclear Information System (INIS)

2002-01-01

A number of nuclear power plants in operation are meeting the problems of aging. Besides maintaining safety and reliability many NPP owners are concerned with service life extension, life management policy, and reactor maintenance procedures. The topics covered in this report are devoted to: NPP life management, economics and technical aspects of service life extension, reactor licensing procedures; aging of reactor components; physical radiation effects on reactor materials; corrosion; mechanical properties of reactor materials; reactor control systems; reactor safety systems

Current activities in support of CANDU plant life management: an industry perspective

International Nuclear Information System (INIS)

Shalaby, B.A.; Price, E.G.; Hopkins, J.; Charlebois, P.

1998-01-01

The current focus of the CANDU industry is to position the nuclear option as a cost competitive, safe and reliable means of electricity production. To achieve its goal the CANDU industry as a whole is undertaking steps to improve further its performance and safety of its nuclear power plants. A number of programs have been planned and implemented particularly for plants in the mid-life range. Some of these programs include life assessment studies of critical systems, Structures and Components (SSCS), refurbishment and upgrading programs and monitoring and periodic inspection programs. Some elements of the programs have been in place from station start up and some are being instituted as part of the aging management and performance improvement program. The industry recognizes that the key to sustaining high performance over the life of the plant is the implementation of an integrated aging management program that encompasses all elements of plant operation and maintenance. A systematically implemented program on optimized maintenance and inspection strategy, standardized work processes, component rehabilitation programs, and applying lessons learned are some of the elements of a sustainable high performance and an effective plant life assurance program. The paper will describe the elements of an integrated program, the multiphase approach defined for CANDU PLIM and some of the activities undertaken by the industry to further improve and sustain plant safety, reliability and performance. (author)

Overview of plant life management for long term operation in nuclear power plants

International Nuclear Information System (INIS)

Kang, K.S.; Vincze, P.; Bychkov, A.

2014-01-01

Many IAEA member states have given high priority to licensing their nuclear power plants to operate for terms longer than the time frame originally anticipated (generally 40 years). The task of managing plant ageing is assigned in most member states to an engineering specialty called 'plant life management' (PLiM) applying a systematic analysis methodology to System Structure Components (SSCs) ageing. In many countries, the safety performance of nuclear power plants is periodically assessed and characterized via the periodic safety review (PSR) process. Regulatory review and acceptance of PSRs constitutes for these countries the licensing requirement for continued operation of the plant to the following PSR cycle (usually 10 years). In the USA and in other countries operating US designed plants, instead of PSR process, a license renewal application (LRA) process is followed, which requires certain prerequisites such as ageing management programs, particularly for passive irreplaceable SSCs. Active components are normally addressed via the maintenance rule (MR) requirements and other established regulatory processes. A third group of member states have adopted a combined approach that incorporates elements of both the PSR process and selected LRA specific requirements, such as time limited ageing analysis. The article ends with some IAEA recommendations for the implementation of national PLiM programs

Overview of German R and D activities relevant to life management of nuclear power plants

International Nuclear Information System (INIS)

Gillot, R.

1998-01-01

Life management issues of German NPPs include measures for qualifying continuous operation of NPPs and research activities related to materials behaviour under operating conditions. Plant management for life extension demand use of on-line monitoring systems for load (mechanical and thermal); vibration; leakage; water chemistry; neutron irradiation as well as replacement of systems, structures and components. The main goals to be achieved under international cooperation are increased safety, increased plant availability, extension of operating lifetime and improvement of plant economics

Plant life management and maintenance technologies for nuclear power plants

International Nuclear Information System (INIS)

Ikegami, Tsukasa; Aoki, Masataka; Shimura, Takao; Kaimori, Kimihiro; Koike, Masahiro

2001-01-01

Nuclear power generation occupying an important position for energy source in Japan and supplying about one third of total electric power usage is now required for further upgrading of its economics under regulation relaxation of electric power business. And, under execution retardation of its new planning plant, it becomes important to operate the already established plants for longer term and to secure their stability. Therefore, technical development in response to the plant life elongation is promoted under cooperation of the Ministry of Economics and Industries, electric power companies, literate, and plant manufacturers. Under such conditions, the Hitachi, Ltd. has progressed some technical developments on check inspection, repairs and maintenance for succession of the already established nuclear power plants for longer term under securing of their safety and reliability. And in future, by proposing the check inspection and maintenance program combined with these technologies, it is planned to exert promotion of maintenance program with minimum total cost from a viewpoint of its plant life. Here were described on technologies exerted in the Hitachi, Ltd. such as construction of plant maintenance program in response to plant life elongation agreeing with actual condition of each plant, yearly change mechanism grasping, life evaluation on instruments and materials necessary for maintenance, adequate check inspection, repairs and exchange, and so forth. (G.K.)

Current status of technology for plant life management

International Nuclear Information System (INIS)

Roche, B.

2000-01-01

In most developed countries of the world, deregulation of electricity markets has been established: competition is fierce, and utilities have to improve the competitiveness of their plants. It is an important challenge for nuclear power plants: a smart way to deal with this problem is life extension of existing units. The financial stakes associated with maintaining or extending the lifetime of nuclear power stations are very high; thus, if their lifetime is shortened by about ten years, dismantling and renewal would be brought forward which would increase their costs by several tens of billions of French francs. Furthermore, every extra year of operation of a 900 MWe unit should save about 500 million French francs per year on financial charges that would be necessary for a new investment, provided that maintenance costs do not become excessive. In order to succeed, utilities must improve their knowledge of ageing mechanisms, demonstrate to safety authorities the feasibility of life extension (especially taking into account critical components), operate existing units in an exemplary way, manage and master the long-term evolution of the safety reference state. (author)

Residual life management. Maintenance improvement

International Nuclear Information System (INIS)

Sainero Garcia, J.; Hevia Ruperez, F.

1995-01-01

The terms Residual Life Management, Life Cycle Management and Long-Term Management are synonymous with a concept which aims to establish efficient maintenance for the profitable and safe operation of a power plant for as long as possible. A Residual Life Management programme comprises a number of stages, of which Maintenance Evaluation focuses on how power plant maintenance practices allow the mitigation and control of component ageing. with this objective in mind, a methodology has been developed for the analysis of potential degradative phenomena acting on critical components in terms of normal power plant maintenance practices. This methodology applied to maintenance evaluation enables the setting out of a maintenance programme based on the Life Management concept, and the programme's subsequent up-dating to allow for new techniques and methods. Initial applications have shown that although, in general terms, power plant maintenance is efficient, the way in which Residual Life Management is approached requires changes in maintenance practices. These changes range from modifications to existing inspection and surveillance methods or the establishment of new ones, to the monitoring of trends or the performance of additional studies, the purpose of which is to provide an accurate evaluation of the condition of the installations and the possibility of life extension. (Author)

Regulatory issues for nuclear power plant life management

International Nuclear Information System (INIS)

Roe, J.

2000-01-01

The workshop of 26-27 june 2000, on nuclear power Plant LIfe Management (PLIM), also included working groups in which major issues facing PLIM activities for nuclear power plants were identified and discussed. The second group was on Regulation. The Regulatory Working Group will attempt to identify some of the more pertinent issues affecting nuclear plant regulation in a changing PLIM environment, to identify some possible actions to be taken to address these issues, and to identify some of the parties responsible for taking these actions. Some preliminary regulatory issues are noted below. This is not intended to be a comprehensive list of such issues but rather is intended to stimulate discussion among the experts attending this Workshop. One of the concerns in the regulatory arena is how the structural integrity of the plants can be assured for an extended lifetime. Technological advances directed toward the following are likely to be important factors in the regulatory process of life extension. - Preventive and corrective maintenance (e.g., water chemistry control, pressure vessel annealing, and replacement of core internals). - Ageing and degradation mechanisms and evaluation (e.g., embrittlement, wear, corrosion/erosion, fatigue, and stress corrosion). - Monitoring, surveillance, and inspection (e.g., fatigue monitoring and non-destructive testing). - Optimisation of maintenance (e.g., using risk-based analysis). On the business side, there is concern about technical support by manufacturers, fuel companies, and construction companies. Maintaining a strong technical base and skilled workers in a potentially declining environment is another concern in the regulatory community. Waste management and decommissioning remain significant issue regarding PLIM. These issues affect all three areas of concern - technology, business, and regulation. It is against this background, that the issues put forth in this paper are presented. The objective of presenting these

Aging management and life assessment of buried commodities in nuclear power plants

International Nuclear Information System (INIS)

Park, J. H.; Jung, I. S.; Jo, H. S.; Kim, M. G.; Kim, S. T.; Lee, S. S.

2000-01-01

General field survey, inspection and life assessment were performed to establish effective aging management program of buried commodities in nuclear power plant. Basic informations on material characteristics, aging degradation experiences and maintenance history were gathered. Considering their degradation effects on power operation or safety, buried commodities were screened for the aging management priority. Various inspection techniques were applied in field survey and inspection, and their results were incorporated in the life assessment of buried commodities. In the aspect of aging degradation, general status of buried commodities were considered still sound while some revealed local degradation

Maintenance for life management

International Nuclear Information System (INIS)

Hevia, F.

1997-01-01

Life Management is based on the detection, monitoring and control of long-term degradation that affects individual plant components and important populations. Experience has shown that in many cases current maintenance practices do not attend to ageing directly; instead they deal with the consequences when it is already too late, when good Life Management is no longer practical. This has brought about the need for specific Maintenance Evaluation and Improvement Programmes to adjust to the basic objective of Life Management which is to project against, monitor and mitigate ageing that can affect the safe and profitable operating life of the facility. New regulatory requirements for ageing monitoring and effective maintenance to ensure safety (Maintenance Rule) have made it even more necessary to implement the Maintenance Evaluation Programme to cope with ageing, and to integrate that tasks in both programmes to optimise effort and use of tools. This paper presents a brief description of the objectives and methodologies of these Programmes which has been applied to plants around the world and in Spain at the Garona and Vandellos II plants in Spain as part of the PIE project for developing a Remanent Life Evaluation System for nuclear power plants. (Author)

Plant life management and modernisation: Research challenges in the EU

International Nuclear Information System (INIS)

Rintamaa, R.; Aho-Mantila, I.

2011-01-01

The European network of excellence NULIFE (nuclear plant life prediction) has been launched with a clear focus on integrating safety-oriented research on materials, structures and systems and exploiting the results of this integration through the production of harmonised lifetime assessment methods. NULIFE will help provide a better common understanding of the factors affecting the lifetime of nuclear power plants which, together with associated management methods, will help facilitate safe and economic long-term operation of existing nuclear power plants. In addition, NULIFE will help in the development of design criteria for future generations of nuclear power plant. NULIFE was kicked-off in October 2006 and will work over a 5-year period to create a single organization structure, capable of providing harmonised research and development (R and D) at European level to the nuclear power industry and the related safety authorities. Led by VTT (Technical Research Centre of Finland), the project has a total budget in excess of 8 million euros, with over 40 partners drawn from leading research institutions, technical support organizations, electric power utilities and manufacturers throughout Europe. NULIFE also involves many industrial organizations and, in addition to their R and D contributions, these take part in a dedicated End User Group. Over the last 15 years the European Commission has sponsored a significant number of R and D projects under the Euratom Framework Programme and its Joint Research Centre has developed co-operative European Networks for mutual benefits on specific topics related to plant life management. However, their overall impact has been reduced due to fragmentation. These networks are considered forerunners to NULIFE. The importance of the long-term operation of the plants has been recognized at European level, in the strategic research agenda of SNETP (Sustainable Nuclear Energy Technology Platform). In NULIFE, the joint EU

Risk-based management of remaining life of power plant components

International Nuclear Information System (INIS)

Roos, E.; Jovanovic, A.S.; Maile, K.; Auerkari, P.

1999-01-01

The paper describes application of different modules of the MPA-System ALIAS in risk-based management of remaining life of power plant components. The system allows comprehensive coverage of all aspects of the remaining life management, including also the risk analysis and risk management. In addition, thanks to the modular character of the system it is also possible to implement new methods: In the case described here, a new (probabilistic) method for determination of the next inspection time for the components exposed to creep loading has been developed and implemented in the system. Practical application of the method has shown (a) that the mean values obtained by the method fall into the range of results obtained by other methods (based on expert knowledge), and (b) that it is possible to quantify the probability of aberration from the mean values. This in turn allows quantifying the additional risks linked to e.g. prolonging of inspection intervals. (orig.) [de

Long-term capital planning considering nuclear plant life-cycle management

International Nuclear Information System (INIS)

Negin, C.A.; Simpson, J.M.; Hostetler, D.R.

1992-09-01

The creation of a Life Cycle Management (LCM) group at utilities to evaluate the long term capital refurbishment needs is gaining favor. Among the functions of such groups can be the responsibility for recommending long term capital planning projects based on results of evaluations of systems, structures, and components that are not only essential to achieving the full current license term of operation, but also to extend the service life of the plant. Making such recommendations, in content and timing, requires the ability to view all recommendations in the context of an overall capital budget and long range outage impacts. This report illustrates an approach for creating a Long-Term Capital Plan with methods for deciding on, compiling, integrating, and presenting projects from the perspective of an LCM program for a nuclear power plant. It also addresses a rationale for capitalization of LCM program activities that would not be allowed under current accounting treatment

Nuclear power plant life management. An overview of identification of key components in relation with degradation mechanism - IAEA guidelines presentation

International Nuclear Information System (INIS)

Bezdikian, Georges

2005-01-01

Nuclear Power Plant (NPP) lifetime has a direct bearing on the cost of the electricity generated from it. The annual unit cost of electricity is dependent upon the operational time, and also annual costs and the capital cost assumptions function of Euros/kw. If the actual NPP lifetime has been underestimated then an economic penalty could be incurred. But the ageing degradation, of nuclear power plants is an important aspect that requires to be addressed to ensure: - that necessary safety margins are maintained throughout service life; - the adequate reliability and therefore the economic viability of older plants is maintained; - that unforeseen an uncontrolled degradation of critical plant components does not foreshorten the plant lifetime. Accommodating the inevitable obsolescence of some components has also to be addressed during plant life. Plant lifetime management requires the identification and life assessment of those components which not only limit the lifetime of the plant but also those which cannot be reasonably replaced. The planned replacement of major or 'key' components needs to be considered - where economic considerations will largely dictate replacement or the alternative strategy of power plant decommissioning. The necessary but timely planning for maintenance and replacements is a necessary consideration so that functions and reliability are maintained. The reasons for the current increasing attention in the area of plant life management are diverse and range from the fact that many of the older plants are approaching for the oldest plants more than 30 years in operation, and for important number of NPPs between 20 and 30 years. The impact of plant life management on the economics of generating electricity is the subject of ongoing studies and it can readily be seen that there can be both savings and additional costs associated with these activities. Not all degradation processes will be of significance in eroding safety margins and there is a

Overview of life cycle management - LCM (plant life management - PLiM)

International Nuclear Information System (INIS)

Nickerson, J.

2006-01-01

This paper discusses life cycle management which involves a structured and comprehensive aging management program to ensure that significant aging effects are detected as early as possible and engineering, operations and maintenance actions are undertaken to control aging degradation and wear out of components

Use of plant specific information in life management

International Nuclear Information System (INIS)

Simola, K.; Talja, H.

2002-01-01

In plant life management decisions are made on prevention and mitigation measures of ageing phenomena. In these processes, information from several sources has to be combined, and the decisions are based on data and analyses including lots of uncertainties. In order to make good decisions, the uncertainties and limitations related to both analyses and the raw data should be recognised. A schematic presentation of the information used in the decision making with an emphasis on data needs and analyses for the technical life assessment of a component is given. On the way from the raw data to the final decision on ageing management there are several steps where engineering judgement is used or more sophisticated analyses are made. In this paper we present a view upon the decision making process in managing the ageing of components, systems and structures. Further, we propose practices to improve the transparency of ageing analyses and means to improve the availability and usability of plant specific information for ageing management purposes. The availability of plant specific information and easy access to these records are vital for the efficient ageing management. Often, the data collection and record keeping has not been organised in an efficient way and the use of experience data is very laborious. As illustrated, a lot of plant specific information is needed in ageing assessment. It is also very important to ensure that the information is up-to-date, e.g. possible modifications are taken into account in lifetime predictions. As an example of improvement in the data collection practices we shortly summarise the pipeline analysis and monitoring system that VTT is developing together with TVO. The system is meant to contain all up-to-date information necessary to analyse and monitor piping systems of an operating plant. The core of the system contains five databases. Piping database contains information like geometry, material, loading, detected cracks etc. All

NNP Life Management Programmes

International Nuclear Information System (INIS)

Hervia Ruperez, F.

1996-01-01

Around the world, power station owners are increasingly concerned to optimise Plant Life Management. In response, they are setting up Life Management programmes, of more or less ambitious scope and depth. Strategic, economic and security concerns and the close link between life extension work and the improved maintenance practices that are so important today, will increase and global these programmes for monitoring and conservation or mitigation of ageing. These programmes are all based on knowledge of the precise condition of all components and population with the greatest effect on the economics and safety of the plant, and trends in changes in their condition. (Author)

Nuclear power plant life management processes: Guidelines and practices for heavy water reactors. Report prepared within the framework of the Technical Working Groups on Advanced Technologies for Heavy Water Reactors and on Life Management of Nuclear Power Plants

International Nuclear Information System (INIS)

2006-06-01

The time is right to address nuclear power plant life management and ageing management issues in terms of processes and refurbishments for long term operation and license renewal aspects of heavy water reactors (HWRs) because some HWRs are close to the design life. In general, HWR nuclear power plant (NPP) owners would like to keep their NPPs in service as long as they can be operated safely and economically. This involves the consideration of a number of factors, such as the material condition of the plant, comparison with current safety standards, the socio-political climate and asset management/ business planning considerations. This TECDOC deals with organizational and managerial means to implement effective plan life management (PLiM) into existing plant in operating HWR NPPs. This TECDOC discusses the current trend of PLiM observed in NPPs to date and an overview of PLiM programmes and considerations. This includes key objectives of such programs, regulatory considerations, an overall integrated approach, organizational and technology infrastructure considerations, importance of effective plant data management and finally, human issues related to ageing and finally integration of PLiM with economic planning. Also general approach to HWR PLiM, including the key PLiM processes, life assessment for critical structures and components, conditions assessment of structures and components and obsolescence is mentioned. Technical aspects are described on component specific technology considerations for condition assessment, example of a proactive ageing management programme, and Ontario power generation experiences in appendices. Also country reports from Argentina, Canada, India, the Republic of Korea and Romania are attached in the annex to share practices and experiences to PLiM programme. This TECDOC is primarily addressed to both the management (decision makers) and technical staff (engineers and scientists) of NPP owners/operators and technical support

Application of plant life management program and experience at NRU

International Nuclear Information System (INIS)

Nickerson, J.; Dam, R.; Arnold, J.; See Hoye, D.

2004-01-01

The National Research Universal (NRU) reactor has seen extensive and excellent service since going into operation in 1957. During that time, significant investments in upgrading and improving the facility have been implemented. Recently, as part of the NRU Licenseability Extension (LE) program, AECL has developed a Plant Life Management (PLiM) program to support planned operation to at least 2012. The objective of the PLiM program is to systematically assess the various aging related degradation mechanisms in order to evaluate both current condition and the potential for further extending service life. Another objective is to identify the associated maintenance, surveillance and inspection strategy for service life extension of important Structures, Systems, and Components (SSCs). The strategy uses approaches that build on AECL's PLiM/PLEx experience at CANDU plants, but also utilizes previous Age Management and refurbishment work performed at NRU. The program is multi-faceted, systematic and integrated, and involves the facility operations organization in the assessment process. The PLiM program has used a number of pilot studies in the initial stages to test out PLiM procedures, gain experience with the various aging assessment techniques and enhance effectiveness of interfaces between the aging assessment team and the facility staff. The aging assessment process begins with the screening and prioritization of the facility SSCs. Selection of the appropriate assessment technique is based on priority and component type. Life and condition assessment techniques used at other plants have been adapted to NRU and performed on important components and structures. For important systems, a combination of condition assessment and systematic maintenance assessment techniques are being used. Detailed PLiM procedures have been developed and are in trial use in pilot studies. These procedures are currently being updated with the experience gained during the pilot studies. In

Development of Information Management System for Plant Life Cycle Management

International Nuclear Information System (INIS)

Byon, SuJin; Lee, SangHyun; Kim, WooJoong

2015-01-01

The study subjects are S. Korean NPP(Nuclear Power Plant) construction projects. Design, construction, operations companies have different nuclear power plant construction project structures, and each company has its own Information Management System. In this study, the end user developed an Information Management System early in the project, and developed a management structure that systematically integrates and interfaces with information in each lifecycle phase. The main perspective of Information Management is moving from the existent document-centric management to the data-centric management. To do so, we intend to integrate information with interfaces among systems. Integrated information management structure and management system are essential for an effective management of the lifecycle information of nuclear power plants that have a lifespan over as much as 80 years. The concept of integration management adopted by the defence, ocean industries or various PLM solution providers is important. Although the NPP project has application systems in each key lifecycle phase, it is more effective to develop and use PLIMS in consideration of the interface and compatibility of information among systems. As an initial study for development of that integrated information management structure, this study is building the system and has interfaced it with a design-stage system

Development of Information Management System for Plant Life Cycle Management

Energy Technology Data Exchange (ETDEWEB)

Byon, SuJin; Lee, SangHyun; Kim, WooJoong [KOREA HYDRO and NUCLEAR POWER CO. LTD, Daejeon (Korea, Republic of)

2015-10-15

The study subjects are S. Korean NPP(Nuclear Power Plant) construction projects. Design, construction, operations companies have different nuclear power plant construction project structures, and each company has its own Information Management System. In this study, the end user developed an Information Management System early in the project, and developed a management structure that systematically integrates and interfaces with information in each lifecycle phase. The main perspective of Information Management is moving from the existent document-centric management to the data-centric management. To do so, we intend to integrate information with interfaces among systems. Integrated information management structure and management system are essential for an effective management of the lifecycle information of nuclear power plants that have a lifespan over as much as 80 years. The concept of integration management adopted by the defence, ocean industries or various PLM solution providers is important. Although the NPP project has application systems in each key lifecycle phase, it is more effective to develop and use PLIMS in consideration of the interface and compatibility of information among systems. As an initial study for development of that integrated information management structure, this study is building the system and has interfaced it with a design-stage system.

Life management of power plant based on structural damage testing

Energy Technology Data Exchange (ETDEWEB)

Tallermo, H; Klevtsov, I [Thermal Engineering Department of Tallinn Technical University, Tallinn (Estonia); Arras, V [Eesti Energia, Tallinn (Estonia)

1999-12-31

Life management system is based on the valid nowadays in Estonian power plants regulation documentation. The system allows to estimate stress distribution in components, find computational assessment of cumulated creep damage, determine when and where it is necessary to cut off the particular number of microsamples or take replicas. Finally, the real metal condition may be assessed on the basis of metallographic specimen research and reasonable 3-R decision - run, repair, replacement - made on further component use. (orig.) 6 refs.

Life management of power plant based on structural damage testing

Energy Technology Data Exchange (ETDEWEB)

Tallermo, H.; Klevtsov, I. [Thermal Engineering Department of Tallinn Technical University, Tallinn (Estonia); Arras, V. [Eesti Energia, Tallinn (Estonia)

1998-12-31

Life management system is based on the valid nowadays in Estonian power plants regulation documentation. The system allows to estimate stress distribution in components, find computational assessment of cumulated creep damage, determine when and where it is necessary to cut off the particular number of microsamples or take replicas. Finally, the real metal condition may be assessed on the basis of metallographic specimen research and reasonable 3-R decision - run, repair, replacement - made on further component use. (orig.) 6 refs.

An overview of actions concerning life management of nuclear power plants in Argentina

International Nuclear Information System (INIS)

Pochettino, A.A.

1995-01-01

An overview of actions concerning life management of nuclear power plants in Argentina is presented including the following issues: reorganization of nuclear activities in Argentina; life extension actions; main specific research and development actions (reactor pressure vessel integrity assessment project; reactor internal components project; heat exchanges project); other research and development actions (non-destructive testing developments; eddy current techniques; acoustic emission applications; materials; vibrations and fretting wear; reactor chemistry; control and instrumentation; probabilistic safety assessment)

3. International Conference on Nuclear Power Plant Life Management (PLiM) for Long Term Operations (LTO). Keynotes, papers, presentations, posters

International Nuclear Information System (INIS)

2012-01-01

The world's fleet of nuclear power plants is, on average, more than 20 years old. Even though the design life of a nuclear power plant is typically 30-40 years, many plants will operate in excess of their design lives, provided that nuclear power plant engineers demonstrate by analysis, equipment and system upgrades, increased vigilance, testing and ageing management that the plant will operate safely. In the operation of nuclear power plants, safety should always be the prime consideration. Plant operators and regulators must always ensure that plant safety is maintained and, where possible, enhanced during its operating lifetime. Nuclear power plant life management (PLiM) has gained increased attention over the past decade, and effective ageing management of systems, structures and components (SSCs) is a key element in PLiM for the safe and reliable long term operation of nuclear power plants. A PLiM programme is an effective tool that allows an operator to safely and cost effectively manage ageing effects in SSCs for long term operation (LTO). A PLiM programme helps facilitate decisions concerning when and how to repair, replace or modify SSCs in an economically optimized way, while assuring that a high level of safety is maintained. The option for extended nuclear power plant operation has been recognized by operators and regulators alike, as evidenced in the number of licence renewal programmes that are being developed by Member States. After the severe accident at the Fukushima Daiichi nuclear power plant, the safe operation of nuclear power plants has become even more important; not only in terms of technical or ageing issues, but also in terms of management system and qualified workforce related issues. Application of an integrated management system and structured workforce planning are needed throughout the plant life in order to ensure effective plant organization and management. The IAEA organized the first and second International Conference on Nuclear

Nuclear power plant life time improvement and management program in Korea

International Nuclear Information System (INIS)

Sung Yull Hong; Ill Seok Jeong; Taek Ho Song

1995-01-01

Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has performed a lifetime management of nuclear power plant program (LMNPP), ''Nuclear Power Plant Lifetime Management (PLIM) (I)'', since November 1993, which is a feasibility study of the Kori Unit 1 lifetime management including aging evaluation of the thirteen major components. The results of the PLIM(I) will provide information which is necessary for decision making of the Kori Unit 1 lifetime improvement. A plan of the work scope and schedule for the next phase, PLIM(II), will also be provided by this project. This paper introduced KEPRI's basic strategy of LMNPP, PLIM organization, current status, some interim results of the PLIM(I), and other related programs in Korea. So far, we have done field data survey, systems/structures screening, components prioritization, lifetime evaluation methodology study, and fracture mechanics tests of the Kori Unit 1 reactor pressure vessel surveillance coupons. Currently life assessment of the major components and PLIM economic evaluation of Kori Unit 1 are under way. (author)

Status of NDE research and applications for life management of nuclear power plants in india

Energy Technology Data Exchange (ETDEWEB)

Raj, B.; Shyamsunder, M.T.; Jayakumar, T. [Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Metallurgy and Materials Group

1999-08-01

The development and application of various nondestructive evaluation techniques and methodologies for the life management of nuclear power plants in India are described. The indigenous development carried out to meet the stringent quality requirements in evaluation of fabricated components and innovative methodologies using multidisciplinary approaches and advances for assessment of inservice performance of plants are highlighted. (orig.)

Status of NDE research and applications for life management of nuclear power plants in india

International Nuclear Information System (INIS)

Raj, B.; Shyamsunder, M.T.; Jayakumar, T.

1999-01-01

The development and application of various nondestructive evaluation techniques and methodologies for the life management of nuclear power plants in India are described. The indigenous development carried out to meet the stringent quality requirements in evaluation of fabricated components and innovative methodologies using multidisciplinary approaches and advances for assessment of inservice performance of plants are highlighted. (orig.)

Competences and life management programmes

International Nuclear Information System (INIS)

Brunatti, S.; Bergara, A.; Ranalli, J.; Versaci, R.

2007-01-01

Full text: The nuclear industry is, at present, at a crucial juncture, where it has to decide about the future of the first generation of nuclear plants, which are approaching the end of their licensed service life. At the same time, long term experience and new advances have established that it is possible to extend the life of nuclear plants beyond their initially licensed life by another 20-30 years. Extending the operating life of existing nuclear plants will help to reduce the short term need for new generating capacity - without new capital costs. However, these extensions must take place in the context of careful safety analysis and monitoring of equipment ageing concerns. A nuclear power plant must be managed in a safe and efficient manner throughout all the life cycle stages from design through decommissioning. The consequences of management decisions about nuclear power plants can have profound economic impacts for the nuclear power plant owner, and possibly for the national economy. In addition, the consequence of a major failure or accident can have catastrophic national socio-economic effects that may be felt internationally. The safe and effective management of a nuclear power plant therefore requires dramatically different perspectives in time from the majority of other industries. The impact of some decisions extends beyond the normal strategic perspective of both owners and governments. The integration of activities for ageing management, safety management and business management of a nuclear power plant are an essential element of 'life cycle management'. The loss of information at any stage of a nuclear power plants life deprives people, at later stages, of knowledge that could be important to safe, economic completion of work or which could aid the analysis of problems and options. It is costly to go through the learning process again, with a risk of potential events or incidents, programme delays, physical injury and increased regulatory

Eu-funded nuclear research on plant life management in the 4. and 5. framework programme

International Nuclear Information System (INIS)

Lemaitre, P.; Van Goethem, G.

2001-01-01

In this paper an overview will be given of the European Union EURATOM research in the field of plant life management and ageing of structural components. The results obtained so far in the projects executed under the 5. framework programme (FP-5/1999-2002) will be presented and discussed in detail. The objectives of the 5. framework programme, which is end-user driven, are: 1) to develop a common basis for the continued safe operation and prolonging the safe operational life-spans of existing nuclear installations; 2) to develop better methods for their inspection, maintenance and management (both in terms of performance and occupational exposure). The following three sections were proposed under this heading of the work programme: Integrity of equipment and structures, on-line monitoring, inspection and maintenance, and organisation and management of safety. Besides the traditional technological challenges, socio-economic concerns are also taken on board, such as public acceptance and cost of the nuclear option as well as plant simplification and man-technology-organisation interaction. An additional challenge for the EU consists of the enlargements process towards Central and Eastern European Countries in the coming years. Therefore FP5 pays attention also to plant safety assessments of VVER reactors and to the spreading of the new safety culture in these candidate countries in co-operation with similar activities run at the Commission especially under the programmes of Tacis/Phare and of the Joint Research Centre (JRC). In the area of plant life management so far 18 projects have been selected for funding by the European Commission. Most of them are costs shared actions, which means that the European Commission on the one hand and the project partners on the other hand provide each 50 % of the necessary funding. The total contract value of the selected projects is about 18 million euros. (authors)

Eu-funded nuclear research on plant life management in the 4. and 5. framework programme

Energy Technology Data Exchange (ETDEWEB)

Lemaitre, P.; Van Goethem, G. [European Commission, Dir. General Research, Bruxelles (Belgium)

2001-07-01

In this paper an overview will be given of the European Union EURATOM research in the field of plant life management and ageing of structural components. The results obtained so far in the projects executed under the 5. framework programme (FP-5/1999-2002) will be presented and discussed in detail. The objectives of the 5. framework programme, which is end-user driven, are: 1) to develop a common basis for the continued safe operation and prolonging the safe operational life-spans of existing nuclear installations; 2) to develop better methods for their inspection, maintenance and management (both in terms of performance and occupational exposure). The following three sections were proposed under this heading of the work programme: Integrity of equipment and structures, on-line monitoring, inspection and maintenance, and organisation and management of safety. Besides the traditional technological challenges, socio-economic concerns are also taken on board, such as public acceptance and cost of the nuclear option as well as plant simplification and man-technology-organisation interaction. An additional challenge for the EU consists of the enlargements process towards Central and Eastern European Countries in the coming years. Therefore FP5 pays attention also to plant safety assessments of VVER reactors and to the spreading of the new safety culture in these candidate countries in co-operation with similar activities run at the Commission especially under the programmes of Tacis/Phare and of the Joint Research Centre (JRC). In the area of plant life management so far 18 projects have been selected for funding by the European Commission. Most of them are costs shared actions, which means that the European Commission on the one hand and the project partners on the other hand provide each 50 % of the necessary funding. The total contract value of the selected projects is about 18 million euros. (authors)

Integrated Life Cycle Management: A Strategy for Plants to Extend Operating Lifetimes Safely with High Operational Reliability

International Nuclear Information System (INIS)

Esselman, Thomas; Bruck, Paul; Mengers, Charles

2012-01-01

Nuclear plant operators are studying the possibility of extending their existing generating facilities operating lifetime to 60 years and beyond. Many nuclear plants have been granted licenses to operate their facilities beyond the original 40 year term; however, in order to optimize the long term operating strategies, plant decision-makers need a consistent approach to support their options. This paper proposes a standard methodology to support effective decision-making for the long-term management of selected station assets. Methods detailed are intended to be used by nuclear plant site management, equipment reliability personnel, long term planners, capital asset planners, license renewal staff, and others that intend to look at operation between the current time and the end of operation. This methodology, named Integrated Life Cycle Management (ILCM), will provide a technical basis to assist decision makers regarding the timing of large capital investments required to get to the end of operation safely and with high plant reliability. ILCM seeks to identify end of life cycle failure probabilities for individual plant large capital assets and attendant costs associated with their refurbishment or replacement. It will provide a standard basis for evaluation of replacement and refurbishment options for these components. ILCM will also develop methods to integrate the individual assets over the entire plant thus assisting nuclear plant decision-makers in their facility long term operating strategies. (author)

Integrated NPP life cycle management - Agency's approach

International Nuclear Information System (INIS)

Gueorguiev, B.

2002-01-01

Full text: The number of nuclear power plants (NPPs) operating in the world has been roughly constant for the past seven years. There are 438 reactors of 353,489 MW(e) capacity in the world and they generated 2448.9 TWh in 2001 giving a total world operating experience with nuclear power of 10,363 years. About 230 units have reached already over 15 years of operation and significant number of these plants are fully depreciated. Share of nuclear power in electricity production sector in Member States utilising nuclear power plants represents a meaningful amount and in 14 countries it exceeds 30%. Therefore, a loss of this share should be covered by new installed capacities either from conventional or alternative sources of electricity generation. Recent forecasts, for nuclear power use over the next two decades range from ∼350 to ∼500 GW(e) worldwide. While assessing the need for any nuclear power related programmes there are several important factors that must be considered since even 350 GW(e) is a very large programme requiring several hundred thousand highly qualified personnel and a substantial infrastructure to assure its continued safe, reliable and cost-effective operation. It is important to assure reliable, safe and economic beneficial performance of the plant, which requires in turn an appropriated management of any activity connected with any taken period of a plant life starting from design and ending by the decided mode of decommissioning. The period between the first and the last payment for the activities connected with the existence of a plant could be defined as a life cycle of the plant. Such integrated approach requires considering the life cycle of the plant in a much broader sense than just operational life and is characterized by the variety of activities and their management represents in a whole a plant life management programme (PLIM). Therefore PLIM could be defined as an aggregate (totality) of technical, financial, economical and

Activities of the IAEA International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP)

International Nuclear Information System (INIS)

Ianko, L.

1994-01-01

Activities of the IAEA international working group on life management of nuclear power plants are outlined with emphasis on objectives, scope of activities, methods of work, organizational matters, financing

Overview of the Italian activities in the field of life management of nuclear power plants

International Nuclear Information System (INIS)

Pini, A.

1994-01-01

Overview of the Italian activities in the field of life management of nuclear power plants is presented, including the following issues: nuclear energy scenario in Italy, study of reactor pressure vessel, piping and containment integrity, seismic risk analysis

FP-4 and FP-5 Euratom research activities in the field of plant life management

International Nuclear Information System (INIS)

Lemaitre, P.; Goethem, G. van

2001-01-01

In this paper an overview is given of the European Union (EU) Euratom research conducted through shared cost and concerted actions in the field of plant life management. After a general introduction on the organisation of the research framework programmes the achievements of the 4th framework programme (FP-4/1994-1998) and the activities under the 5th framework programme (FP-5/1999-2002) in the field of plant life management are presented and discussed in detail. Besides technological safety requirements, socio-economic aspects are becoming increasingly important due to the level of public and political acceptance and to the economic pressure of deregulated electricity markets. It is shown that research conducted in the Euratom framework may contribute to meet these requirements, thereby maintaining nuclear power as a competitive and sustainable option for the energy policy of the European Union. (author)

Russian conceptions of plant life management and decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Bugaenko, S.E.; Butorin, S.L.

2000-01-01

Plant life management (PLIM) of nuclear power plant is the concept and practice to provide profitability of safe operation of nuclear electricity-generating installations. Therefore, application of the PLIM technology is a unique possibility for the nuclear power not only to preserve its presence at the generated electricity market but also to enlarge it there at the first quarter of the third millennium. PLIM is considered as the concept and procedure covering the whole life cycle of NPP, consisting of three main phases: pre-operation, operation, post-operation. When considering the list of the main standard works for PLIM, one can notice that the structure of a full volume of works can be presented as the sum of two constituents: specific for a particular power unit and universal one. A specific constituent implies realising the PLIM process at a particular power unit, and universal one implies development scientific-methodological, technological and normative basis supporting PLIM process. The concept of decommissioning NPP power units was developed and adopted in 1991, and nowadays is renewed. Its main principles and provisions correspond to a general approach to decommissioning nuclear power plants which was adopted in international practice and recommended in the IAEA documents. Elimination of NPP power unit is adopted in it as the basic option

Life cycle management at nuclear power plants; La gestion de la vida util de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Diez, R.I.

2010-07-01

The Life Management Plan (PGV) consists in a series of actions aimed at improving the reliability and availability of a plant by guaranteeing its operation in safe conditions during its design life while keeping open the option of renewing the operating license in the long term. (Author).

RIMAP demonstration project. Pat. 1: Risk based life management of piping system in power plant Heilbronn

International Nuclear Information System (INIS)

Bareiss, J.; Puck, P.; Matschecko, B.; Jovanovic, A.; Balos, D.; Perunicic

2003-01-01

In the framework of EU project RIMAP [1] a new European Guideline for optimized risk based maintenance and inspection planning of industrial plants (RBLM - Risk Based Life Management) is being developed. The RIMAP project consists of the three clustered projects: development (RTD), demonstration (DEMO) and thematic network (TN). Current work and future, planned work in RIMAP demonstration project on applications of the RIMAP methodology in power plants are presented briefly in the first part of the paper. Also presented in the paper are the results of a preliminary analysis of piping system in power plant Heilbronn using the concept of risk-based monitoring as part of overall concept of risk-based life management. Shortly the following issues are discussed in the paper: identification of critical components, application of a multilevel risk analysis (..from ''screening'' to ''detailed analysis''), determination of PoF - Probability of Failure, determination of COF - Consequence of Failure and optimation of inspection and maintenance plan. (orig.)

A resource guide to nuclear plant life-cycle management

International Nuclear Information System (INIS)

Negin, C.A.; Klein, D.J.

1993-11-01

Forecasting the useful economic life of a nuclear unit and addressing the complementary issue of license renewal, both key elements of life cycle management, are complex undertakings. This guide is a resource document emphasizing the technical elements of life cycle management (LCM) with focus on the determination of adequate maintenance programs and the identification of data and records necessary to support them. Information on other life cycle management issues, such as license renewal regulation, is also provided. Because of the volume of information required for LCM evaluations and the need for periodic updating, this Guide is presented as an updatable ''electronic book.''

Steam generator life management

International Nuclear Information System (INIS)

King, P.; McGillivray, R.; Reinhardt, W.; Millman, J.; King, B.; Schneider, W.

2003-01-01

'Full-Text:' Steam Generator Life Management responsibility embodies doing whatever is necessary to maintain the steam generation equipment of a nuclear plant in effective, reliable service. All comes together in that most critical deliverable, namely the submission of the documentation which wins approval for return to service after an outage program. Life management must address all aspects of SG reliability over the life of the plant. Nevertheless, the life management activities leading up to return to service approval is where all of it converges. Steam Generator Life Management activities entail four types of work, all equally important in supporting the objective of successful operation. These activities are i) engineering functions; including identification of inspection and maintenance requirements, outage planning and scope definition plus engineering assessment, design and analysis as necessary to support equipment operation, ii) fitness of service work; including the expert evaluation of degradation mechanisms, disposition of defects for return to service or not, and the fitness for service analysis as required to justify ongoing operation with acceptable defects, iii) inspection work; including large scale eddy current inspection of tubing, the definition of defect size and character, code inspections of pressure vessel integrity and visual inspections for integrity and iv) maintenance work; including repairs, retrofits, cleaning and modifications, all as necessary to implement the measures defined during activities i) through iii). The paper discusses the approach and execution of the program for the achievement of the above objectives and particularly of items i) and ii). (author)

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Life extension and life cycle management

International Nuclear Information System (INIS)

Hoang, H.

2010-10-01

To continue the effort of nuclear energy as the clean energy offsetting the increase in greenhouse gas emission that contributes to the increased global warming effect, the nuclear industry is focused on the optimization of their current nuclear generation assets. Plant life extension (Plex) and Plant life management (Plim), together with power up rate, are the key strategies for the optimization effort. Plex begins with the process to obtain the regulatory approval for an additional 20 years of operation, beyond the current 40-year limit. This highly standardized process consists of the following steps: 1) Scoping: identify the systems, structures and components for inclusion in the license renewal scope of work. 2) Screening: narrow down the selection of the in-scope systems, structures and components based on passive and long-lived characteristics. 3) Aging management review: demonstrate that aging effects will continue to be managed during the additional 20 years of operation. 4) Time limiting aging analyses: confirm the acceptability of design bases analyses that assume the 40-year plant life as a key input assumptions. To provide a consistent approach for the preparation of the license renewal application, the following are the key guidance documents: NUREG-1800: Standard review plan; NUREG-1801: Generic aging lessons learned; Nuclear Energy Institute NEI 95-10. The objectives of Plim are to focus on improving plant reliability/availability, and to plan for equipment upgrades for efficiency improvement as well as technological obsolescence. Plim is a technical evaluation combined with a risk assessment to produce a long-range business plant with a time horizon of 10 years or longer. Due to its long view nature, this plan will be reviewed on a yearly basis for any required adjustments. The technical evaluation consists of the following major steps: 1) Select systems, structures and components with performance deficiencies experience. 2) Collect operating data

Life Limiting Issues for Long Term Operation of Nuclear Power Plants

International Nuclear Information System (INIS)

Esselman, Thomas; Gaertner, John

2012-01-01

This paper reports on a study which identified and characterized life limiting issues for consideration by nuclear plant owners in their decision to extend plant life or seek subsequent license renewal. As nuclear plants operate for longer periods, the risk that a condition in the plant or an event that occurs, at the plant or elsewhere, will cause a plant owner not to extend plant life increases. The Fukushima accident has made this concept concrete. This paper defines 'Life Limiting' concepts for nuclear plants. It identifies the highest risk conditions and events that may limit duration of continued operation in nuclear plants and employs a survey to prioritize these concerns. Methods for evaluating these risks and changing the capability of systems, structures, and components (SSC) to reduce and manage this risk in long term operation are presented. Integrated obsolescence -the existence of an accumulation of events or condition that can threaten long term operation- is discussed. Many of the life limiting conditions or events may be controllable by early identification, recognition, and mitigation of the potential threat. The recognition of conditions may allow measures to be taken to mitigate the condition. Recognition of the potential for events that may be life limiting may allow actions to be taken that will minimize the likelihood or consequences of the event. These actions may include enhanced research on the expected behavior of the SSC, risk assessment and management, and enhanced monitoring and aging management at the plant. (author)

Aging plant life management - the requirements defined to date by the KTA nuclear engineering codes

International Nuclear Information System (INIS)

Kalinowski, I.

1996-01-01

German nuclear engineering codes so far do not enclose a specific aging plant life management programme. However, the existing codes and standards do contain a number of applicable requirements and principles of relevance to objectives and principles of such programmes, as they also cover aging-induced effects on power plants. The major principles relating to preventive safety engineering and quality assurance are laid down in the publications KTA 1401, 1404, 1201, 1202, and KTA 3211. (DG) [de

Nuclear power plant life management: flow accelerated corrosion and chemical control. Application to Embalse Nuclear power plant

International Nuclear Information System (INIS)

Chocron, Mauricio; Saucedo, Ramona E.; Sainz, Ricardo A.; Ovando, Luis E.

2006-01-01

The chemistry of a water-steam cycle is one of the main aspects of the Plant Life Management of a Nuclear Power Plant and it is important for the preservation, efficiency and availability of the whole system. In that sense this aspect has to be prioritized in any study whose aim is the life extension of the plant. In particular, the flow-assisted -corrosion or FAC is a problem that worldwide has been considered important due to the piping wall thinning that in some occasions has led to severe accidents. The FAC phenomena is not easy to be interpreted and addressed although nowadays there are some accepted models to understand and predict sensitive areas of the cycle. The objectives of the present paper have been: a) The construction of an integrated code that involves all the aspects that have influence on FAC, i.e., materials, composition, geometry, temperature and flow rate, quality, chemistry, etc.; b) Establish or adapting current models to the circuit of Embalse PHWR NPP; c) Identify new locations for inspection and wall thickness measurement in order to predict residual life; d) Compare different chemistries and e) handle large sets of inspection data. Among the results, new lines have been incorporated to the inspection schedule of the 2005' programmed outage. Also, the evaluation is part of the PLIM-PLEX programme at Embalse-N.A.S.A. in collaboration with C.N.E.A. is being carried out. (author)

Towards a more consolidated approach to material data management in life assessment of power plant components

Energy Technology Data Exchange (ETDEWEB)

Jovanovic, A; Maile, K [MPA Stuttgart (Germany)

1999-12-31

The presentation discusses the necessity of having a more consolidated (unified, possibly `European`) framework for all (not only pure experimental) material data needed for optimized life management and assessment of high-temperature and other components in power and process plants. After setting the main requirements for such a system, a description of efforts done in this direction at MPA Stuttgart in the area of high-temperature components in power plants is given. Furthermore, a reference to other relevant efforts elsewhere is made and an example of practical application of the proposed solution described (optimized material selection and life assessment of high-temperature piping). (orig.) 10 refs.

Towards a more consolidated approach to material data management in life assessment of power plant components

Energy Technology Data Exchange (ETDEWEB)

Jovanovic, A.; Maile, K. [MPA Stuttgart (Germany)

1998-12-31

The presentation discusses the necessity of having a more consolidated (unified, possibly `European`) framework for all (not only pure experimental) material data needed for optimized life management and assessment of high-temperature and other components in power and process plants. After setting the main requirements for such a system, a description of efforts done in this direction at MPA Stuttgart in the area of high-temperature components in power plants is given. Furthermore, a reference to other relevant efforts elsewhere is made and an example of practical application of the proposed solution described (optimized material selection and life assessment of high-temperature piping). (orig.) 10 refs.

RIMAP demonstration project. Risk-based life management of piping system in power plant Heilbronn

International Nuclear Information System (INIS)

Bareiss, J.; Buck, P.; Matschecko, B.; Jovanovic, A.; Balos, D.; Perunicic, M.

2004-01-01

In the framework of EU project RIMAP [Risk Based Inspection and Maintenance Procedures for European Industry (2000)] a new European Guideline for optimized risk based maintenance and inspection planning of industrial plants (RBLM, Risk Based Life Management) is being developed. The RIMAP project consists of the three clustered projects: - development (RTD); - demonstration (DEMO): - thematic network (TN). Current work and future, planned work in RIMAP demonstration project on applications of the RIMAP methodology in power plants are presented briefly in the first part of the paper. Also presented in the paper are the results of a preliminary analysis of piping system in power plant Heilbronn using the concept of risk-based monitoring as part of overall concept of risk-based life management. Shortly the following issues are discussed in the paper: - identification of critical components; - application of a multilevel risk analysis (...from 'screening' to 'detailed analysis'); - determination of PoF (Probability of Failure); - determination of CoF (Consequence of Failure); - optimation of inspection and maintenance plan. From our experience with the application of the RIMAP methodology the following conclusions can be drawn: The use of risk-based methods in inspection and maintenance of piping systems in power plants gives transparency to the decision making process and gives an optimized maintenance policy based on current state of the components. The results of the work clearly show the power of the proposed method for concentration on critical items: out of 64 monitored components 5 were selected for intermediate analysis and only 1 for the detailed analysis (probabilistic high temperature fracture mechanics)

Managing ageing of Karachi nuclear power plant (KANUPP)

International Nuclear Information System (INIS)

Hoda, M. Qamrul; Jamal-ur-Rahman

2002-01-01

Full text: Karachi Nuclear power Plant (KANUPP), a 137 MWe CANDU plant, was built on a turn-key basis by the Canadian General Electric (CGE) in the late sixties. The plant with a design life of thirty years went into commercial operation in October, 1972. After nearly three decades of operation, KANUPP like all other plants has faced the problem of equipment ageing and obsolescence. KANUPP has been striving hard to combat these problems with the assistance from IAEA, COG and WANO. During early eighties IAEA expert missions were called at KANUPP on various safety issues and on their recommendations various projects such as Safe Operation of KANUPP, Technical Upgradation Project, Balancing, Modernization and Rehabilitation project were initiated to combat equipment ageing and obsolescence. KANUPP has made substantial progress in the implementation of the tasks under these projects and the operating life of the plant is expected to be extended by 15 years. Three IAEA expert missions were invited at KANUPP during 1999-2000 to carry out assessment of the ongoing activities related to plant ageing management. On the basis of their recommendations an ageing Management Programme has been formally established at KANUPP to manage age-related degradation of plant systems, structures and components important to safety and to ensure that the required safety functions are available for the extended life of the plant. Being close to completion of its nominal design life in October 2002, KANUPP has already applied to Pakistan Nuclear Regulatory Authority for renewal of operating license. This paper briefly describes the activities related to ageing management of KANUPP to fulfil the requirement for its continued operation beyond its design life. (author)

Lifetime management research trend of Kori-1 nuclear power plant

International Nuclear Information System (INIS)

Kim, J. S.; Jeong, I. S.; Hong, S. Y.

1998-01-01

KEPRI launched the Nuclear Power Plant Lifetime Management Study(II) for the management of the latter half life of Kori-1. Main goal of LCM-IV study is the detail evaluation of main equipment life and establishment of aging management based on LCM-IV result. The result of LCM-IV on the kori-1 confirmed the technical and economical feasibility of life extension beyond the design life. Owing to absence of The regulatory policy for the life extension in korea, LCM-IV will focus on the minimum study which is essential for the actual lifetime management for the old nuclear power plant. License renewal study is expected after the establishment of Regulatory policy about the life extension of nuclear power plant. LCM trend in korea and abroad, result of technical and economical feasibility study and summary of LCM-IV is described on this paper

Nuclear Power Plant Life Management - Challenges and Proposal for a Unified Model Integrating Safety and Economics

International Nuclear Information System (INIS)

Contri, Paolo; Elsing, Bernhard

2011-01-01

In recent years many electric utilities and nuclear power plants adopted policies for improved coordination of both safety and non-safety programs, called plant life management (PLIM), also in view on plant life extension programs, but mainly for an optimisation of operating costs. The implementation of PLIM programs has followed many different approaches, being intrinsically dependent on the national regulatory framework and technical traditions. In Countries with some experience, the PLIM program proved very convenient, especially when coupled with Maintenance, Surveillance an Inspection (MS and I) optimization: average savings are reported in the range of 20-30% of total (maintenance) costs. A unified European model for PLIM was developed at the JRC-Institute for Energy with the support of a network of stakeholders (SENUF), and validated at some EU nuclear plants. This paper provides a summary of the model features, the result of its validation at some plants and summarises the perceived scientific/technological challenges on which JRC proposes to focus, based upon its competencies and skills, having in mind both the European and world-wide context and its potential evolution. (author)

Plant life time management for safe long term operation

International Nuclear Information System (INIS)

Burket, Danes

2010-01-01

The topics discussed include LTO (long-term operation) and licensing procedure in general and specifically for the Dukovany NPP, components of an LTO programme, the PLIM (plant life management) concept for Dukovany and Temelin, the LTO implementation project for Dukovany, LTO strategy, LTO risk study, international verification. The Conclusions include the following items: (i) Technical-economic study of Dukovany NPP LTO demonstrates technical feasibility and economic profitability of Dukovany NPP LTO with perspective for up to 60 years of operation. (ii) Safety part of Program for assurance of Dukovany NPP LTO complies with IAEA SALTO recommendations. (iii) Dukovany NPP LTO programme incorporated IAEA SALTO Peer Review Mission recommendations. (iv) LTO Implementation Project for 2009-2015 was approved with major targets to renew operational permission and prepare NPP for operation up to 60 years. (v) Preparation of Temelin NPP LTO programme has been started. (P.A.)

Materials for Nuclear Plants From Safe Design to Residual Life Assessments

CERN Document Server

Hoffelner, Wolfgang

2013-01-01

The clamor for non-carbon dioxide emitting energy production has directly  impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments  provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts.   Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, material...

French nuclear plants PWR vessel integrity assessment and life management

Energy Technology Data Exchange (ETDEWEB)

Bezdikian, G. [Electricite de France (EDF), Div. Production Nucleaire, 93 - Saint-Denis (France); Quinot, P. [FRAMATOME, Dept. Bloc Reacteur et Boucles Primaires, 92 - Paris-La-Defence (France); Faidy, C.; Churier-Bossennec, H. [Electricite de France (EDF), Div. Ingenierie et Service, 69 - Villeurbanne (France)

2001-07-01

The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

French nuclear plants PWR vessel integrity assessment and life management

International Nuclear Information System (INIS)

Bezdikian, G.; Quinot, P.; Faidy, C.; Churier-Bossennec, H.

2001-01-01

The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

Life cycle management in the U.S.: Stone and Webster's experience

International Nuclear Information System (INIS)

Banerjee, A.K.

1992-01-01

Life Cycle Management (LCM) is a sound methodology that integrates plant operations, maintenance requirements and practices, capital improvements, radioactive waste strategies, decommissioning, and life extension. It is a structured decision-making process for plant aging management and performance improvement. Stone and Webster has used this process for many fossil plants, and is now using it at several nuclear plants. This paper discusses Stone and Webster's experiences with LCM programs at U.S. nuclear power plants. 1 ref., 3 tabs., 8 figs

Configuration management; Solution for mid-life crisis

International Nuclear Information System (INIS)

Hancock, L.R.

1993-01-01

With the age of most commercial nuclear power plants hovering around twenty years, there is a mid-life crisis facing their engineering management. The crisis is that the design of the plant represented on the engineering documents (electronic or hard copy) and the actual plant configuration increasingly do not match each other. This paper will present: (1) an historical perspective on the evolution of nuclear plant design control technology, (2) impacts that plant operations have on the design, (3) a discussion of the consequences of weak design control, and (4) will offer a methodology to define and improve the configuration management program

NPP component maintenance and life management in Russia

International Nuclear Information System (INIS)

Tutnov, I.; Lyssakov, V.

2002-01-01

This report represents the conceptual strategies (ideas) on life management programs for nuclear power plants. Use of the optimum programs for NPP's NDE, maintenance service, operation and service life can provide the best economic benefit for the utilities. The paper presents general approaches to life management, maintenance service, and risks of operating and service life of NPPs in Russia. The report offers some optimized ways for the solution of these important tasks

Residual life management. Maintenance improvement; Gestion de vida remanente. Mejora del mantenimiento

Energy Technology Data Exchange (ETDEWEB)

Sainero Garcia, J; Hevia Ruperez, F

1996-12-31

The terms Residual Life Management, Life Cycle Management and Long-Term Management are synonymous with a concept which aims to establish efficient maintenance for the profitable and safe operation of a power plant for as long as possible. A Residual Life Management programme comprises a number of stages, of which Maintenance Evaluation focuses on how power plant maintenance practices allow the mitigation and control of component ageing. with this objective in mind, a methodology has been developed for the analysis of potential degradative phenomena acting on critical components in terms of normal power plant maintenance practices. This methodology applied to maintenance evaluation enables the setting out of a maintenance programme based on the Life Management concept, and the programme`s subsequent up-dating to allow for new techniques and methods. Initial applications have shown that although, in general terms, power plant maintenance is efficient, the way in which Residual Life Management is approached requires changes in maintenance practices. These changes range from modifications to existing inspection and surveillance methods or the establishment of new ones, to the monitoring of trends or the performance of additional studies, the purpose of which is to provide an accurate evaluation of the condition of the installations and the possibility of life extension. (Author)

Management of nuclear power plants lifetime

International Nuclear Information System (INIS)

Hutin, J.P.

2006-01-01

The factors influencing the management of the service life of nuclear power plants can be of various types and the 'heaviest' ones have to be managed through robust and explicit approaches involving all actors. However, the mastery of the service life starts with the mastery of the technical problems, in particular the physical aging of the facilities. This mastery requires to foresee and anticipate the problems and thus a good understanding of the phenomena involved. This article presents: 1 - the general problem of service life management: lifetime concept, situation of French power plants, service life management policy; 2 - aging mechanisms: embrittlement of steel under irradiation, swelling of materials, thermal aging, fatigue, stress corrosion, aqueous corrosion of metals, corrosion-erosion, mechanisms of concrete degradation, mechanisms of elastomers and polymers degradation, wear; 3 - non-replaceable parts: reactor vessel, containment building; 4 - replaceable parts: cables, instrumentation and control system, core internals, primary loop piping, auxiliary primary piping, pressurizer, primary pump, steam generator tubes, other Ni-Cr-Fe alloy parts, secondary loop piping, turbine, alternator; 5 - non-technical aspects: perenniality of the industrial support, evolution of safety requirements, public acceptance, economical aspects, knowledge and information systems; 6 - situation in foreign countries: status of the world nuclear park, lifetime notion in foreign countries, situation in the USA. (J.S.)

Proceedings: 2003 Workshop on Life Cycle Management Planning for Systems, Structures, and Components

International Nuclear Information System (INIS)

2003-01-01

These proceedings of the 2003 EPRI Life Cycle Management Workshop provide nuclear plant owners with an overview of the state of development of methods and tools for performing long-term planning for maintenance, aging management, and obsolescence management of systems, structures, and components important to a plant's long-term safety, power production, and value in a market-driven industry. The proceedings summarize the results of applying life cycle management at several plants

R and D status for NPP life management in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Ryong [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

2009-04-15

The economical benefits may be achieved by the plant life management (PLiM) as well as structural integrity of the critical components of NPP. Systems, structures and components (SSC) of NPP are designed to have safety margins in design stage, and being operated with operational margins. As the plant gets older and older, however, aging of SSC occurs and some of SSC may be sometimes failed due to the unexpected aging mechanisms in design stage. Most countries which have operated NPP have their own R and D programs to establish proper countermeasures against the aging and degradation of SSC, The well known program are materials reliability program (MRP) and steam generator management program (SGMP) of EPRI. In Korea, we also have our own R and D programs for the plant life management. In this paper, the present status of the R and D programs will be introduced. Long term operation of a nuclear power plant is one of the goals that the plant wants to achieve, which may be possible as long as the plant safety is maintained and the economical benefits is expected. The economical benefits may be achieved by the plant life management (PLiM) activities. Many R and D activities related to PLiM have been carried out and implemented to Korean NPP, Kori Unit 1 and Wolsong Unit 1 in particular, for the long term operation beyond their original design lives. Those activities include PLiM study, PSR, SGMP, MRP, thinned pipe management program, study on dissimilar metal welds, aging monitor etc. With the results of R and D activities, continued operation of Kori Unit 1 was successfully started from January 17, 2008 for next 10 years beyond its design life. It must be a landmark of 30 years history of nuclear power generation in Korea. Subsequently Wolsong Unit 1 is also expected to start its continued operation when the replacement of pressure tubes and feeders are completed in 2009. Many countries have plans to build new reactors or to extend the life of operating plants.

R and D status for NPP life management in Korea

International Nuclear Information System (INIS)

Kim, Tae Ryong

2009-01-01

The economical benefits may be achieved by the plant life management (PLiM) as well as structural integrity of the critical components of NPP. Systems, structures and components (SSC) of NPP are designed to have safety margins in design stage, and being operated with operational margins. As the plant gets older and older, however, aging of SSC occurs and some of SSC may be sometimes failed due to the unexpected aging mechanisms in design stage. Most countries which have operated NPP have their own R and D programs to establish proper countermeasures against the aging and degradation of SSC, The well known program are materials reliability program (MRP) and steam generator management program (SGMP) of EPRI. In Korea, we also have our own R and D programs for the plant life management. In this paper, the present status of the R and D programs will be introduced. Long term operation of a nuclear power plant is one of the goals that the plant wants to achieve, which may be possible as long as the plant safety is maintained and the economical benefits is expected. The economical benefits may be achieved by the plant life management (PLiM) activities. Many R and D activities related to PLiM have been carried out and implemented to Korean NPP, Kori Unit 1 and Wolsong Unit 1 in particular, for the long term operation beyond their original design lives. Those activities include PLiM study, PSR, SGMP, MRP, thinned pipe management program, study on dissimilar metal welds, aging monitor etc. With the results of R and D activities, continued operation of Kori Unit 1 was successfully started from January 17, 2008 for next 10 years beyond its design life. It must be a landmark of 30 years history of nuclear power generation in Korea. Subsequently Wolsong Unit 1 is also expected to start its continued operation when the replacement of pressure tubes and feeders are completed in 2009. Many countries have plans to build new reactors or to extend the life of operating plants.

Enhanced design, operation and maintenance practices for a longer plant service life

International Nuclear Information System (INIS)

Raimondo, E.; Courcoux, A.

2004-01-01

Plant service life problems have been under detailed investigation in France and the experience acquired by our company over the past 25 years in the design, construction and maintenance of Pressurized Water Reactors has contributed to develop skills, equipment and capabilities available for efficient plant aging management and component service life extension. The service life of a nuclear power plant is deeply dependant of the provisions made during the design stage, directly linked to good operating conditions and adequate maintenance practices. This paper presents the importance of these three steps (design, operation and maintenance) for plant service life concern. (author)

IAEA activities in the field of NPP life management

International Nuclear Information System (INIS)

Gueorguiev, B.; Lyssakov, V.; Davies, L.M.

1997-01-01

The IAEA has established programmes in the field of Nuclear Plant Lifetime in the Division of Nuclear Power and the Fuel Cycle (NEPF) and also in the Division of Nuclear Safety. In the Division of NEPF the International Working Group on Life Management of Nuclear Power Plants carries out its activities within the IAEA Project A2.03 ''Nuclear Power Plant Life Management''. Activities under this project have produced a wealth of information by organizing specialists meeting, preparing technical publications on related topics and arranging co-ordinated research programmes with good results. The most recent development is a database which has been developed and is being maintained. 4 figs

IAEA activities in the field of NPP life management

Energy Technology Data Exchange (ETDEWEB)

Gueorguiev, B; Lyssakov, V; Davies, L M

1997-09-01

The IAEA has established programmes in the field of Nuclear Plant Lifetime in the Division of Nuclear Power and the Fuel Cycle (NEPF) and also in the Division of Nuclear Safety. In the Division of NEPF the International Working Group on Life Management of Nuclear Power Plants carries out its activities within the IAEA Project A2.03 ``Nuclear Power Plant Life Management``. Activities under this project have produced a wealth of information by organizing specialists meeting, preparing technical publications on related topics and arranging co-ordinated research programmes with good results. The most recent development is a database which has been developed and is being maintained. 4 figs.

COMSY- A Software Tool For Aging And Plant Life Management With An Integrated Documentation Tool

International Nuclear Information System (INIS)

Baier, Roman; Zander, Andre

2008-01-01

For the aging and plant life management the integrity of the mechanical components and structures is one of the key objectives. In order to ensure this integrity it is essential to implement a comprehensive aging management. This should be applied to all safety relevant mechanical systems or components, civil structures, electrical systems as well as instrumentation and control (I and C). The following aspects should be covered: - Identification and assessment of relevant degradation mechanisms; - Verification and evaluation of the quality status of all safety relevant systems, structures and components (SSC's); - Verification and modernization of I and C and electrical systems; - Reliable and up-to-date documentation. For the support of this issue AREVA NP GmbH has developed the computer program COMSY, which utilizes more than 30 years of experience resulting from research activities and operational experience. The program provides the option to perform a plant-wide screening for identifying system areas, which are sensitive to specific degradation mechanisms. Another object is the administration and evaluation of NDE measurements from different techniques. An integrated documentation tool makes the document management and maintenance fast, reliable and independent from staff service. (authors)

Management of life cycle and ageing at nuclear power plants: Improved I and C maintenance. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2004-08-01

The topic of this TECDOC was originally suggested in the May 2001 meeting of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG NPPCI). It was then approved by the IAEA for work to begin in 2002. It originated from the remarks of the TWG members that it is now time to address the instrumentation and control (I and C) ageing issues in terms of plant life management and licence renewal. Furthermore, the nuclear industry is believed to be able to survive only if plant economy is favourable in addition to plant safety. Therefore, in dealing with I and C ageing and obsolescence, one has to consider how to proceed in addressing this question, not only from a plant operational and safety standpoint, but also in the context of plant economy in terms of the cost of electricity production, and including initial and recurring capital costs. For this important reason, consideration of new technologies, such as on-line monitoring and in situ testing methods is recommended. These can be used not only to predict the consequences of ageing, and guard against it, but also to verify equipment performance throughout the lifetime of the plant, and help establish replacement schedules for I and C equipment, and predict residual life. The basic ageing and obsolescence management process involves: Understanding the ageing and obsolescence phenomena and identifying the (potential) effects on I and C; Addressing the specific impact of these effects on the plant taking into account operational profiles and analyzing the risks; Carrying out necessary mitigating actions to counteract the effects of ageing and obsolescence. Based on the above listed activities the ageing and obsolescence management programme needs to be an iterative process. The goal of this TECDOC is to provide the latest information on ageing, obsolescence, and performance monitoring of those I and C equipment that are classified as safety equipment and/or safety-related equipment, are

System, structure, and component evaluation for life-cycle management

International Nuclear Information System (INIS)

Hanley, N.E.; Banerjee, A.K.; Woods, P.B.; Perrin, J.S.; Marian, F.A.

1992-01-01

In recent years, many nuclear organizations and utilities have studied the possibility of extending the service life of nuclear power plants beyond the original license period. From these studies, recommendations have resulted for maintaining the option of future decisions concerning operating license renewal. Several of the recommendations are considered beneficial to the management and operation of nuclear plants in meeting many of their near-term goals. In 1986, Public Service Electric and Gas (PSE and G) concluded that a full-scale nuclear plant license renewal program for their Salem 1 and 2 and Hope Creek nuclear stations was not cost-effective at that time. Rather, it would be better served if the nuclear plant life extension (PLEX) option were maintained for future consideration. To help plan for the life extension option, a strategic 5-yr life cycle management (LCM) program was begun. In support of the LCM program, evaluations for the following Salem structures and components were performed: (1) intake structures, (2) reactor vessel support, (3) containment liner, and (4) containment structure (below grade). This paper discusses the systems, structures, and components (SSC) evaluation methodology and, as an example, discusses the evaluation performed for reactor vessel support

Licensed bases management for advanced nuclear plants

International Nuclear Information System (INIS)

O'Connell, J.; Rumble, E.; Rodwell, E.

2001-01-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E; Rodwell, E [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

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)

Summary of plant life management evaluation for Onagawa Nuclear Power Station Unit-1

International Nuclear Information System (INIS)

Nodate, Kazumi

2014-01-01

The Onagawa Nuclear Power Station Unit-1 (Onagawa NPS-1) began commercial operation on June 1, 1984, and has reached 30-year from starting of operation on June of 2014. To that end, we implemented the Plant Life Management (PLM) evaluation for Onagawa NPS-1 as our first experience. We decided on a Long-term Maintenance Management Policy from result of the evaluation, and then applied the Safety-Regulations change approval application on November 6, 2013 and its correcting application on April 16, 2014. Our application was approved on May 21, 2014 through investigation by the Nuclear Regulatory Agency. Also at implementation of the PLM evaluation, we considered effects of the Great East Japan Earthquake that occurred on March 11, 2011 against ageing phenomena. In this paper, we introduce summary of PLM evaluation for Onagawa NPS-1 and the evaluation that considered effects of the Great East Japan Earthquake. (author)

The iPlant collaborative: cyberinfrastructure for enabling data to discovery for the life sciences

Science.gov (United States)

The iPlant Collaborative provides life science research communities access to comprehensive, scalable, and cohesive computational infrastructure for data management; identify management; collaboration tools; and cloud, high-performance, high-throughput computing. iPlant provides training, learning m...

Remaining life assessment and plant life extension in high temperature components of power and petrochemical plant

International Nuclear Information System (INIS)

Fleming, A.

2003-01-01

This paper explains the reasons why plant life can so easily be extended beyond the original design life. It details the means by which plant life extension is normally achieved, a structured plan for achieving such plant life extension at reasonable cost and some of the key techniques used in assessing the remaining life and discusses the simple repair options available. (author)

24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 2. Papers 28-63

International Nuclear Information System (INIS)

1999-01-01

The second volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The following topics are discussed: 1. Integrity of vessels, pipes and components. 2. Fracture mechanics. 3. Measures for the extension of service life, and 4. Online Monitoring. All 30 contributions are separately analyzed for this database. (orig.)

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J. [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E.; Rodwell, E. [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Nuclear power plant life extension in the United Kingdom

International Nuclear Information System (INIS)

Goodison, D.; Seddon, J.W.; Pape, E.M.

1991-01-01

The safety cases for the United Kingdom's older nuclear power plant have been reviewed by their utilities in order to justify continued operation of the reactors up to an age of at least 30 year. These 'long term safety reviews' have identified worthwhile plant modifications and aspects where further studies or plant inspections are required. As the plants approach the age of 30 years, 'life extension reviews' are now being undertaken, concentrating on management of ageing, to support operation to at least 40 years. (author)

Plant life management and modernisation: Research challenges in the EU

International Nuclear Information System (INIS)

Rintamaa, R.; Aho-Mantila, I.

2010-01-01

The NULIFE (Nuclear plant life prediction) European network of excellence is described in detail. The following topics are highlighted: Vision; Consortium; Organization and working methods; Research and development planning; Research project portfolio (pilot projects, umbrella projects); Strategic research planning; and Conclusions. (P.A.)

Life Management of high energy piping girth welds

International Nuclear Information System (INIS)

Cohn, M.J.; Paterson, S.R.

1994-01-01

Life management of high energy piping systems is a synergistic process that combines the collective results from nondestructive examination (NDE), stress analysis, metallurgical replication, and fracture mechanics evaluations. To achieve conclusions with high confidence and reliability, the methodology requires that: (1) all weldments must be appropriately examined to establish initial baseline data and indicate both fabrication and inservice damage, (2) as-found stress analyses must be consistent with field estimated displacements to select sites of maximum in-service damage, and (3) metallurgical replicas must be taken at high stress sites determined as an outcome of a life exhaustion evaluation. The multidiscipline tasks are effectively managed by developing a rational framework incorporating all of the above requirements. Analytical algorithms that estimate linear and nonlinear degradation effects are included in the remaining life predictions. High damage locations are selected based on a life exhaustion calculation. Localized remaining life and reexamination intervals for failures governed by creep and fatigue damage are estimated by metallurgical replica cavitation damage and the service life. Stress-based creep damage identified in metallurgical replicas should correspond to the predicted high damage locations from the life exhaustion calculation. The methodology minimizes future reexamination locations while providing high certainty of monitoring lead-the-fleet damage. This life management program recognizes the aging process in plant equipment. It establishes a continuous process of examinations, evaluations, and decisions to track degradation of the piping system life cycle. Potential problems are identified long before failures occur. Corrective action is taken during scheduled outages to maintain the required level of plant performance

Design basis reconstitution and configuration management of nuclear power plants

International Nuclear Information System (INIS)

Smith, P.R.; Cook, R.A.

1990-01-01

This paper presents a method by which all plants (those under construction, as well as those in operation) can benefit from a formal, step-by-step approach to data capture, storage, and retrieval for use throughout the plant life cycle. To demonstrate the viability and in-practice success of a single three-dimensional Configuration Management database, the specific capabilities of one such system are discussed in detail: the Plant Configuration Management System (PLANT/CMS). (orig.)

Canadian programs on understanding and managing aging degradation of nuclear power plant components

International Nuclear Information System (INIS)

Chadha, J.A.; Pachner, J.

1989-06-01

Maintaining adequate safety and reliability of nuclear power plants and nuclear power plant life assurance and life extension are growing in importance as nuclear plants get older. Age-related degradation of plant components is complex and not fully understood. This paper provides an overview of the Canadian approach and the main activities and their results towards understanding and managing age-related degradation of nuclear power plant components, structures and systems. A number of pro-active programs have been initiated to anticipate, detect and mitigate potential aging degradation at an early stage before any serious impact on plant safety and reliability. These programs include Operational Safety Management Program, Nuclear Plant Life Assurance Program, systematic plant condition assessment, refurbishment and upgrading, post-service examination and testing, equipment qualification, research and development, and participation in the IAEA programs on safety aspects of nuclear power plant aging and life extension. A regulatory policy on nuclear power plants is under development and will be based on the domestic as well as foreign and international studies and experience

Economic evaluation of Kori and Wolsong Unit 1 plant life extension

International Nuclear Information System (INIS)

Song, T. H.; Jeong, I. S.

2002-01-01

24 years have been passed since Kori Unit 1 began its commercial operation, and 19 years have been passed since Wolsong Unit 1 began its commercial operation. As the end point of design life become closer, plant life extension and periodic safety assessment is paid more and more attention to by the utility company. In this paper, the methodologies and results of plant lifetime management economic evaluations of both units have been presented in comparison with Korean standard nuclear power plant 10, 20 and 30 year life extension cases respectively. In addition to that, sensitivity analysis and break even point analysis results are presented with the variables of capacity factor, operation and maintenance cost, and discount rate

Characterization of in-containment cables for nuclear plant life extension

International Nuclear Information System (INIS)

DuCharme, A.R.; Bustard, L.D.

1988-01-01

Electrical cable is made by a large number of manufacturers and used for a variety of applications in nuclear plants. cables have been identified in the Monticello and Surry Pilot Plant life extension studies and the NRC Nuclear Plant Aging Research Program as components important to the economic and safety aspects of life extension. Currently, fitness for service is largely determined by preoperational testing. The US Department of Energy is supporting work at Sandia National Laboratories to assess the technical basis for the life extension of cables found inside containment at US nuclear plants. The work is being performed in coordination with the Nuclear Management and Resource Council's (NUMARC) NUPLEX Working Group. The initial task of this effort is to characterize the design attributes of in-containment cables. This has been completed via development of a data base depicting the manufacturer, type, material composition, use, qualification, and relative popularity of cables installed in containment. Other ongoing work is focused on a review of cable operational experience and assessment of the issues affecting cable life extension. In the long term, the work aims to identify the technical criteria and life extension strategies needed to support continued cable qualification by nuclear plant owner/operators. 7 refs., 4 tabs

A full life cycle nuclear knowledge management framework based on digital system

International Nuclear Information System (INIS)

Wang, Minglu; Zheng, Mingguang; Tian, Lin; Qiu, Zhongming; Li, Xiaoyan

2017-01-01

Highlights: • A full life cycle nuclear power plant knowledge management framework is introduced. • This framework benefits the safe design, construction, operation and maintenance. • This framework enhances safety, economy and reliability of nuclear power plant. - Abstract: The nuclear power plant is highly knowledge-intensive facility. With the rapid advent and development of modern information and communication technology, knowledge management in nuclear industry has been provided with new approaches and possibilities. This paper introduces a full cycle nuclear power plant knowledge management framework based on digital system and tries to find solutions to knowledge creation, sharing, transfer, application and further innovation in nuclear industry. This framework utilizes information and digital technology to build top-tier object driven work environment, automatic design and analysis integration platform, digital dynamic performance Verification & Validation (V&V) platform, collaborative manufacture procedure, digital construction platform, online monitoring and configuration management which benefit knowledge management in NPP full life cycle. The suggested framework will strengthen the design basis of the nuclear power plants (NPPs) and will ensure the safety of the NPP design throughout the whole lifetime of the plant.

Evaluation of the integrity and duration of the Laguna Verde nuclear power plant life- Plant Life Management program (PLIM). TC MEX 04/53 Technical Cooperation Project

International Nuclear Information System (INIS)

Arganis J, C.R.; Diaz S, A.; Aguilar T, J.A.

2006-01-01

As part of the IAEA TC MEX 04/53 Project 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Handling Program of plant' whose objective is the one of beginning the actions to apply the methodology of Handling of plant life in the Unit 1 of the Laguna Verde Nucleo electric Central for to obtain the Renovation of License in 2020 the ININ, through the Department of Synthesis and Characterization of materials has carried out more of 20 analysis of susceptibility to the intergranular cracking for corrosion under effort in interns so much of the reactor of the unit 1 like of the unit 2 documenting the current state of components based on the type or types of materials that conform them, to it thermomechanical history, operational and of production, as well as of the particularities associated to its use and operation. For the application of the methodology of life handling of plant 5 structure systems or pilot components were selected, to carry out the programs of handling of the aging and handling of plant life: The encircling of the reactor core (Core Shroud), the reactor pressure vessel (Reactor Pressure Vessel), the primary container (Primary Containment), the recirculation system of feeding water (Reactor Feed Water) and cables. (Author)

Nuclear plant life extension

International Nuclear Information System (INIS)

Negin, C.A.

1989-01-01

The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

Operational data collection and analysis for nuclear plant life extension

International Nuclear Information System (INIS)

DuCharme, A.R.; Berg, R.M.; Bailey, T.L.

1989-01-01

This paper describes initial work undertaken by the US Department of Energy, through Sandia National Laboratories in Albuquerque, New Mexico, to define the operational data necessary for support of nuclear plant life extension (PLEX) programs. This work is being performed in coordination with the Working Group on Plant Life Extension of the US Nuclear Management and Resources Council. The intent of the effort is to use results gained initially from pilot PLEX programs a US BWR and a US PWR to build towards the use of ''PLEX indicators'' by which a plant's readiness for successful life extension can be measured. Another objective of the study was to examine chemistry data in detail to determine how well US plants are collecting, preserving, and trending the chemistry data that is important to PLEX. The methods used to disseminate this data to outside agencies and other utilities were studied. Finally, an analysis was made to determine additional chemistry data needed to support PLEX

Life management for a non replaceable structure: the reactor building

International Nuclear Information System (INIS)

Torres, V.; Francia, L.

1998-01-01

Phase 1 of UNESA N.P.P. Lifetime Management Project identified and ranked important components, relative to plant life management. The list showed the Reactor Containment Structure in the third position, and thirteen concrete structures were among the list top twenty. Since the Reactor Containment Building, together with the Reactor Vessel, is the only non-replaceable plant component, and has a big impact on the plant technical life, there is an increasing interest on understanding its behavior to maintain structural integrity. This paper presents: a) IAEA (International Atomic Energy Agency) Coordinated Research Program experiences and studies. Under this Program, international experts address the most frequent degradation mechanisms affecting the containment building. b) IAEA Aging Management Program adapted to our plants. The paper addresses the aging mechanisms affecting the concrete structures, reinforcing steel and prestress systems as well as the aging management programs and the mitigation and control methods. Finally, this paper presents a new module called STRUCTURES, included in phase 2 of the above mentioned project, which will monitor and document the different aging mechanisms and management programs described in item b) regarding the Reactor Containment Building (concrete liner, post stressing system, anchor elements). This module will also support the Maintenance Rule related practices. (Author)

International Working Group on Life Management of Nuclear Power Plants. (IWG-LMNPP). Regular meeting. Working material. V. 2

International Nuclear Information System (INIS)

1998-01-01

National programs of Hungary, Japan, Korea, Russian Federation, Bulgaria, Slovenia, Sweden, Switzerland, Ukraine, United Kingdom and USA, related to nuclear power plants life management presented at the Technical Committee Meeting are published in this volume. The main features of the reports are oriented towards extension of NPP lifetime and conditions indispensable to achieve in order to fulfil the safety requirements including testing the mechanical properties of relevant reactor components

A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

2000-01-01

Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

Maintenance related to life management: Survey and control of equipment ageing

International Nuclear Information System (INIS)

Hevia Ruperez, F.

2000-01-01

The aim of this paper is to review relevant objectives and aspects of the Maintenance Evaluation and Improvement Programmes for Nuclear Power Plant Life Management. Recent experience shows that current maintenance practice often fails to directly address long-term degradation that affects singular plant components and equipment populations. Instead, delayed attention to the consequences makes good Life Management unfeasible. This has brought about the need for specific Maintenance Evaluation and Improvement Programmes to adjust to the basic objective of Life Management which is to protect against, mitigate and/or monitor ageing that affects the safe, profitable life of the facility. The paper analyses the methodologies used, incidents during their application and the main conclusions reached from the implementation of these programmes in Spanish nuclear power plants. Special attention is paid to recommended solutions for improving the efficiency of the utility's contributions, its leadership in task development and integration, and its interfaces with organisations specialised in providing services that support Life Management Programmes. The coexistence of these and other similar maintenance programmes make it necessary to integrate tasks to optimise effort and tools. The paper analyses the guidelines to be considered when integrating these Programmes with other maintenance optimisation programmes (economy and feasibility, RCM) and with tasks derived from the application of Maintenance Rule regulatory requirements. Lastly, the paper reports on the state of these Maintenance Evaluation and Improvement Programmes, their development, what prospects they have, and the Industry's initiative and actions concerning the matter. (author)

IAEA activities on steam generator life management

International Nuclear Information System (INIS)

Gueorguiev, B.; Lyssakov, V.; Trampus, P.

2002-01-01

The International Atomic Energy Agency (IAEA) carries out a set of activities in the field of Nuclear Power Plant (NPP) life management. Main activities within this area are implemented through the Technical Working Group on Life Management of NPPs, and mostly concentrated on studies of understanding mechanisms of degradation and their monitoring, optimisation of maintenance management, economic aspects, proven practices of and approaches to plant life management including decommissioning. The paper covers two ongoing activities related to steam generator life management: the International Database on NPP Steam Generators and the Co-ordinated Research Project on Verification of WWER Steam Generator Tube Integrity (WWER is the Russian designed PWR). The lifetime assessment of main components relies on an ability to assess their condition and predict future degradation trends, which to a large extent is dependent on the availability of relevant data. Effective management of ageing and degradation processes requires a large amount of data. Several years ago the IAEA started to work on the International Database on NPP Life Management. This is a multi-module database consisting of modules such as reactor pressure vessels materials, piping, steam generators, and concrete structures. At present the work on pressure vessel materials, on piping as well as on steam generator is completed. The paper will present the concept and structure of the steam generator module of the database. In countries operating WWER NPPs, there are big differences in the eddy current inspection strategy and practice as well as in the approach to steam generator heat exchanger tube structural integrity assessment. Responding to the need for a co-ordinated research to compare eddy current testing results with destructive testing using pulled out tubes from WWER steam generators, the IAEA launched this project. The main objectives of the project are to summarise the operating experiences of WWER

NPP life management program - status report for Slovenia

International Nuclear Information System (INIS)

Glumac, B.

1998-01-01

Status report on NPP life management in Slovenia is dealing with possible life extension of NPP Krsko which comprises: replacement of steam generator; power upgrade; exchange of plant process computer; snubber reduction program, additional forced ventilation cooling system. Fuel improvements are predicted as well as the problems of storing spent fuel, low and intermediate waste if the plant is to operate through 2023 and possibly beyond that date. Related research activities are concerned with radiation damage, modelling of reactor core parameters by Monte Carlo calculations and PSA and severe accidents studies. Most of the activities are performed in cooperation with foreign organisations

Fracture mechanics based life assessment in petrochemical plants

International Nuclear Information System (INIS)

Norasiah Ab Kasim; Abd Nassir Ibrahim; Ab Razak Hamzah; Shukri Mohd

2004-01-01

The increasing use of thick walled pressure vessels in petrochemical plants operating at high pressure under severe service conditions could lead to catastrophic failure. In the Malaysian Institute for Nuclear Technology Research (MINT), initial efforts are underway to apply fracture mechanics approach for assessment of significance of defects detected during periodic in service inspection (ISI) of industrial plants. This paper outlines the integrity management strategy based on fracture mechanics and proposes a new procedure for life assessment of petrochemical plants based on ASME Boiler and Pressure Vessel Code, Section XI, BSI PD 6493:1991, BSI 6539:1994, BSI Standard 7910:1999 and API 579:2000. Essential relevant data required for the assessment is listed. Several methods available for determination of fracture toughness are reviewed with limitations in their application to petrochemical plants. A new non destructive method for determination of fracture toughness based on hardness testing and normalized key roughness curve is given. Results of fracture mechanics based life assessment conducted for 100 mm thick ammonia converter of Ni r o steel and 70 mm thick plat forming reactor vessel of ASTM A 38 7 grade B steel in operational fertilizer and petroleum refining plants are presented. (Author)

Brain surgery breathes new life into aging plants

Energy Technology Data Exchange (ETDEWEB)

Makansi, J. [Pearl Street Inc. (United States)

2006-04-15

Unlike managing the human aging process, extending the life of a power plant often includes brain surgery, modernizing its control and automation system. Lately, such retrofits range from wholesale replacing of existing controls to the addition of specific control elements that help optimize performance. Pending revisions to safety codes and cybersecurity issues also need to be considered. 4 figs.

Aging and lifetime management - A plant-wide concept and examples for realization

International Nuclear Information System (INIS)

Erve, M.

1998-01-01

It is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. 'Aging' in this context is understood to mean the change over time of the service-related characteristics and properties of the following nuclear power plant items: the equipment (mechanical components, structures, electrical and I and C systems); the computer systems (hardware and software) required for plant operation; the plant specifications and documentation. From this it is obvious that a competent strategy for aging and plant life management must cover all key-components relevant for safety and availability of the plant. Besides mechanical components, instrumentation and control devices, and civil engineering structures are to be considered, regarding both aspects, function and integrity. 'Aging and plant life management' encompasses all organizational and technical measures with which aging phenomena are recognized and managed by the plant operator, and which thereby guarantee full utilization of a component or system over its entire service life, or which must be taken at the proper time to extend service life and guarantee long-term plant integrity. An adequate strategy follows for taking measures to avoid detrimental effects on lifetime. Preventive measures can be the change of operation modes to suppress rigid degradation, the change of operating parameters or system engineering methods to optimize the operation of systems and components, and the replacement of aged component parts, components, or systems by new ones, made with an improved design or representing an advanced technique. The strategy is challenging: the improvement of availability by optimizing the outage times and the operation; the increase of safety and reliability; the reduction of man-rem exposure and costs for waste management and amount of waste; the optimized early

Life cycle management at Ontario Power Generation

International Nuclear Information System (INIS)

Spekkens, P.

2006-01-01

This paper outlines the Life Cycle Management (LCM) program at Ontario Power Generation. LCM is carried out at different levels that includes components, systems, unit and fleet. A system involves cumulative effect of individual component aging. These components include steam generators, pressure tubes and feeders. A unit involves an overall unit aging strategy integrating all systems. At the fleet level, there is an optimal strategy for plant-level investments including end-of-life of a unit

Life Management and Safety of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

2014-10-15

The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

Life cycle management of service water systems

International Nuclear Information System (INIS)

Egan, Geoffrey R.; Besuner, Philip M.; Mahajan, Sat P.

2004-01-01

As nuclear plants age, more attention must focus on age and time dependent degradation mechanisms such as corrosion, erosion, fatigue, etc. These degradation mechanisms can best be managed by developing a life cycle management plan which integrates past historical data, current conditions and future performance needs. In this paper we present two examples of life cycle management. In the first example, the 20-year maintenance history of a sea water cooling system (cement-lined, cast iron) is reviewed to develop attributes like maintenance cost, spare part inventory, corrosion, and repair data. Based on this information, the future expected damage rate was forecast. The cost of managing the future damage was compared with the cost to replace (in kind and with upgraded materials. A decision optimization scheme was developed to choose the least cost option from: a) Run as-is and repair; b) replace in kind; or c) replace with upgraded material and better design. In the second example, life cycle management techniques were developed for a ceilcote lined steel pipe cooling water system. Screens (fixed and traveling), filters, pumps, motors, valves, and piping were evaluated. (author)

Non-destructive testing for plant life assessment

International Nuclear Information System (INIS)

2005-01-01

expectation of components, facilities and products is feasible. NDT technology for remaining life assessment of industrial equipment and engineering structures is already established in routine service mostly in developed countries. The NDT inspection of concrete structures and civil engineering constructions is another subject in development with much interest for developing Member States. There is a need for training material, which will assist developing Member States in formation and continuous training and education of their NDT specialists. The training course document on NDT applications provides basic information on NDT technology as applied for plant life assessment and concrete structures. It describes principles and practical aspects of major NDT methods. It contains useful information about the quality control and accreditation in NDT work according to ISO standards. This training textbook can be used as additional technical document for further qualification of NDT specialists and as basic material for information of managers and decision makers of industry on NDT prospects. It helps in transferring NDT technology to developing Member States

Aging management guideline for commercial nuclear power plants-pumps

International Nuclear Information System (INIS)

Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D.

1994-03-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging management guideline for commercial nuclear power plants-pumps

Energy Technology Data Exchange (ETDEWEB)

Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D. [MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

Aging management guideline for commercial nuclear power plants - heat exchangers

International Nuclear Information System (INIS)

Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

1994-06-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging management guideline for commercial nuclear power plants - heat exchangers

Energy Technology Data Exchange (ETDEWEB)

Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

1994-06-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

International Working Group on Life Management of Nuclear Power Plants. (IWG-LMNPP). Regular meeting. Working material. V. 1

International Nuclear Information System (INIS)

1998-01-01

National programs of Argentina, Brazil, Belgium, Czech Republic, Canada, France and Germany related to nuclear power plants life management presented at the Technical Committee Meeting are published in this volume. Finnish report VTT-TIED-1843 included in this volume was already included separately in the INIS Database. The main features of the reports are oriented towards extension of NPP lifetime and conditions indispensable to achieve in order to fulfil the safety requirements including testing the mechanical properties of relevant reactor components

Managing Daily Life

Science.gov (United States)

... Duchenne / Managing Daily Life Print Email Managing Daily Life Environmental accessibility As the person with Duchenne starts ... such as wider doorways and ramps, can make life easier once the person with Duchenne cannot climb ...

IAEA effort on the evaluation and management of safety aspects of nuclear power plant ageing

International Nuclear Information System (INIS)

Pachner, J.; Yaremy, E.M.

1991-01-01

The questions attached to nuclear power plant (NPP) ageing and the need for monitoring and assessment of plant condition will grow in importance as more NPPs approach and pass the end of their nominal design lives. Ageing in nuclear plants must be effectively managed to ensure plant safety during their entire service life. This paper provides an overview of the IAEA programme and its results on the evaluation and management of safety aspects of NPP ageing. Under this programme, three generic guidance documents have been prepared on: data collection and record keeping; ageing management methodology; and the use of probabilistic safety assessment in plant life extension considerations. A two pronged strategy involving both technical and regulatory aspects has been adopted for the current and future work. (author)

An introduction to a new IAEA safety guide: 'ageing management for nuclear power plants'

International Nuclear Information System (INIS)

Pachner, J.; Inagaki, T.; Kang, K.S.

2008-01-01

This paper reports on a new IAEA Safety Guide entitled 'Ageing Management for Nuclear Power Plants' which is currently in an advanced draft form, awaiting approval of publication. The new Safety Guide will be an umbrella document for a comprehensive set of guidance documents on ageing management which have been issued by the IAEA. The Safety Guide first presents basic concepts of ageing management as a common basis for the recommendations on: proactive management of ageing throughout the life cycle of a nuclear power plant (NPP); systematic approach to managing ageing in the operation of NPPs; managing obsolescence; and review of ageing management for long term operation (life extension). The Safety Guide is intended to assist operators in establishing, implementing and improving systematic ageing management programs in NPPs and may be used by regulators in preparing regulatory standards and guides, and in verifying that ageing in nuclear power plants is being effectively managed. (author)

The iPlant Collaborative: Cyberinfrastructure for Enabling Data to Discovery for the Life Sciences.

Science.gov (United States)

Merchant, Nirav; Lyons, Eric; Goff, Stephen; Vaughn, Matthew; Ware, Doreen; Micklos, David; Antin, Parker

2016-01-01

The iPlant Collaborative provides life science research communities access to comprehensive, scalable, and cohesive computational infrastructure for data management; identity management; collaboration tools; and cloud, high-performance, high-throughput computing. iPlant provides training, learning material, and best practice resources to help all researchers make the best use of their data, expand their computational skill set, and effectively manage their data and computation when working as distributed teams. iPlant's platform permits researchers to easily deposit and share their data and deploy new computational tools and analysis workflows, allowing the broader community to easily use and reuse those data and computational analyses.

Research projects on life management: materials ageing

International Nuclear Information System (INIS)

Gomez Briceno, D.

1997-01-01

Materials ageing is a time-dependent process, that involves the loss of availability of nuclear plants. Radiation embrittlement, stress corrosion cracking, irradiation assisted stress corrosion cracking, and thermal ageing are the most relevant time-dependent material degradation mechanisms that can be identified in the materials ageing process. The Materials Programme of Nuclear Energy Institute at CIEMAT carries out research projects and metallurgical examinations of failed components to gain some insight into the mechanisms of materials degradation with a direct impact on the life management of nuclear plants. (Author)

24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 1. Papers 1-27

International Nuclear Information System (INIS)

1999-01-01

The first volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The main topic in the volume is the contribution of nondestructive testing to the reactor safety from an international point of view. All 20 papers are separately analyzed for this database. (orig.)

Aging management guideline for commercial nuclear power plants-stationary batteries

International Nuclear Information System (INIS)

Berg, R.; Shao, J.; Krencicki, G.; Giachetti, R.

1994-03-01

The Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant stationary batteries important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Aging Management Guideline for commercial nuclear power plants: Electrical switchgear

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.; Schuler, K.

1993-07-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

On the implementation of activities for the life management of nuclear power plants in Brazil

International Nuclear Information System (INIS)

Di Lorenzo, R.F.; Mansur, T.R.; Moreira, R.M.; Quinan, M.A.; Rocha, Z.; Soares, W.A.; Tofani, P.C.

1998-01-01

Brazil joined the IAEA IWG-LMNPP in 1993, in view of a potential interest in the LMNPP subject. In this report, aspects of nuclear activities, as well as activities related to LMNPP, are reviewed. The nuclear energy scenario is presented with emphasis on the nuclear share of the total electrical energy supply and on the nuclear sector organization. Angra Nuclear Power Plant units are presented and some construction and/or operational features are discussed. Concerning the activities on LMNPP, the contribution of different nuclear sector organizations is briefly considered. Some aspects are stressed with regard to an integrated approach of LMNPP and the country's available manpower and technical infrastructure capabilities in the nuclear field. The technical assistance of the IAEA in the area of plant life management if focused. From the experience of this first phase (1993-97) representing Brazil in the IWG-LMNPP, special aspects are emphasized aiming, on the basis of their consideration, at improving the efficiency of this process. The implementation of a Brazilian network, the BRWG-LMNPP, is underway, formulating plans for the future. (author)

Steam generator life cycle management challenges - on-going and new build

International Nuclear Information System (INIS)

Spekkens, P.

2009-01-01

Ontario Power Generation (OPG) is committed to the safe, reliable, and cost-effective operation of its fleet of CANDU plants. Steam Generators (SGs) are a major component of the heat transport system in these plants and maintaining their health is an essential element to achieving plant safety, reliability and economic performance. OPG has been actively engaged in formal life cycle management of its SGs for about 15 years. Over this time, we have developed stable, mature, detailed life cycle plans for each of our plants on a unit by unit, and in some cases, SG by SG, basis. These plans have been externally reviewed over the years by our regulator and by other third-party experts, and they've been acknowledged as being among the best life cycle plans anywhere. Although we are pleased that our life cycle plans are as detailed and mature as they are, we certainly aren't fully satisfied because they're not perfect. Even if they were perfect at any point in time, they wouldn't be for very long because the environment is constantly changing, both the technical environment and the business environment. This paper presents some of these challenges and offers some possible solutions or suggestions based on OPG's experience. The paper describes the background on SG life cycle management in OPG, i.e. what it is and how we do it. Then it presents challenges in the following areas: despite having some very detailed and technically strong life cycle plans, we still face some technical issues; in addition, we face challenges in integrating these plans into the overall business processes within the company; up until now, our life cycle planning has been aimed at early-and mid-life in our units. But our units are aging and we are now within sight, at least in a life cycle management sense, of a point at which decisions need to be made on refurbishment, life extension or retirement of the units. We need to adjust our life cycle management approach as we approach those major

Life extension for fossil power plants: The EPRI [Electric Power Research Institute] strategy

International Nuclear Information System (INIS)

Byron, J.; Dooley, B.

1988-01-01

Fossil fuel-fired generating plants have traditionally been built under the assumption of an economic life of 20-30 years. Due to low load growth, escalating interest rates and costs of construction, and increasing regulation, great interest is expressed in retaining these units in service for 50-60 years or longer. Life extension activities are part of an ongoing process that continues throughout the extended lives of a utility's units. The process begins with an initial evaluation of life extension as a generation alternative, resulting in a ranking of units for life extension and a prioritization of components for evaluation. As the process continues, more detailed inspection data are created by a three-level approach, as well as a means for collecting, organizing and scheduling the information. This is implemented through the Integrated Life Extension Management (ILEM) model. This model provides information needed for management decision making such as component performance on unit power rating, availability of components on unit availability, component performance on unit availability and overall costs of the life extension tasks. Risks involved in life extension include the initial unavailability of capacity credits, uncertainty as to the level of availability that can be achieved by the life-extended plant, and uncertainties in environmental compliance. 8 refs., 1 fig., 2 tabs

Reactor pressure vessel and reactor coolant circuit cast duplex stainless steel components contribution of the expertise for life management studies

International Nuclear Information System (INIS)

Bezdikian, Georges

2006-09-01

The life management of French Nuclear Power Plants is a major stake from an economic and a technical point of view considering the aging management assessment of the key components of the plant. The actual life evaluation is the result of prediction of life assessment from important program of expertise for the 3-loop PWR and 4-loop PWR plants in operation. To optimize the strategic policy in order to achieve the best possible performance and to prepare the technical and economical choice and decision, the paper presents the association of life management strategy and the program of expertise considering: - the identification of degradation for different components and prediction criteria proposed; - the large database from cast reactor coolant and component removed from nuclear power plants and expertise studies to confirm the prediction; - the life evaluation of RPV with radiation surveillance program based on the expertise of irradiation capsules, it is particularly shown how the expertise is in the center of the strategic choice. The French utility has organized the life management of nuclear plant as a function of several programs of expertise of knowledge on the long term experience feedback and the maintenance program for life. This paper shows updated on RPV and reactor coolant equipment activities engaged by utility on: - periodic maintenance and volume of expertise; - Alternative maintenance actions; - Large volume of expertise and how are managed these results to predict the aging management. (author)

The iPlant Collaborative: Cyberinfrastructure for Enabling Data to Discovery for the Life Sciences.

Directory of Open Access Journals (Sweden)

Nirav Merchant

2016-01-01

Full Text Available The iPlant Collaborative provides life science research communities access to comprehensive, scalable, and cohesive computational infrastructure for data management; identity management; collaboration tools; and cloud, high-performance, high-throughput computing. iPlant provides training, learning material, and best practice resources to help all researchers make the best use of their data, expand their computational skill set, and effectively manage their data and computation when working as distributed teams. iPlant's platform permits researchers to easily deposit and share their data and deploy new computational tools and analysis workflows, allowing the broader community to easily use and reuse those data and computational analyses.

NULIFE - the European NoE 'Nuclear Plant Life Prediction'

International Nuclear Information System (INIS)

Cojan, Mihail

2008-01-01

INR Pitesti become on the 29th September 2006 a partner in the European Network of Excellence Nuclear Plant Life Prediction (NULIFE) coordinated by Technical Research Centre of Finland (VTT). The EU's Network of Excellence NULIFE has been launched under the EURATOM FP6 Program with a clear focus on integrating safety-oriented research on materials, structures and systems and exploiting the results of this integration through the production of harmonized lifetime assessment methods. NULIFE will help provide a better common understanding of, and information on, the factors affecting the lifetime of nuclear power plants which, together with associated management methods, will help facilitate extensions to the safe and economic lifetime of existing nuclear power plants. (author)

Nutritional and cultural aspects of plant species selection for a controlled ecological life support system

Science.gov (United States)

Hoff, J. E.; Howe, J. M.; Mitchell, C. A.

1982-01-01

The feasibility of using higher plants in a controlled ecological life support system is discussed. Aspects of this system considered important in the use of higher plants include: limited energy, space, and mass, and problems relating to cultivation and management of plants, food processing, the psychological impact of vegetarian diets, and plant propagation. A total of 115 higher plant species are compared based on 21 selection criteria.

Plant life management strategies for pressurized heavy water reactors

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Suk; Kwon, Sang Chul; Choo, Ki Nam; Ahn, Sang Bok; Kuk, Il Hyun [Korea Atomic Energy Research Institute, Taejon (Korea)

1998-06-01

This technical report reviewed aging mechanism of the major components of CANDU 6 reactor such as pressure tubes, calandria tube, end fitting, fuel channel spacer and calandria. Furthermore, the surveillance methodology was described for monitoring and inspection of these core components. Based on the in-reactor performances data such as delayed hydride cracking, leak-before-break, enhanced deformation-creep and growth, the life management of pressure tubes was illustrated in this report. (author). 19 refs., 11 figs., 2 tabs.

International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 2

International Nuclear Information System (INIS)

1995-01-01

This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 1

International Nuclear Information System (INIS)

1995-01-01

This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

Management of age-related degradation for nuclear power plants

International Nuclear Information System (INIS)

Gregor, Frank E.

2004-01-01

Life extension for nuclear power plants has been studied in the USA for the last six years, largely supported by EPRI, DOE and the USNRC. Though there are diverse opinions for the strategies and priorities of life extension and aging management, one common conclusion has been formulated regarding the need of current maintenance programs having to focus on aging and degradation management. Such program, called 'Maintenance Effectiveness Evaluation and Enhancement' or M3E for short, has been developed to assist plant operators to upgrade and enhance existing programs by integrating aging/degradation management activities for important or critical equipment and components. The key elements of the M3E program consist of the definition and selection of the critical components or commodities to be included in the scope, the survey/inventory of the current programs and their respective action steps, frequencies, corrective measures and extent of coverage, the component/commodity degradation mechanism, sites and severity, safety functions and service environments and lastly, the correlation of degradation/aging with the individual maintenance activities. The degree of correlation provides a measure of effectiveness and the opportunity to identify/specify needed enhancements, abandonment or generation of new maintenance activities. Implementation of the activities can then be prioritized at the option of the plant staff. (author)

Steam generator maintenance and life management at Embalse Nuclear Station

International Nuclear Information System (INIS)

Sainz, R.; Diaz, G.; Sveruga, H.; Ramakrishnan, T.K.; Azeez, S.

2004-01-01

The Embalse Nuclear Station has four steam generators (SGs) with inverted vertical U tubes manufactured by Babcock and Wilcox Canada (B and W). These are main components, both from the operative point of view as the heat transfer from the Primary Heat Transport System (PHTS) to the Secondary System, and from the point of view of safety, as they are the part of the PHTS and its radioactive inventory pressure barrier. In addition, they are one of the most important cost-related elements for potential life extensions. Maintenance and inspections are carried out in order to maintain a high availability of the SGs, as they have had a positive impact on the operational availability of the plant, and to reduce the tube failure probabilities, thus minimizing the amount of radioactive effluents and taking care of the condition of the main components in order to enable the plant life management and the planning of the plant life extension. The most relevant maintenance activities performed have been the inspections performed on 100% of the tubes every 3 years. the mechanical cleaning of the inside of the tubes, the sludge removal from the secondary side tubesheet, the divider plate replacement, and the inspection of internals of the secondary side.Thanks to the latter and to the eddy current inspections, the degradation in the U-bend supports was detected early and every effort is being made to repair them shortly. Besides, a life management program has been started covering the entire plant starting with this important component. The Embalse Nuclear Station's SGs show a low percentage of plugged tubes compared to other stations in similar conditions, but they must be monitored continually and systematically if a life extension is intended. (author)

LWR power plants lifetime management strategies. The Spanish approach

International Nuclear Information System (INIS)

Francia, Lorenzo; Carmena, Pio; Gomez Santamaria, Jesus; Regano, Martin; Marcelles, Ignacio

2002-01-01

During the last years, Spanish nuclear power plant (NPP) owners are increasingly concerned with optimising Plant Life Management. As a result of this interest, they are setting up Lifetime Management Programmes with the strategic objective to operate the NPPs beyond 40 years. In addition, a close link exists between life management work and improved maintenance practices concerning strategic, economic and safety aspects of NPP. As results of these important considerations, utilities will increase and globalise programmes for monitoring and mitigation of ageing. The afore mentioned programmes are based on knowledge of the precise condition of all components with the greatest effect on the economics and safety of the plant, and trends in their condition. The technical support for these programmes is: Methodologies and knowledge required identifying degradation mechanisms as a function of the characteristics of the components and operating conditions; Techniques for determining condition and trends; Analysis of the maintenance practices efficiency based on the above knowledge, techniques and methodologies; Improvement of maintenance practices for adequate mitigation and monitoring of ageing; Techniques and tools for collecting and ordering data about ageing and for condition assessment. Spanish NPPs have developed, under UNESA coordination, a standard methodology for lifetime management of LWRs. The methodology consists in the following main steps: Define with high accuracy the priorities and scope of the Life Management Programme. In this first step, plant systems, structures and components, important for lifetime management of LWRs, are selected and prioritised using a methodology based on screening criteria. The LCM Programme begins with an initial condition evaluation, which serves as the basis for establishing the main corrective and monitoring actions, and for preparing the first cost/benefit analyses for Life Management. The LCM Programme continues to progress

The System 80+ Standard Plant Information Management System

Energy Technology Data Exchange (ETDEWEB)

Turk, R.S.; Bryan, R.E. [ABB Combuions Engineering Nuclear Systems (United States)

1998-07-01

Historically, electric nuclear power plant owners, following the completion of construction and startup, have been left with a mountain of hard-copy documents and drawings. Hundreds of thousands of hours are spent searching for relevant documents and, in most cases, the documents found require many other documents and drawings to fully understand the design basis. All too often the information is incomplete, and eventually becomes obsolete. In the U.S., utilities spend millions of dollars to discover design basis information and update as-built data for each plant. This information must then be stored in an easily accessed usable form to assist satisfy regulatory requirements and to improve plant operating efficiency. ABB Combustion Engineering Nuclear Systems (ABB-CE) has an active program to develop a state-of-the-art Plant Information Management System (IMS) for its advanced light water reactor, the System 80+TM Standard Plant Design. This program is supported by ABB's Product Data Management (PDM) and Computer Aided Engineering (CAE) efforts world wide. This paper describes the System 80+ plant IMS and how it will be used during the entire life cycle of the plant. (author)

The System 80+ Standard Plant Information Management System

International Nuclear Information System (INIS)

Turk, R.S.; Bryan, R.E.

1998-01-01

Historically, electric nuclear power plant owners, following the completion of construction and startup, have been left with a mountain of hard-copy documents and drawings. Hundreds of thousands of hours are spent searching for relevant documents and, in most cases, the documents found require many other documents and drawings to fully understand the design basis. All too often the information is incomplete, and eventually becomes obsolete. In the U.S., utilities spend millions of dollars to discover design basis information and update as-built data for each plant. This information must then be stored in an easily accessed usable form to assist satisfy regulatory requirements and to improve plant operating efficiency. ABB Combustion Engineering Nuclear Systems (ABB-CE) has an active program to develop a state-of-the-art Plant Information Management System (IMS) for its advanced light water reactor, the System 80+TM Standard Plant Design. This program is supported by ABB's Product Data Management (PDM) and Computer Aided Engineering (CAE) efforts world wide. This paper describes the System 80+ plant IMS and how it will be used during the entire life cycle of the plant. (author)

Solvent management in a reprocessing plant

International Nuclear Information System (INIS)

Guillaume, B.; Germain, M.; Puyou, M.; Rouyer, H.

1987-01-01

Solvent management in large capacity reprocessing plant is studied to limit production of organic wastes. Chemical processing increases life time of solvent. Low pressure distillation allows the recycling of TBP and diluent at a low activity level. Besides heavy degradation products are eliminated. For the safety the flash point of distillated diluent increases slightly. Tests on an industrial scale started in 1985 and since more than 500 cubic meters were treated [fr

Cost drivers for the assessment of nuclear power plant life extension

International Nuclear Information System (INIS)

2002-09-01

In the period of the nineteen-sixties to eighties, nuclear power had rapidly expanded in many countries of the world. The nuclear power plants built in this period, will reach the end of their planned life in the near future. Statistics drawn from IAEA's Power Reactor Information System (PRIS) indicate that, by the end of 2001, there were 175 nuclear power units (NPPs) with about 122 GWe of net electrical capacity, having 21 to 45 years of operation. This represents about 34% of the total installed nuclear capacity in the world. Since these plants were initially designed for 30-40 years of operation, utilities operating such NPPs will now have to consider whether they will shutdown, decommission, and replace the plants reaching the end of their planned life, or refurbish the plants and extend their original design life. This decision is quite complex, involving a number of political, technical and economic issues. Finally, the utilities involved should manage their assets in a manner that is as close as practicable to the best possible economic optimum scenario. Well before the end of the plant life, NPP operators must evaluate the technical and economic feasibility for PLEX options, seek and obtain regulatory approvals, and implement PLEX schemes that are justified. Often they also have to substantiate the planned life extension, including the economic viability to the relevant governmental bodies, as well as to assure the general public acceptance. Economic feasibility analysis requires cost data that are not readily available. A recent IAEA review of published information on costs of PLEX revealed the scarcity of published information, while the estimated costs of NPP decommissioning are widely available. This is due in part to the reluctance by NPP operators to divulge the cost data that are considered commercial/confidential, as more plant operators are being privatised, and in part to the absence of a common framework and methodology to account for the

A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

2001-01-01

Fundamental concepts on the life extension of the nuclear power plant and decommissioning optimization were established from the domestic abroad information and case analyses. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the standard of the decommissioning(decontamination dismantling) regulation. Moreover, basics were set for the decommissioning of domestic nuclear power plants and research reactors from the analyses on the decommissioning technology and precedence.

Plant life (PLIM) and ageing management (AM) in German NPPs. Prerequisite for long term operation (LTO)

International Nuclear Information System (INIS)

Schuler, X.

2010-01-01

dependant) or based on monitoring of relevant parameters (predictive). The results of these procedures are assessed for each SSC, specifically. For both groups of SSC, in addition to the control of (known) damage mechanisms, all significant plant data (e.g. reports of failures, work orders) and the reports from other plants (incl. exchange of knowledge) are assessed regularly in order to be prepared for new damage mechanisms (and to prevent / control them consequently). This is performed by an appropriate software approach. Within this SSC-specific assessment the entity of measures to control degradation effects is reviewed and modified / extended, if necessary. On the basis of good experiences with the AM procedure and driven by the latest political development (nuclear power is an option in energy supply again) the utilities are re-structuring their plant life management (PLIM), actually. PLIM addresses both safety and economical aspects. Consequently, all SSC of a plant and every possible degradation mechanism have to be considered within PLIM - besides other more not-technical aspects. AM is part of the plant life management. Regarding technical equipment, the PLIM procedure is similar to that established in AM. Depending on the requirements it is necessary to - establish quality during design and manufacture - safeguard this quality in operation by appropriate measures - assess procedure / measures and existing quality, regularly. Living an effective PLIM procedure the utilities are kept on the state of the art; on this basis energy production can be safe and economic at any time. This is an essential prerequisite for long term operation (LTO). (orig.)

Aging Management Guideline for commercial nuclear power plants: Motor control centers

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.; O'Hearn, E.

1994-02-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

Near-term benefits of the plant life extension program

International Nuclear Information System (INIS)

Kaushansky, M.M.

1987-01-01

The aging process can be expected to reduce the availability and increase the production costs of nuclear power plants over time. To mitigate this process and recover or enhance plant availability, capacity, thermal efficiency, and maintenance expenditures, the utility must dedicate increased attention and commitment to a comprehensive plant life extension (PLEX) program. Improvements must be justified by balancing the cost of the recommended modifications with the economic value of benefits obtained from its implementation. It is often extremely difficult for utility management to make an optimal selection from among hundreds of proposed projects, most of which are cost-effective. A properly structured PLEX program with an emphasis on near-term benefits should provide the utility with a means of evaluating proposed projects, thus determining the optimum combination for authorization and implementation

Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

International Nuclear Information System (INIS)

Wang Dalin; Sun Jinlong

2012-01-01

Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (author)

Update on the status of life extension in U.S. Nuclear Power Plants

International Nuclear Information System (INIS)

Hevia Ruperez, F.; Lehnert, D.F.; Gregor, F.E.

1997-01-01

The purpose of this paper is to provide an update on the status of key activities that may affect the plant life extension option for U.S. nuclear power plants and to explain how the progress on the regulatory and technical developments may affect the world-wide nuclear industry. Establishing a predictable and stable regulatory process is the final piece that is needed by U.S. utilities to confidently consider the plant life extension option in their strategic planning. Certain technical issues were also identified in the previous studies where additional investigation would benedict the U.S. nuclear power industry's understanding of an aging effect and/or capability to demonstrate that the aging effect can be effectively managed. It is concluded that the lessons learned from the U.S. industry activities and the associated interactions with the NRC are leading to a positive indication that U.S. utilities believe the differences between the NRC and industry on the implementation of the amended license renewal rule can be successfully resolved and the that many utilities generally are interested in pursuing the life extension option as part of their strategic planning. The methodology and guidance developed in the U.S. for performing integrated plant assessments and evaluating time-limited aging analyses will be of significant interest to utilities and regulators in other countries. They will undoubtedly lay the foundation for an acceptable approach for demonstrating that aging processes are being processes are being effectively managed by plant programs and that safety margins or bases will be maintained during an extended operating period. (Author)

At-reactor storage of spent fuel for life-of-plant

International Nuclear Information System (INIS)

Fuierer, A.A.

1990-01-01

The management of commercial spent fuel is a fairly broad topic beginning with the discharge from a reactor, its storage on-site, its transport from the reactor site to a U.S. Department of Energy (DOE) facility, and its ultimate disposal in a geologic repository. This paper discusses spent-fuel management in the at-reactor phase. There are two basic methods for at-reactor storage of spent fuel. The first is wet storage in a pool, and the second is dry storage external to the plant in some form of cask or vault. Spent-fuel consolidation will impact the utility and the DOE waste system. Some of these impacts have a positive effect and some have a negative effect, and each will vary somewhat for each utility. Spent-fuel consolidation and life-of-plant storage will be an increased burden to utilities but will likely result in significant cost savings to the overall waste management system and by proper integration can result in significant institutional benefits

Aging management and life extension - Containment aging study

International Nuclear Information System (INIS)

Tai, Tom M.; Deng, Daniel

2004-01-01

Bechtel is currently completing an aging study on a concrete containment structure. The target plant is a two-unit PWR plant with a generating capacity of about 850 MWe from each unit. Both units are less than 20 years old. The total electrical energy output from this plant site accounts for more than 50% of the utility's baseload operation. Although no utility in the United States has made a decision to submit a license renewal application, some have begun to investigate the feasibility of developing an life cycle management (LCM) program for a strategy to operate their plants efficiently, to investigate the financial benefit and safety implications of license renewal to operate their nuclear power plants beyond their current licensed periods, and to prepare a program plan for plant decommissioning. The LCM program includes economic, environmental, regulatory and technical aspects of continuing plant operations beyond the current license period. The Electric Power Research Institute (EPRI) has been supportive to assist utilities and owners groups in their research and development efforts to develop the technical requirements and the issues associated with important to license renewal structures. The focus of this paper is on the technical issues related to the evaluation of the material condition of the containment structure with respect to aging and the effective management of that aging. (author)

Life cycle management. Condition monitoring of wind power plants; Life-cycle-management. Zustandsueberwachung von Windenergieanlagen

Energy Technology Data Exchange (ETDEWEB)

Wolff, R. [cmc GmbH, Kiel (Germany)

2013-06-01

The author of the contribution under consideration reports on maintenance strategies and condition monitoring in the field of wind energy. Beside the components in the drive train of wind turbines under consideration, the condition monitoring of the hardware systems and their software is explained. A brief overview of the field of machinery diagnosis and an explanation of the transmission of the measured data follow. Additional sensors such as sensors for the rotor blade monitoring, oil particles counter or oil quality sensors are described. In the field of diagnostic certainty, special follow-up studies such as video endoscopy, analysis of oil or grease, filter testing and material testing are discussed. The information from these thematic fields is used in the life-cycle management database for operationally relevant evaluations and considerations of economy of condition monitoring systems.

Aging Management Guideline for commercial nuclear power plants: Power and distribution transformers

International Nuclear Information System (INIS)

Toman, G.; Gazdzinski, R.

1994-05-01

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

NDE and plant life extension

International Nuclear Information System (INIS)

Liu, S.N.; Ammirato, F.V.; Nottingham, L.D.

1991-01-01

Component life extension is the process of making run-repair-replace decisions for plant components and includes a thorough analysis of the capability of the component to perform throughout the projected lifetime. For many critical plant components, nondestructive evaluation (NDE) is essential in determining whether the component can be operated safely and economically in the extended life period and to help utilities determine safe and economic inspection intervals. NDE technology is required for not only detecting defects that could grow to a size of concern during extended lifetimes, but also will be called upon to measure and monitor accumulating material degradation that strongly affects component reliability. This paper discusses the role of NDE in life extension by reviewing three examples--a reactor pressure vessel, steam turbine-generator rotors, and generator retaining rings. In each example, the contribution of NDE to life extension decisions is described. (author)

Aging management guideline for commercial nuclear power plants - tanks and pools

International Nuclear Information System (INIS)

Blocker, E.; Smith, S.; Philpot, L.; Conley, J.

1996-02-01

Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities

Aging management guideline for commercial nuclear power plants - tanks and pools

Energy Technology Data Exchange (ETDEWEB)

Blocker, E.; Smith, S.; Philpot, L.; Conley, J.

1996-02-01

Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities.

Nuclear plant life cycle costs

International Nuclear Information System (INIS)

Durante, R.W.

1994-01-01

Life cycle costs of nuclear power plants in the United States are discussed. The author argues that these costs have been mishandled or neglected. Decommissioning costs have escalated, e.g. from $328 per unit in 1991 to $370 in 1993 for the Sacramento Municipal Utility District, though they still only amount to less than 0.1 cent per kWh. Waste management has been complicated in the U.S. by the decision to abandon civilian reprocessing; by the year 2000, roughly 30 U.S. nuclear power units will have filled their storage pools; dry storage has been delayed, and will be an expense not originally envisaged. Some examples of costs of major component replacement are provided. No single component has caused as much operational disruption and financial penalties as the steam generator. Operation and maintenance costs have increased steadily, and now amount to more than 70% of production costs. A strategic plan by the Nuclear Power Oversight Committee (of U.S. utilities) will ensure that the ability to correctly operate and maintain a nuclear power plant is built into the original design. 6 figs

Practice and perspectives of nuclear power plants life management activities in Russia

International Nuclear Information System (INIS)

Kurakov, Y.; Yanko, L.

1998-01-01

Extension of safe operation of NPPs is of special importance for Russia for economical reasons. The principles of NPP life extension are the same as for issuing licences for operation by the Regulatory body. It is requested to prove that undertaken measures compensate effects of ageing of structural components. Special attention is foreseen for methods of modernization of power plants for their safe operation

Plant control system upgrades in the context of industry trends towards plant life-extension

International Nuclear Information System (INIS)

De Grosbois, J.; Basso, R.; Hepburn, A.; Kumar, V.

2002-01-01

Domestic CANDU nuclear plants were brought online between 1972 and 1986. Over the next decade, most of these stations will be nearing the end of their designed operating life. Effort has traditionally been placed on ensuring that the existing installed plant control system equipment could operate reliably until the end of this design life. Until recently, little attention has been given to plant control system upgrades or replacements to meet the expected requirement for 30+ years of additional plant operation following potential plant refurbishments. Industry developments are changing this thinking. The combination of expected increases in electricity demand (and prices), and the many recent successful turnaround stories of U.S. nuclear power plants has resulted in new interest in plant life improvement and plant life extension programs. Plant control system upgrade decisions are now being driven by the need to replace or upgrade these systems to support plant life extension. This article is the first of several that investigate aspects of plant control system upgrades or replacement, specifically in the context of the CANDU station digital control computers (DCCs). It sets the context for the discussion in the subsequent articles by providing a brief review of industry trends favouring plant refurbishment, by outlining the basic issues of aging and obsolescence of control system equipment, by establishing the need for upgrades and replacements, and by introducing some of the basic challenges to be addressed by the industry as it moves forward. (author)

V-Model based Configuration Management Program for New-Build Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

2014-05-15

As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

Buried piping integrity management at fossil power plants

Energy Technology Data Exchange (ETDEWEB)

Shulder, Stephen J. [Structural Integrity Associates, Annapolis, MD (United States); Biagiotti, Steve [Structural Integrity Associates, Inc., Centennial, CO (United States)

2011-07-15

In the last decade several industries (oil and gas pipelines, nuclear power, and municipal water) have experienced an increase in the frequency and public scrutiny of leaks and failures associated with buried piping and tank assets. In several industries, regulatory pressure has resulted in the mandated need for databases and inspection programs to document and ensure the continued integrity of these assets. Power plants are being extended beyond their design life and the condition of below grade assets is essential toward continued operation. This article shares the latest advances in managing design, operation, process, inspection, and historical data for power plant piping. Applications have also been developed to help with risk prioritization, inspection method selection, managing cathodic protection data for external corrosion control, and a wide variety of other information. This data can be managed in a GIS environment allowing two and three dimensional (2D and 3D) access to the database information. (orig.)

Work flow management systems applied in nuclear power plants management system to a new computer platform

International Nuclear Information System (INIS)

Rodriguez Lorite, M.; Martin Lopez-Suevos, C.

1996-01-01

Activities performed in most companies are based on the flow of information between their different departments and personnel. Most of this information is on paper (delivery notes, invoices, reports, etc). The percentage of information transmitted electronically (electronic transactions, spread sheets, files from word processors, etc) is usually low. The implementation of systems to control and speed up this work flow is the aim of work flow management systems. This article presents a prototype for applying work flow management systems to a specific area: the basic life cycle of a purchase order in a nuclear power plant, which requires the involvement of various computer applications: purchase order management, warehouse management, accounting, etc. Once implemented, work flow management systems allow optimisation of the execution of different tasks included in the managed life cycles and provide parameters to, if necessary, control work cycles, allowing their temporary or definitive modification. (Author)

Safe ageing management of nuclear power plants: An European synthesis

International Nuclear Information System (INIS)

Grandemange, J.M.

2002-01-01

Ageing of nuclear power plants means evolution of material or equipment properties on one side, and evolution of personnel skill and procedure adequacy on the other side, both of which, after a certain time, may not be compatible with the required safety provisions, or with an economic operation of the plant. Repair or replacement of components, as well as change in service conditions for a better compatibility with component reduced capabilities can be used to mitigate ageing effects. The paper summarises the results of a study conducted in this field with the support of the European Commission. It presents: the synthesis of the work done under international auspices, and in the European context; the comparison of ageing management approaches used in several European countries with international recommendations; the summary of the various potential phenomena and their governing parameters, the methods of in-service ageing identification and possible mitigation methods; illustrative ageing management practices, taking material ageing aspects as examples. Concerning the first topic, the European report identifies 56 OECD and IAEA reports on ageing management issues, 35 being summarised in an appendix to the report. It also identifies numerous European and international studies covering topics of interest to ageing and Plant Life management. ageing management approaches have been considered from the regulatory point of view and from the utilities management point of view. Contributors to the study have identified a general consensus in Europe, with no limited time operating authorisation, the safety being a utility responsibility under continuous surveillance by the regulatory authority. Practical ageing management methods include: periodic safety reviews (PSR), a ten years periodicity being a common practice, completed by continuous ageing management taking into account safety and industrial anticipation needs; the implementation of life-time management programmes

Life Cycle Management

DEFF Research Database (Denmark)

Bey, Niki

2018-01-01

This chapter gives an overview of Life Cycle Management (LCM)—a discipline that deals with the managerial tasks related to practicing sustainable development in an organisation . Just as Life Cycle Assessment, LCM advocates the life cycle perspective , and it applies this perspective in decision...

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

International Nuclear Information System (INIS)

2011-11-01

At present there are over four hundred forty operational nuclear power plants (NPPs) in IAEA Member States. Ageing degradation of the systems, structures of components during their operational life must be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuteriumuranium (CANDU) reactor, boiling water reactor (BWR), pressurized water reactor (PWR), and water moderated, water cooled energy reactor (WWER) plants are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life cycle management of the plant components, which involves the integration of ageing management and economic planning. The target audience of the reports consists of technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present publication is the steam

Nuclear plant life - A business decision

International Nuclear Information System (INIS)

Joosten, J.K.

1995-01-01

Regarding the future of the nuclear power option, many scenarios have been put forth over the years. The most commonly accepted projections for installed nuclear capacity show it growing at a rate of about 2% per year throughout the next few decades. These projections appear modes on the surface. However, underlying the projections are critical assumptions and sometimes misconceptions about the lifetimes of existing reactors and how they are determined. The notion of a 40 year plant life is very common. Consequently, many projections start either with the assumption that no plants will be retired in the near terms or with the assumption that each retired plant will be replaced by another nuclear plant after 40 years. Effectively, these assumptions yield future projections for installed capacity that might be characterized as low growth, medium growth and high growth scenarios - or grow, grow, grow. The question remains as to whether or not these assumptions accurately model the driving forces and constraints to nuclear development. After all, there is no scientific basis for believing that all plants, PWRs BWRs, RBMKs, etc., should have the same 40 year life. Most power plant owners purchase the plant for the main reason of supplying electrical power to their consumer. For these owners, electricity production is a day to day commercial activity with various alternatives on how to achieve the prime objective. The decision of which electricity generation alternative to select (gas, coal, nuclear or renewable energy) and how long to operate the plant before replacing it with a new one is essentially a business decision. The paper discusses ageing, the nuclear plant life decision process, the factors which influence the decision and their ramifications regarding the near term growth of nuclear power capacity. The modelling of nuclear plant lifetimes is also discussed. (author). 5 refs, 10 figs, 1 tab

Ageing Management for Nuclear Power Plants. Safety Guide (Russian Edition); Upravlenie stareniem atomnykh ehlektrostantsij. Rukovodstvo po bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-01-15

The median age of nuclear power plants connected to the grid worldwide is increasing. Ageing management has become an important issue in ensuring the availability of required safety functions throughout the service life of a plant. This Safety Guide provides recommendations on meeting the requirements for safe long term operation and identifies key elements of effective ageing management for nuclear power plants.

Power plant operation and management in a deregulated market

Energy Technology Data Exchange (ETDEWEB)

Carraretto, Cristian [Department of Mechanical Engineering, University of Padova, Via Venezia, 1-35131 Padova (Italy)

2006-05-15

This paper analyzes the influence of electricity deregulation on the design, operation and management of the power plants owned by strategic and non-strategic producers. After a sensitivity analysis aimed at finding market conditions of profitable operation for thermal and hydroelectric power plants, a Nash-equilibrium market model is used to determine producers' optimum strategies, depending on their relative market power and overall production characteristics. Attention is then focused on the operation of single thermal power plants. Their short-term management plans and consequent effects on emission levels and residual life are described. The available reserve for primary and secondary control deriving from producers' market strategies is discussed. Some design options to improve combined cycles contribution to reserve service are finally described. The paper discusses these problems with a general approach, and uses many cases and examples derived from the current Italian scenario. (author)

Power plant operation and management in a deregulated market

International Nuclear Information System (INIS)

Carraretto, Cristian

2006-01-01

This paper analyzes the influence of electricity deregulation on the design, operation and management of the power plants owned by strategic and non-strategic producers. After a sensitivity analysis aimed at finding market conditions of profitable operation for thermal and hydroelectric power plants, a Nash-equilibrium market model is used to determine producers' optimum strategies, depending on their relative market power and overall production characteristics. Attention is then focused on the operation of single thermal power plants. Their short-term management plans and consequent effects on emission levels and residual life are described. The available reserve for primary and secondary control deriving from producers' market strategies is discussed. Some design options to improve combined cycles contribution to reserve service are finally described. The paper discusses these problems with a general approach, and uses many cases and examples derived from the current Italian scenario. (author)

Activities for the life management of nuclear power plant in Argentina

International Nuclear Information System (INIS)

Chocron, M.; Fabbri, S.; Versaci, R.A.

2003-01-01

Since September 1994 the organisation of Argentine nuclear power activities includes the following entities: Argentine Nucleo Electric S.A (NASA) with operates two NPPs (Atucha-1 and Embalse), National Regulatory Board of Nuclear Activities (ARN), National Atomic Energy Commission Commission (CNEA) Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to NASA for NPP operation. Works on Life Management of NPPs are included in these activities. In the past, NPP Life Management in Argentina was mainly based on the corrective maintenance concept based on the replacement of damaged part detected during the periodical outages. In recent times, as a consequential of an increasing concern about ageing a Subprogram was created to take care of these subjects. The subprogram, now in the first steps, comprise several tasks: The first task involves the identification of components ageing mechanism and materials likely to age. In the area of mechanical components. a starting point is matrix involving major components such as: Reactor Pressure Vessel, Reactor Internals, Steam Generators, Pressure Tubes, Piping, etc. In this work the apply methodology for the selection of the components will be presented. (Full text)

International requirements for life extension of nuclear power plants

International Nuclear Information System (INIS)

Wernicke, Robert

2009-01-01

Lifetime extension or long-term operation of nuclear facilities are topics of great international significance against the backdrop of a fleet of nuclear power plants of which many have reached 2/3 of their planned life. The article deals with the conditions for, and the specific requirements of, seeking long-term operation of nuclear power plants as established internationally and on the basis of IAEA collections. Technically, long-term operation is possible for many of the nuclear power plants in the world because, normally, they were built on the basis of conservative rules and regulations and, as a consequence, incorporate significant additional safety. Application of requirements to specific plants implies assessments of technical safety which show that conservative design philosophies created reserves and, as a consequence, there is an adequate level of safety also in long-term plant operation. For this purpose, the technical specifications must be revised, necessary additions made, and (international) operating experience taken into account and management of aging established. Two examples are presented to show how the approach to long-term plant operation is put into practice on a national level. (orig.)

Management plan of useful life; Plan de gestion de vida util

Energy Technology Data Exchange (ETDEWEB)

Sanchez Zapata, J. D.

2009-07-01

The Cofrentes NPP Life Management Plan is a plant management program that covers all those activities aimed at monitoring, controlling and mitigating the effects of ageing in the safety-related structures, systems and components, as well as in the equipment that is of particular importance for long-term availability of the plant. the methodology used is based on the system and methods of the so-called UNESA Methodology, whose safety-related aspects have been updated with the application of criteria defined in Licensing Renewal regulation 10 CFR 54. the text develops the details of this plan and describes its status at the present time. (Author)

Maintenance, rehabilitation, long life-the CANDU potential

International Nuclear Information System (INIS)

Torgerson, D.F.; Charlebois, P.; Hopkins, J.

1998-01-01

Plant life extension beyond the original design life is becoming an attractive economic consideration in the nuclear industry. Plant Life Management and life extension considerations have been built into the complete life cycle of the CANDU plant. The plant life management studies demonstrate that life extension for operating plants beyond 30 years is economically viable. The new CANDU designs benefit from this experience feedback and as a result, the plant design basis is now 40 years or better with potential for economical life extension. AECL is therefore confident that the new CANDU designs will exceed the performance record of the first generation CANDU 6 units and is committed to providing continued support and services during the operating life of the plant

NPP service life management

International Nuclear Information System (INIS)

Elagin, Yu.P.

2001-01-01

Problems of NPP service life management and service life prolongation are reviewed. Methods for the prolongation of the French NPP service life are discussed, priority directions of nuclear block service life management in regard to aging in the context of the European program of investigation into the materials aging are identified. Questions of the provision of the 60 years service life of the Mihama 1 block (Japan) and decision of the problem of the control equipment aging in Great Britain are discussed. Situation with the prolongation of licenses on the NPP operation in the USA and Spain is considered [ru

Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessels

International Nuclear Information System (INIS)

2005-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

Technical Evaluation on Ageing Management in Nuclear Power in Japan -Life Extension over 40 Years at Japanese Nuclear Power Plants-

International Nuclear Information System (INIS)

Tanaka, H.; Iwasaki, M.; Miyama, S.

2012-01-01

The Japanese commercial reactors have accumulated more than 40 years operating experience since Tsuruga-1 started commercial operation in March 1970. However, the severe accident occurred at Fukushima nuclear power plants triggered by East Japan Great Earthquake on March 11 last year. The facts that all the reactors having experienced core meltdown had operated for more than 30 years and Fukushima Daiichi unit 1 had just received the approval for its 40th year Ageing Management Technical Evaluation results from the Japanese government caused increasing distrust among the public in nuclear power plants operating for a long period of time. However, investigations of the accident conducted so far have not revealed any evidence that ageing degradation accelerated the accident. In addition, the analysis of seismic accelerations of the earthquake did not show that any component function was lost due to the accident. Considering these facts, I would like to discuss the issues to be continuously pursued and to be additionally implemented as part of the plat life management activities. In addition, I will introduce the efforts made by the Japanese utilities following the accident. (author)

Computer-assisted power plant management

International Nuclear Information System (INIS)

Boettcher, D.

1990-01-01

Operating a power plant and keeping it operational is ensured by a multiplicity of technical management subtasks which are cross referenced and based on an extensive inventory of descriptive and operational plant data. These data stocks are still registered in an isolated mode and managed and updated manually. This is a labor intensive, error prone procedure. In this situation, the introduction of a computer-assisted plant management system, whose core is a data-base of assured quality common to all activities, and which contains standardized processing aids fully planned for the subtasks occurring in the plant, is likely to achieve a considerable improvement in the quality of plant management and to relieve the staff of administrative activities. (orig.) [de

Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies

International Nuclear Information System (INIS)

2001-02-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring, and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs) including the Soviet designed water moderated and water cooled energy reactors (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which

Plant management in concurrent engineering

International Nuclear Information System (INIS)

Haubensack, D.; Malvache, P.; Valleix, P.

1997-01-01

The ImagIn project consist in a method and a set of computer tools apt to bring perceptible and assessable improvements in the operational safety of a nuclear plant. Its aim is to design an information system that would maintain a highly detailed computerised representation of a nuclear plant, in its initial state and throughout its in-service life. It is not a tool to drive or help driving the nuclear plant, but a tool that manages concurrent operations that modify the plant configuration in a very general way (maintenance for example). The configuration of the plant, as well as rules and constraints about it, are described in a object-oriented, knowledge database, which is built using a generic ImagIn meta-model based on the semantical network theory. An inference engine works on this database and is connected to reality through interfaces to operators and captors on the installation; it verifies constantly in real-time the consistency of the database according to its inner rules, and reports eventual problems to concerned operators. A special effort is made on interfaces to provide natural and intuitive tools (using virtual reality, natural language, voice recognition and synthesis). A laboratory application on a fictive but realistic installation already exist and is used to simulate various test and scenari. A real application is being constructed on SILOE, an experimental reactor of the CEA. (authors)

Safety Aspects of Ageing Management throughout the Full Life Cycle of NPPs

International Nuclear Information System (INIS)

Dou, Yikang

2012-01-01

Most component failures stem from effects of one or multiple ageing mechanism(s). Ageing management is one of the most robust measures to prevent failure and to maintain and increase safety of nuclear power plants. Based on Nuclear Safety Guideline on Ageing Management (NS-G-2.12) published by IAEA in 2009, the paper summarizes main ageing management activities required for all stages of life cycle of NPPs, including design, construction/manufacture, commissioning, operation, life extension for long-term operation and decommissioning. Interactive relations of ageing management in successive stages are analyzed. Implementation of the IAEA Guideline in comprehensive way will bring new challenges to design conception, modes of construction, manufacture, commissioning, equipment qualification, O and M, licensing, life extension and decommissioning for NPPs, however, it will be beneficial to enhance nuclear safety level, especially to promote development of nuclear power in China in a safe, reliable, profitable and sustainable way. (author)

A Plan to Optimize the Management of Weld ID SSN Numbering System for Nuclear Power Plants in Korea

International Nuclear Information System (INIS)

Yoo, Hyun Ju; Cho, Chan Hee; Kim, Jin Hoi; Park, Dong Min

2016-01-01

Summary Sheet Number(SSN) in the current LTP is an ID which means a weldment in a nuclear power plant. However, the SSN ID, which is unique on in a nuclear power plant, is not unique one if the weldments of entire nuclear power plant in Korea are treated in one system. Therefore, it is hard to manage the data during life time using the existing SSN ID system. It is also hard to configure the characteristics of weldment in mind because IDs implying Alloy600 and overlay weld do not exist in the existing SSN ID System. An optimized SSN numbering system managing weldments for the life time is introduced in this paper. Moreover, it is explained how to manage the SSN numbering system in the computer program system, too. The problem, which the weld is not harmoniously managed, would be solved provided adapting the new SSN ID introduced in this paper. A weld is managed during its life time from creation to extinction. The inquiry of inspection history of a concerned weld and the reference of statistics would be performed easily and rightly because the concerned weld can be accessed from anywhere connected to KHNP network such as KHNP headquater, plants and CRI

Viewpoint of utilities regarding fuel management of nuclear power plants

International Nuclear Information System (INIS)

Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

1977-01-01

The engagement of utilities in nuclear power requires them to engage in an increasing amount of fuel management activities in order to carry out all the tasks involved. Essentially, these activities involve two main areas: The procurement of all steps of the fuel cycle from the head to the back end; and in-core fuel management. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be borne by the utilities. Today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The fuel management activities of the utilities are analysed with respect to organizational, technical, safeguarding, and financial aspects. The active participation of the utilities in fuel management helps to achieve high availability and flexibility of the nuclear power plant during its whole life as well as safe waste isolation. This can be ensured by continuous optimization of all fuel management aspects of the power plant or, on a larger scale, of a power plant system, i.e. activities by utilities to minimize fuel-cycle effects on the environment, which include optimization of fuel behaviour, and radiation exposure to the public and personnel; and technical and economic evaluations by utilities of out- and in-core fuel management. (author)

IMPLEMENTATION OF WORK LIFE QUALITY PROGRAMS WITH THE PROJECT MANAGEMENT MODEL

Directory of Open Access Journals (Sweden)

Maria Lúcia Granja Coutinho

2010-06-01

Full Text Available The research studies the implementation of Quality of Working Life (QWL programs using project management techniques. Quality of Work Life projects have undergone a constant increase in scope to the point where they currently involve such diverse themes as change in dietary habits, exercise, stress management, socio environmental responsibility, and adult education. The major focus of this research is to analyze the processes and knowledge areas of project management being used to deal with this increased scope. The managerial processes identified were divided into categories of preparation, structuring, execution, and conclusion. The knowledge areas studied were: communication, risks, human resources, and acquisitions. The firms studied included mid to large sized firms located in the north, southeast and south of Brazil. We interviewed managers, directors, CEOs, plant managers, and line managers as part of this effort. The results suggest that the project management practices used were ad hoc and based on day to day needs. They also suggest that sound project management practices are applicable to QWL programs in the firms we studied.

Utilities' view on the fuel management of nuclear power plants

International Nuclear Information System (INIS)

Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

1977-01-01

Utilities engagement in nuclear power requires an increasing amount of fuel management activities by the utilities in order to meet all tasks involved. These activities comprise essentially two main areas: - activities to secure the procurement of all steps of the fuel cycle from the head to the back end; - activities related to the incore fuel managment. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be realized by the utilities. Starting in the past, today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The scope of utilities' fuel management activities is analyzed with respect to organizational aspects, technical aspects, safeguarding aspects, and financial aspects. Utilities taking active part in the fuel management serves to achieve high availability and flexibility of the nuclear power plant during the whole plant life as well as safe waste isolation. This can be assured by continuous optimization of all fuel management aspects of the power plant or on a larger scale of a power plant system, i.e., utility activities to minimize the effects of fuel cycle on the environment, which includes optimization of fuel behaviour, radiation exposure to public and personnel, and utility technical and economic evaluations of out- and incore fuel management. These activities of nuclear power producing utilities in the field of nuclear fuel cycle are together with a close cooperation with fuel industry as well as national and international authorities a necessary basis for the further utilization of nuclear power

NPP life management (abstracts)

International Nuclear Information System (INIS)

Litvinskij, L.L.; Barbashev, S.V.

2002-01-01

Abstracts of the papers presented at the International conference of the Ukrainian Nuclear Society 'NPP Life Management'. The following problems are considered: modernization of the NPP; NPP life management; waste and spent nuclear fuel management; decommissioning issues; control systems (including radiation and ecological control systems); information and control systems; legal and regulatory framework. State nuclear regulatory control; PR in nuclear power; training of personnel; economics of nuclear power engineering

Aging management of containment structures in nuclear power plants

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Ellingwood, B.R.; Graves, H.L. III; Norris, W.E.

1996-01-01

Research is being conducted by Oak Ridge National Laboratory under US nuclear regulatory commission (USNRC) sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a structural materials information center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of non-destructive evaluation techniques, assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants. (orig.)

Aging management of containment structures in nuclear power plants

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

1994-01-01

Research is being conducted by Oak Ridge National Laboratory under U.S. Nuclear Regulatory Commission sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the US-NRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a Structural Materials Information Center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of nondestructive evaluation techniques, assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants. (author). 29 refs., 2 figs

Aging management of containment structures in nuclear power plants

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Ellingwood, B.R.; Graves, H.L. III; Norris, W.E.

1994-01-01

Research is being conducted by ORNL under US Nuclear Regulatory Commission (USNRC) sponsorship to address aging management of nuclear power plant containment and other safety-related structures. Documentation is being prepared to provide the USNRC with potential structural safety issues and acceptance criteria for use in continued service evaluations of nuclear power plants. Accomplishments include development of a Structural Materials Information Center containing data and information on the time variation of 144 material properties under the influence of pertinent environmental stressors or aging factors, evaluation of models for potential concrete containment degradation factors, development of a procedure to identify critical structures and degradation factors important to aging management, evaluations of nondestructive evaluation techniques. assessments of European and North American repair practices for concrete, review of parameters affecting corrosion of metals embedded in concrete, and development of methodologies for making current condition assessments and service life predictions of new or existing reinforced concrete structures in nuclear power plants

IAEA activities and main achievements on human resource management and training of nuclear power plant personnel

International Nuclear Information System (INIS)

Kossilov, A.

2002-01-01

The Nuclear Power Engineering Section is responsible for implementation of the Agency's sub-programme on Engineering and Management Support for Competitive Nuclear Power. The objectives of the sub-programme is to increase Member State capabilities in utilizing the best engineering and management practices for improving NPP performance and competitiveness, optimizing plant service life and decommissioning and strengthening nuclear power infrastructure. NPES' main activities cover: Nuclear power infrastructure, Knowledge management, Personal training and qualification, Quality Management and QA, NPP life management including databases, Modern NPP control and instrumentation, and NPP performance management

The Software Life-Cycle Based Configuration Management Tasks for the KNICS Project

International Nuclear Information System (INIS)

Cheon, Se Woo; Kwon, Kee Choon

2005-01-01

Software configuration management (SCM) is an activity, which configures the form of a software system (e.g., design documents and programs) and systematically manages and controls the modifications used to compile the plans, development, and operations resulting from software development and maintenance. The SCM tool, NuSCM, has been specifically developed for the software life-cycle configuration management of developing the KNICS plant protection system (PPS). This paper presents the application of NuSCM to the KNICS project

Assessment and Management of ageing of major nuclear power plant components important to safety: PWR pressure vessels

International Nuclear Information System (INIS)

1999-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g., caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs; and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which involves the integration of

Life cycle management (LCM)

DEFF Research Database (Denmark)

Remmen, Arne; Thrane, Mikkel

2004-01-01

The chapter gives an introduction to Life Cycle Management (LCM) and shows how LCM can be practiced in different contexts and at different ambition levels.......The chapter gives an introduction to Life Cycle Management (LCM) and shows how LCM can be practiced in different contexts and at different ambition levels....

Specification of life cycle assessment in nuclear power plants

International Nuclear Information System (INIS)

Abbaspour, M.; Kargari, N.; Mastouri, R.

2008-01-01

Life Cycle Assessment is an environmental management tool for assessing the environmental impacts of a product of a process. life cycle assessment involves the evaluation of environmental impacts through all stages of life cycle of a product or process. In other words life cycle assessment has a c radle to grave a pproach. Some results of life cycle assessment consist of pollution prevention, energy efficient system, material conservation, economic system and sustainable development. All power generation technologies affect the environment in one way or another. The main environmental impact does not always occur during operation of power plant. The life cycle assessment of nuclear power has entailed studying the entire fuel cycle from mine to deep repository, as well as the construction, operation and demolition of the power station. Nuclear power plays an important role in electricity production for several countries. even though the use of nuclear power remains controversial. But due to the shortage of fossil fuel energy resources many countries have started to try more alternation to their sources of energy production. A life cycle assessment could detect all environmental impacts of nuclear power from extracting resources, building facilities and transporting material through the final conversion to useful energy services

Life Cycle Environmental Management

DEFF Research Database (Denmark)

Pedersen, Claus Stig; Jørgensen, Jørgen; Pedersen, Morten Als

1996-01-01

A precondition for environmentally conscious management is the awareness of the environmental impact potentials created by an industrial company. There is an obvious need for management tools to support the implementation of relevant environmental criteria into the industrial decision making...... processes. The discipline of life cycle environmental management (LCEM) focuses on the incorporation of environmental criteria from the life cycles of products and other company activities into the company management processes. This paper introduces the concept of LCEM as an important element...... of the complete set of environmental objects in an industrial manufacturing company....

Life-time management for mechanical components; Lebensdauermanagement mechanischer Komponenten

Energy Technology Data Exchange (ETDEWEB)

Roos, E. [Stuttgart Univ. (DE). Materialpruefungsanstalt (MPA)

2006-07-01

The safety and economic efficiency of industrial systems depend on the quality of components and systems. In the field of power generation, power plants should be safe and have high availability and minimum specific generation cost. Life management is essential for this. Depending on the safety relevance of systems, structures and components (SSC), this includes proofs of integrity, time-oriented or condition-oriented preventive maintenance, or just failure-oriented maintenance. (orig.)

Plant life management (XVO). Report 1999

International Nuclear Information System (INIS)

Solin, J.

2001-02-01

Experimental and analytical research is being carried out in an industrially oriented project dealing with on estimating and managing lifetime of critical structural components in energy industry. The research topics included systematic component lifetime management, lifetime of pressure bearing components, piping vibrations and integrity management, management of materials ageing, non-destructive inspection, water chemistry, oxide films and their role in service reliability and build-up of activity levels, stress corrosion cracking in Inconel welds, irradiation assisted stress corrosion cracking of core components, development of crack growth testing methods as well as the mechanisms of environmentally assisted cracking. The main results of the first project year are summarised in this report. (orig.)

EVALUATING THE LIFE CYCLE COSTS OF PLANT ASSETS – A MULTIDIMENSIONAL VIEW

Directory of Open Access Journals (Sweden)

Markus Gram

2012-11-01

Full Text Available This paper shows the results of the task group "Asset life cycle management" of the AustrianScientific Maintenance and Asset Management Association (ÖVIA. One purpose of the researchactivities is to create a generic life cycle model for physical assets which includes all costs in everyphase of the asset life cycle. The first step is a literature review determining the most established lifecycle cost models. This is the input for discussing the completeness of such frameworks with theparticipating industrial companies. A general model is deducted from existing approaches and thedetermined costs are evaluated with respect to priority and practical relevance. The result of theevaluation shows which costs are taken into account for investment decisions. Another outcome ofthe study is the verification of importance of the proposed costs for industrial companies, especiallyfor the process industry. The derived life cycle cost framework is the basis for developing a calculationtool and subsequently, for further research in the flied of uncertainty-based methodologies forlife cycle cost analyzing of physical plant assets.

Data collection and record keeping for the management of nuclear power plant ageing: A safety practice

International Nuclear Information System (INIS)

1991-01-01

This Safety Practice is the first in a series of reports under the programme on the management of nuclear power plant ageing. The purpose of the programme is to facilitate the exchange of information and to promote co-operation among Member States towards understanding and managing the ageing degradation of components, with the aim of maintaining safe and reliable plant operation. The availability and evaluation of appropriate data on nuclear power plant components are essential to safety and constitute a key factor in plant life extension considerations. The present publication provides guidance on data requirements and an effective and practical system for data collection and record keeping in relation to the evaluation and management of ageing and service life. This guidance is based on current practices. It is envisaged that the application of the guidance will contribute to the safe and reliable operation of nuclear power plants and will facilitate international information exchange on ageing related component failures, malfunctions and degradation, since data collected using the same ground rules would be easier to exchange and compare. The guidance is intended primarily for the management, maintenance and technical staff of nuclear power plants, on whom the ultimate success of the recommended system and its associated benefits depend. Intended secondary audiences include utility management and central technical support organizations, regulatory bodies, standards organizations, design companies, and research and development institutes. 8 refs, 1 fig., 1 tab

Some activities in France related to life management of nuclear power plants

International Nuclear Information System (INIS)

Petrequin, P.

1998-01-01

Significant events concerned with life management of NPPs in France were: replacement of steam generators of TRICASTIN 1 NPP, defect detected in the emergency cooling system of DAMPIERRE 1 reactor and expertise of decommissioned CHOOZ A reactor. Programs in progress described in this report are: irradiation of materials for internal components and fracture toughness studies of irradiated materials

Chapter 15. Plant pathology and managing wildland plant disease systems

Science.gov (United States)

David L. Nelson

2004-01-01

Obtaining specific, reliable knowledge on plant diseases is essential in wildland shrub resource management. However, plant disease is one of the most neglected areas of wildland resources experimental research. This section is a discussion of plant pathology and how to use it in managing plant disease systems.

Steam generator life cycle management - B and W perspective

International Nuclear Information System (INIS)

Dhar, D.; Fluit, S.; Millman, J.

2006-01-01

This paper is an effort towards the B and W perspective about the effective life cycle management (LCM) of the CANDU Steam Generators (SGs) based on the identification of active and plausible degradation mechanisms for various SG components and the need to achieve a safe and economic operating interval for the station. The objective of this paper is to provide the long-term effective strategy for inspections, maintenance and design modifications as necessary for the safe and reliable operation of the SGs during the plant design life. The derived activities of this strategy need to be integrated with the station outage specific work scope plan for an effective life cycle management. The technical basis for these activities is based on the review of previous field inspection records, maintenance work and modifications at the station and operational experience (OPEX) from other CANDU steam generators with similar design. These activities need to be performed in order to ensure that the SGs perform within an acceptable level of safety and reliability as per the licensing bases, while optimizing station production and cost effectiveness. (author)

Risk informed life cycle plant design

International Nuclear Information System (INIS)

Hill, Ralph S. III; Nutt, Mark M.

2003-01-01

Many facility life cycle activities including design, construction, fabrication, inspection and maintenance are evolving from a deterministic to a risk-informed basis. The risk informed approach uses probabilistic methods to evaluate the contribution of individual system components to total system performance. Total system performance considers both safety and cost considerations including system failure, reliability, and availability. By necessity, a risk-informed approach considers both the component's life cycle and the life cycle of the system. In the nuclear industry, risk-informed approaches, namely probabilistic risk assessment (PRA) or probabilistic safety assessment (PSA), have become a standard tool used to evaluate the safety of nuclear power plants. Recent studies pertaining to advanced reactor development have indicated that these new power plants must provide enhanced safety over existing nuclear facilities and be cost-competitive with other energy sources. Risk-informed approaches, beyond traditional PRA, offer the opportunity to optimize design while considering the total life cycle of the plant in order to realize these goals. The use of risk-informed design approaches in the nuclear industry is only beginning, with recent promulgation of risk-informed regulations and proposals for risk-informed codes. This paper briefly summarizes the current state of affairs regarding the use of risk-informed approaches in design. Key points to fully realize the benefit of applying a risk-informed approach to nuclear power plant design are then presented. These points are equally applicable to non-nuclear facilities where optimization for cost competitiveness and/or safety is desired. (author)

U.S. National and regional impacts nuclear plant life extension

International Nuclear Information System (INIS)

Makovick, L.; Fletcher, T.; Harrison, D.L.

1987-01-01

The purpose of this study was to evaluate the economic impacts of nuclear plant life extension on a national and regional level. Nuclear generating capacity is expected to reach 104 Gigawatts (119 units) in the 1994-1995 period. Nuclear units of the 1970 to 1980 vintage are expected to account for 96% of nuclear capacity. As operating licenses expire, a precipitous decline in nuclear capacity results, with an average of 5 gigawatts of capacity lost each year from 2010 to 2030. Without life extension, 95% of all nuclear capacity is retired between the years 2010 and 2030. Even with historically slow growth in electric demand and extensive fossil plant life extension, the need for new generating capacity in the 2010-2030 time period is eight times greater than installed nuclear capacity. Nuclear plant life extension costs and benefits were quantified under numerous scenarios using the DRI Electricity Market Model. Under a wide range of economic assumptions and investment requirements, nuclear plant life extension resulted in a net benefit to electricity consumers. The major source of net benefits from nuclear plant life extension results from the displacement of fossil-fired generating sources. In the most likely case, nuclear plant life extension provides a dollar 200 billion net savings through the year 2030. Regions with a large nuclear capacity share, newer nuclear units and relatively higher costs of alternative fuels benefit the most from life extension. This paper also discusses the importance of regulatory policies on nuclear plant life extension

Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessel internals

International Nuclear Information System (INIS)

2005-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and ware out of components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of heavy water moderated reactors (HWRs), boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

Nuclear Power Plants Secondary Circuit Piping Wall-Thinning Management in China

International Nuclear Information System (INIS)

Zhong Zhimin; Li Jinsong; Zheng Hui

2012-01-01

Research and field feedbacks showed that nuclear power plants secondary circuit steam and water piping are more sensitive than that of fuel plant to the attack of flow-accelerated corrosion (FAC). FAC, Liquid droplet impingement or cavitation erosion will cause secondary circuit piping local wall-thinning in NPPs. Without effective management, the wall-thinning in those high energy piping will cause leakage or pipe rupture during nuclear power plant operation, more seriously cause unplanned shut down, injured and fatality, or heavy economic losses. This paper briefly introduces the history, development and state of the art of secondary circuit piping wall-thinning management in China NPPs. Then, the effectiveness of inspection grid size selecting was analyzed in detail based on field feedbacks. EPRI recommendatory inspection grid, JSME code recommendatory grid and plant specific inspection grid were compared and the detection probabilities of local wall-thinning were estimated. Then, the development and application of NPPs Secondary Circuit Piping Wall Thickness Management Information System, developed, operated and maintained by our team, was briefly introduced and the statistical analysis results of 11 PWR units were shared. It was conclude that the long term, systemic, effective wall-thinning management strategy of high energy piping was very important to the safety and economic operation of NPPs. Furthermore, take into account the actual situation of China nuclear power plants, some advice and suggestion on developing effective nuclear power plant secondary circuit steam and water piping wall-thinning management system are put forward from code development, design and manufacture, operation management, pipeline and locations selection, inspection method selection and application, thickness measurement result evaluation, residual life predication and decision making, feedbacks usage, personnel training and etc. (author)

Plant life extensions for German nuclear power plants? Controversial discussion profit taking of nuclear power plant operators

International Nuclear Information System (INIS)

Matthes, Felix C.

2009-10-01

The discussion on the plant life extensions for German nuclear power plants beyond the residual quantity of electricity particularly focus on three aspects: Effects for the emission of carbon dioxide as a greenhouse gas; Development of the electricity price for which a reduction or attenuation is postulated due to a plant life extension; Skimming of additional profits at operating companies and their use in the safeguarding of the future (development of renewable energies, support of energy efficiency, promotion of the research, consolidation of the public budget, and so on). Under this aspect, the author of the contribution under consideration reports on the profit taking of nuclear power plant operators. The presented analysis considers three aspects: (a) Specification of the quantity structures for the investigated model of plant life extension; (b) The decisive parameter is the revenue situation and thus the price development for electricity at wholesale markets; (c) Determination and evaluation of the course in time of the profit taking.

Configuration management of plant modifications for nuclear power plants

International Nuclear Information System (INIS)

Ritsch, W.J.

1987-01-01

Due to the increasing complexity of nuclear power plant operation, regulatory pressure, and the large numbers of people required to operate and support the stations, the control of plant modifications at these plants needs to be expanded and improved. The aerospace and defense industries, as well as the owners or operators of large energy projects have established configuration management programs (CMPs) to control plant design changes. These programs are composed of well-defined functions for identifying, evaluating, recording, tracking, issuing, and documenting the established baseline conditions, as well as required changes to these baseline conditions. The purpose of this paper is to describe a recommended CMP for plant modifications consisting of a computerized data base installed on the utility's computer to provide a central storage of plant design and operations data necessary to control the following activities as they are affected by plant design changes: training; record management; operations; maintenance; health physics; planning/scheduling; procurement/inventory control; outage management (including modifications); and emergency response

Plant life management. An integral part of operation and maintenance policy

International Nuclear Information System (INIS)

Faidy, C.; Hutin, J.-P.

2002-01-01

Electricite de France is now operating 58 PWR nuclear power plants that produce 75% of electricity in France. Besides maintaining safety and availability on a routine basis, it is outmost important to protect the investment. That is the reason why EDF is devoting important resources to implement ageing management concern as an integral part of operation and maintenance programs (for example through appropriate data collection and analysis, specific repair and replacement projects and important anticipation efforts, taking in account the high level of standardisation of the units). A particular organisation has been set up to continuously observe and analyse all activities so as to make sure that ageing concern is correctly taken in account in strategies and that no decisions are susceptible to impair plant lifetime. This 'lifetime program' is paying attention to technical issues associated with main components but is also dealing with issues related to economics and industry situation. (orig.)

Guideline for ageing management in nuclear power plants

International Nuclear Information System (INIS)

Herter, K.H.; Schuler, X.; Hienstorfer, W.; Pompe, W.

2007-01-01

During operation of nuclear power plants, the quality of systems, structures and components may change as a result of ageing (conceptional ageing, technological ageing or physical ageing), which will affect the system quality. Ageing management is necessary to ensure safety and availability throughout the life of the systems. This necessitates a systematic, integrative and knowledge-based approach. Systems, structures and components are grouped according to their relevance for meeting the set goals. Ageing mangement should be process-oriented and should be integrated in the organisational procedure in cooperation with the safety manager. The procedure should follow the PDCA principle (plan - do - check - act). The data, documents, knowledge and evaluations required for ageing management are part of the knowledge base of the nuclear power station and are updated regularly. The efficiency of ageing management must be reassessed at regular intervals. (orig.)

Analysis of integrated plant upgrading/life extension programs

International Nuclear Information System (INIS)

McCutchan, D.A.; Massie, H.W. Jr.; McFetridge, R.H.

1988-01-01

A present-worth generating cost model has been developed and used to evaluate the economic value of integrated plant upgrading life extension project in nuclear power plants. This paper shows that integrated plant upgrading programs can be developed in which a mix of near-term availability, power rating, and heat rate improvements can be obtained in combination with life extension. All significant benefits and costs are evaluated from the viewpoint of the utility, as measured in discounted revenue requirement differentials between alternative plans which are equivalent in system generating capacity. The near-term upgrading benefits are shown to enhance the benefit picture substantially. In some cases the net benefit is positive, even if the actual life extension proves to be less than expected

Assessment and management of ageing of major nuclear power plant components important to safety. Primary piping in PWRs

International Nuclear Information System (INIS)

2003-07-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. The

Configuration management and load monitoring procedures for nuclear plant structures

International Nuclear Information System (INIS)

Chu, S.L.; Skaczylo, A.T.

1990-01-01

This paper describes a computer-aided engineering tool called the Load Monitoring System (LMS) that was proven effective for monitoring floor framing, loads, and structural integrity. The system links structural analysis, design investigation, and reporting and automated drafting programs with a Data Base Management System (DBMS). It provides design engineers with a powerful tool for quickly incorporating, tracking, and assessing load revisions and determining effects on steel floor framing members and connections, thereby helping to reduce design man-hours, minimize the impact of structural modifications, and maintain and document the design baseline. The major benefit to utilities are the reduction in engineering costs, assistance with plant configuration management, and assurance of structural safety throughout the operating life of a nuclear plant and at evaluation for license renewal. (orig./HP)

Aging management of nuclear power plants in Japan

International Nuclear Information System (INIS)

Maeda, Noriyoshi

2003-01-01

The Resource and Energy Agency of the Ministry of Trade and Industry (at present, the Nuclear and Industrial Safety Agency of the Ministry of Economy and Industry) carried out technical and present state conservation evaluations on soundness on a case of supposing operation of main apparatuses important for safety for sixty years, on three nuclear power plants constructed at initial period, on April, 1996, to open her basic concept on their aging management. The electricity companies also carried out their technical evaluation to investigate aging management measures for apparatuses important for safety and succession of operation, to summarize some essential measures for its long-term conservation plan. And, long-term and steady efforts such as technical development, preparation on national technical codes and private standards, data accumulation on materials and apparatuses are also required, to successively act them under adequate role-sharing and cooperation among government, universities and industries. Here were described periodical safety review, containing aging management technical evaluation, preparations of standards on apparatus maintenance standard, and so on, promotion of technical development, and Nuclear Power Plant Life Engineering Center (PLEC). (G.K.)

Monitoring ethylene emissions from plants cultured for a controlled ecological life support system

Science.gov (United States)

Corey, Kenneth A.

1995-01-01

Emission of hydrocarbons and other volatile compounds by materials and organisms in closed environments will be a major concern in the design and management of advanced life support systems with a bioregenerative component. Ethylene, a simple hydrocarbon synthesized by plants, is involved in the elicitation of a wide range of physiological responses. In closed environments, ethylene may build up to levels which become physiologically active. In several growouts of 'Yecora Rojo' wheat in Kennedy Space Center's Biomass Production Chamber (BPC), it was observed that leaf flecking and rolling occurred in the sealed environment and was virtually eliminated when potassium permanganate was used to scrub the atmospheric environment. It was suggested that ethylene, which accumulated to about 60 ppb in the chamber and which was effectively absorbed by potassium permanganate, was responsible for the symptoms. The objectives of this work were to: (1) determine rates of ethylene evolution from lettuce (Lactuca sativa cultivar Waldemann's Green) and wheat (Triticum aestivum cultivar Yecora Rojo) plants during growth and development; (2) determine the effects of exposure of whole, vegetative stage plants to exogenous ethylene concentrations in the range of what would develop in closed environment growth chambers; and (3) develop predictive functions for changes in ethylene concentration that would develop under different cropping and closed environment configurations. Results will lead to the development of management strategies for ethylene in bioregenerative life support systems.

Proceedings of the topical meeting on nuclear power plant life extension

International Nuclear Information System (INIS)

Anon.

1988-01-01

This book contains the proceedings of the topical meeting on nuclear power plant life extension. The sessions are organized under the following headings: Perspectives on nuclear power plant life extension, the potential for additional years of power production, NRC and industry life extension initiatives, concrete and structures degradation and evaluation of useful remaining life, plant life extension programs, Reactor pressure vessel and intervals degradation and evaluation of useful remaining life, life extension decision making issues and institutions, systems degradation and evaluation of remaining life, monitoring and repair, design records and maintenance activities for life extension, Mechanical and electrical component degradation and evaluation of remaining life, expert systems and other techniques for enhanced and continued operation, life extension aspect of codes, standards, and related technologies, piping and valve degradation and evaluation of useful remaining life

Contribution of Enterprise Asset Management (EAM) systems and CAP programs to support NPP life extension program

International Nuclear Information System (INIS)

Luanco, E.

2007-01-01

There is no specific IS (Information System) which supports the entire scope of a plant life extension, but there are a number of existing solutions that contributes to support it. Globally there are 2 categories of IS solution in the market: those supporting the Plant Life Improvement (PLIM) side of the life extension program and the others supporting the Plant Life Extension (PLEX) process side of it. The first category involves a large number of applications that span from ageing evaluation criteria programs, to monitoring solution for the critical components and to analysis and decision tools. The second category comprises solutions which support partially or globally the overall business process under a regulatory controlled manner. Both categories require 3 conditions to be satisfied: -) a comprehensive set of data (these data are often produced by various applications and the ability to correlate all the data together with a high degree of integrity is an important success factor); -) a feedback mechanism whose dual aspect is the monitoring of the ageing phenomena and the management of all the actions to be coordinated to ensure that preset objectives will be achieved in due time; and -) good people management to ensure particularly that staff will be well acquainted with new equipment or with new operating processes

Plant life history and above–belowground interactions

NARCIS (Netherlands)

Deyn, de Gerlinde

2017-01-01

The importance of above–belowground interactions for plant growth and community dynamics became clear in the last decades, whereas the numerous studies on plant life history improved our knowledge on eco-evolutionary dynamics. However, surprisingly few studies have linked both research fields

Using Plants to Explore the Nature & Structural Complexity of Life

Science.gov (United States)

Howard, Ava R.

2014-01-01

Use of real specimens brings the study of biology to life. This activity brings easily acquired plant specimens into the classroom to tackle common alternative conceptions regarding life, size, complexity, the nature of science, and plants as multicellular organisms. The activity occurs after a discussion of the characteristics of life and engages…

Life cycle management of french operating nuclear power plants

International Nuclear Information System (INIS)

Valibus, L.; Loriette, Ph.

1998-01-01

The PWR units of the EDF generation capacity in operation are young. They represent a technical and financial asset with a strategic significance both for the company and for France. According to regulations, even if the safety reports take into account a 40-year lifetime for the NSSS, the French regulations do not specify a time limit for the operation of the facilities according to the plant authorization decree. The Safety Authorities may, at any time require another safety re-examination. In fact, it was decided to carry out unit safety periodic reviews according to types of series. A program was set up in order to achieve regular assessments on the aging of the facilities. This program, combining all the skills within EDF and the manufacturers, is a guarantee for the coherence and the exhaustivity of the consideration as it relies on a great number of evaluation areas. It seems to day that under operational conditions, an appropriate surveillance and maintenance of components the 900 and 1300 MWe units should be able to fulfill the expected duty for a 40-year design life and very likely even longer. (author)

[The evolution of plant life span: facts and hypotheses].

Science.gov (United States)

2006-01-01

There are two different views on the evolution of life forms in Cormophyta: from woody plants to herbaceous ones or in opposite direction - from herbs to trees. In accordance with these views it is supposed that life span in plants changed in the course of evolution from many years (perennials) to few years (annuals, biennials), or went in reverse - from few years to many years. The author discusses the problems of senescence and longevity in Cormophyta in the context of various hypotheses of ageing (programmed death theory, mutation accumulation, antagonistic pleiotropy, disposable soma, genes of ageing, genes of longevity). Special attention is given to bio-morphological aspects of longevity and cases of non-ageing plants ("negative senescence", "potential immortality"). It is proposed to distinguish seven models of simple ontogenesis in Cormophyta that can exemplify the diversity of mechanisms of ageing and longevity. The evolution of life span in plants is considered as an indirect result of natural selection of other characteristics of organisms or as a consequence of fixation of modifications (episelectional evolution). It seems that short life span could emerge several times during evolution of one group of plants, thus favoring its adaptive radiation.

Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies

International Nuclear Information System (INIS)

Berg, R.; Stroinski, M.; Giachetti, R.

1994-02-01

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant battery chargers, inverters and uninterruptible power supplies important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already, experienced) and aging management program activities to the more generic results and recommendations presented herein

Life time of nuclear power plants and new types of reactors

International Nuclear Information System (INIS)

2003-05-01

This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

Optimization of life cycle management costs

International Nuclear Information System (INIS)

Banerjee, A.K.

1994-01-01

As can be seen from the case studies, a LCM program needs to address and integrate, in the decision process, technical, political, licensing, remaining plant life, component replacement cycles, and financial issues. As part of the LCM evaluations, existing plant programs, ongoing replacement projects, short and long-term operation and maintenance issues, and life extension strategies must be considered. The development of the LCM evaluations and the cost benefit analysis identifies critical technical and life cycle cost parameters. These open-quotes discoveriesclose quotes result from the detailed and effective use of a consistent, quantifiable, and well documented methodology. The systematic development and implementation of a plant-wide LCM program provides for an integrated and structured process that leads to the most practical and effective recommendations. Through the implementation of these recommendations and cost effective decisions, the overall power production costs can be controlled and ultimately lowered

Experiences with the technical cooperation project TC MEX 04/53. Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant. Management program of the plant life (PLIM)

International Nuclear Information System (INIS)

Arganis J, C.R.; Aguilar T, J.A.; Guevara M, A.; Garcia M, C.; Martinez G, R.R.; Griz C, M.M.; Sanchez M, M.A.; Diaz O, R.C.

2006-01-01

In the biennium 2005-2006 the project of technical cooperation with the International Atomic Energy Agency OIEA TC MEX 04/53 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Plant life handling program (PLIM)' was approved, which has as objective the one to begin the actions to apply the methodology of Handling of life of Plant (PLIM) in the Unit I (Ul) of the Laguna Verde Nucleo electric Central (CNLV), in order to obtain the Renovation of License (LR), in a long term (2020). To apply this methodology 5 systems they were selected, structures or components (SEC) to carry out the handling programs of the one aging (AMP), and PLIM which are: The encircling of the reactor core (Core Shroud), the pressure vessel of the reactor (Reactor Pressure Vessel), the one primary container (Primary Containment), the system of feeding water (Reactor Feed Water) and cables, which were not in this work to be of another nature. The report presents the more important aspects considered in these systems for their programs of AMP and PLIM, as like a revision of those selection processes and evaluation (screening and scoping) for the application of PLIM in the systems of the Ul of the CNLV. (Author)

Chemistry management system for nuclear power plants

International Nuclear Information System (INIS)

Nagasawa, Katsumi; Maeda, Katsuji

1998-01-01

Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

Identification of Bottlenecks in the Plant Life Cycle for Sustainable Conservation of Rare and Endangered Species

Directory of Open Access Journals (Sweden)

Giovanna Aronne

2017-07-01

Full Text Available Long term survival of a species relies on maintenance of genetic variability and natural selection by means of successful reproduction and generation turnover. Although, basic to monitor the conservation status of a plant species, life history data are rarely available even for threatened species due to the gap between the large amount of information required and the limits in terms of time and available economic resources to gather these data. Here, the focus on bottlenecks in life-cycle of rare endangered plant species is proposed as a resolving approach to address the challenges of feasible conservation actions. Basic considerations for this approach are: (a all biological and ecological studies on plant species can be scientifically important, but not all of them are equally relevant to conservation planning and management requirements; (b under a changing environment, long term survival of a species relies on generation turnover; (c for conservation purposes, priority should be given to studies aimed to focus on bottlenecks in the succession of generations because they prevent, or slow down natural selection processes. The proposed procedure, named Systematic Hazard Analysis of Rare-endangered Plants (SHARP, consists of a preliminary survey of the already available information on the species and two main components. The first component is the identification of the bottlenecks in the life cycle by means of field surveys. The second is the diagnosis of the causes of the bottleneck by appropriate experimental methods. The target is to provide researchers, managers and practitioners with substantiated indications for sustainable conservation measures.

Information management systems improve advanced plant design

International Nuclear Information System (INIS)

Turk, R.S.; Serafin, S.A.; Leckley, J.B.

1994-01-01

Computer-aided engineering tools are proving invaluable in both the design and operation of nuclear power plants. ABB Combustion Engineering's Advanced Light Water Reactor (ALWR) features a computerized Information Management System (IMS) as an integral part of the design. The System 80+IMS represents the most powerful information management tool for Nuclear Power Plants commercially available today. Developed by Duke Power Company specifically for use by nuclear power plant owner operators, the IMS consists of appropriate hardware and software to manage and control information flow for all plant related work or tasks in a systematic, consistent, coordinated and informative manner. A significant feature of this IMS is that it is primarily based on plant data. The principal design tool, PASCE (Plant Application and Systems from Combustion Engineering), is comprised of intelligent databases that describe the design and from which accurate plant drawings are created. Additionally the IMS includes, at its hub, a relational database management system and an associated document management system. The data-based approach and applications associated with the IMS were developed, and have proven highly effective, for plant modifications, configuration management, and operations and maintenance applications at Duke Power Company's operating nuclear plants. This paper presents its major features and benefits. 4 refs

The ASME Section 11 Special Working Group On Plant Life Extension

International Nuclear Information System (INIS)

Katz, L.R.

1990-01-01

The codes and standards applicable to plant life extension have not been identified in the U.S. at this time. However, several initiatives have been taken to establish specific codes and standards pertaining to nuclear plant life extension (PLEX). One of these initiatives, sponsored by ASME, is the Section XI Special Working Group on Plant Life Extension (SWG-PLEX). The SWG-PLEX reports to the ASME Section XI Subcommittee and is responsible for recommending or drafting rules and requirements for modifying Section XI to accommodate age-related degradation to support nuclear plant life extension. This paper summarizes the results and reports the activities of the SWG-PLEX during the 1989/1990 period

Development of a support system to make economic and technical assessments for the issues relating to plant life extension

International Nuclear Information System (INIS)

Takao, T.; Soneda, N.; Sakai, T.

1994-01-01

To realize the life extension of nuclear power plants, overall evaluation for the plant is required, which covers technology, economy such as cost of repair or/and replacement of components, and regal regulations for licensing. A prototype of integrated assessment support system for life extension ''INPLEX'' have developed in order to evaluate the technical and economic issues relating to the plant life extension and to make a life extension scenario. Analysis procedure of INPLEX is as follows. A comparison of the cost between the life extension and the reconstruction is made to see whether the life extension is cost effective or not. Next, components required detailed assessments are selected, and the residual life assessment of these components are made. After those procedures life extension measures are selected and the implementation time schedule is set on the basis of the formulas for predicting the degradation of the components and the component reliability data. Finally the implementation time schedule is optimized from the viewpoint of economy, and the life extension scenario is proposed. INPLEX also has the data base ''PRINS'', in which information and data related to life extension are registered, such as component degradation experiences, degradation management methodologies, degradation mitigation measures, and so on. PRINS can be referred at any time during the operation of INPLEX

Plant life extension program for Indian PHWR power plants - Actual experience and future plans

International Nuclear Information System (INIS)

Sharma, M.B.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

2002-01-01

concludes with a discussion of the strategies of plant life extension for future reactors where the emphasis will be on better and more automated tooling preparation, modular replacement, detailed planning, engineering, configuration control and management of outage. (author)

Advanced life-cycle management for an increased steam generator performance

International Nuclear Information System (INIS)

Beck, J.; Schwarz, T.; Bouecke, R.; Schneider, V.

2006-01-01

High steam generators performance is a prerequisite for high plant availability and possible life time extension. During operation, the performance is reduced by fouling of the heating tubes and by corrosion, resulting on a reduction of the heat-exchange area. Such steam generator degradation problems arise from mechanical degradation and a continuous ingress of non-volatile contaminants, i.e. corrosion products and salt impurities accumulated in the steam generators. In addition, the tube scales in general affect the steam generator thermal performance, which ultimately cause a reduction of power output. AREVA applied an integrated service for utilities to evaluate all operational parameters influencing the steam generator performance. The evaluation is assisted by a systematic approach to evaluate the major steam generator operational data. The different data are structured and indexed in a Cleanling-Matrix. The result of this matrix is a quantified, dimensionless figure, given as the Fouling Index. The Fouling Index allows to monitor the condition of steam generators, compare it to other plants and, in combination with a life-time management applied at several German utilities, it allows verified statements on the past operation. Based on these data, an extrapolation of the potential additional life-time of the component is possible. As such, the Fouling Index is a valuable tool concerning life-time extension considerations. The application of the cleanliness criteria in combination with operational data with respect to life-time monitoring and improvements of steam generator performance are presented. (author)

Nuclear power plant ageing management programmes in foreign countries

International Nuclear Information System (INIS)

Simola, K.; Laakso, K.; Pekkonen, A.

1992-09-01

The report describes ageing studies of nuclear power plants and research programmes on plant life extension in foreign countries. Ageing studies are aimed to ascertain that the availability and safety of components and structures can be maintained throughout the plant lifetime. In life extension programmes the purpose is to evaluate the technical and economical possibilities to extend the plant lifetime beyond the originally planned operation period, without reducing the plant safety. The main emphasis of the report is put on the ageing and life extension programmes in the United States. Besides the U.S. studies, research on plant life extension possibilities conducted in France and Japan are also described. Examples of studies performed in other nuclear energy producing countries are given. These examples are mainly related to the development of maintenance programmes and techniques

Condition Based Prognostics of Passive Components - A New Era for Nuclear Power Plant Life Management

International Nuclear Information System (INIS)

Bakhtiari, S.; Mohanty, S.; Prokofiev, I.; Tregoning, R.

2012-01-01

As part of a research project sponsored by the U.S. NRC, Argonne National Laboratory (ANL) conducted scoping studies to identify viable and promising sensors and techniques for in-situ inspection and real-time monitoring of degradation in nuclear power plant (NPP) systems, structures, and components (SSC). Significant advances have been made over the past two decades toward development of online monitoring (OLM) techniques for detection, diagnostics, and prognostics of degradation in active nuclear power plant (NPP) components (e.g., pumps, valves). However, early detection of damage and degradation in safety-critical passive components, (e.g. piping, tubing pressure vessel), is challenging, and will likely remain so for the foreseeable future. Ensuring the structural integrity of the reactor pressure vessel (RPV) and piping systems in particular is a prerequisite to long term safe operation of NPPs. The current practice is to implement inservice inspection (ISI) and preventive maintenance programs. While these programs have generally been successful, they are limited in that information is only obtained during plant outages. Additionally, these inspections, often the critical path in the outage schedule, are costly, time consuming, and involve potentially high dose to nondestructive examination/evaluation (NDE) personnel. A viable plant-wide on-line structural health monitoring program for continuous and automatic monitoring of critical SSCs could be a more effective approach for guarding against unexpected failures. Specifically, OLM information about the current condition of the SSCs could be input to an online prognostics (OLP) system to forecast their remaining useful life in real time. This paper provides an overview of scoping studies performed at ANL on assessing the viability of OLM and OLP systems for real time and automated monitoring and remaining of condition and the remaining useful life of passive components in NPPs. (author)

Interrelationships of food safety and plant pathology: the life cycle of human pathogens on plants.

Science.gov (United States)

Barak, Jeri D; Schroeder, Brenda K

2012-01-01

Bacterial food-borne pathogens use plants as vectors between animal hosts, all the while following the life cycle script of plant-associated bacteria. Similar to phytobacteria, Salmonella, pathogenic Escherichia coli, and cross-domain pathogens have a foothold in agricultural production areas. The commonality of environmental contamination translates to contact with plants. Because of the chronic absence of kill steps against human pathogens for fresh produce, arrival on plants leads to persistence and the risk of human illness. Significant research progress is revealing mechanisms used by human pathogens to colonize plants and important biological interactions between and among bacteria in planta. These findings articulate the difficulty of eliminating or reducing the pathogen from plants. The plant itself may be an untapped key to clean produce. This review highlights the life of human pathogens outside an animal host, focusing on the role of plants, and illustrates areas that are ripe for future investigation.

Oconee: Is life extension in the cards for plants of this vintage

International Nuclear Information System (INIS)

Killian, D.E.; Moore, K.E.; Tally, C.W.

1986-01-01

Recent nuclear-industry interest in plant life extension is prompted by the realization that the economics of plant life extension are clearly favorable. Studies sponsored by the Electric Power Research Institute (EPRI) show that replacing even the most costly nuclear components can easily be justified, if the life of the plant can be extended just a few years. This may not be apparent for the early, small plants, but its applicability to the larger plants that started to appear in the early 70s-such as the three 860-MW Oconee units-is hard to dispute. The large capital investment in the typical nuclear station and extensive decommissioning costs add impetus to life-extension efforts. The same is true for fossil plants, and they are being successfully refurbished to extend their operating lives. Refurbishment of a fossil plant is comparatively simple, however, especially with regard to licensing and environmental qualifications where recognized standards are already in place. In the case of nuclear plants, much work must be done before all the pertinent issues and alternatives are identified. Potentially conflicting objectives may require resolution before a utility makes long-term decisions about life extension. For example, a utility may decide to designate a plant to accommodate grid load swings. In the near term, this may be a logical choice. However, the long-term negative aspects of component thermal cycling should be considered, especially if plant life extension is deemed important

Life cycle management for equipments in nuclear plants based on reliability and actual conditions

International Nuclear Information System (INIS)

Dalin, Wang; Jingquan, Liu; Peng, Liu

2010-01-01

Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (authors)

Fast-slow continuum and reproductive strategies structure plant life-history variation worldwide.

Science.gov (United States)

Salguero-Gómez, Roberto; Jones, Owen R; Jongejans, Eelke; Blomberg, Simon P; Hodgson, David J; Mbeau-Ache, Cyril; Zuidema, Pieter A; de Kroon, Hans; Buckley, Yvonne M

2016-01-05

The identification of patterns in life-history strategies across the tree of life is essential to our prediction of population persistence, extinction, and diversification. Plants exhibit a wide range of patterns of longevity, growth, and reproduction, but the general determinants of this enormous variation in life history are poorly understood. We use demographic data from 418 plant species in the wild, from annual herbs to supercentennial trees, to examine how growth form, habitat, and phylogenetic relationships structure plant life histories and to develop a framework to predict population performance. We show that 55% of the variation in plant life-history strategies is adequately characterized using two independent axes: the fast-slow continuum, including fast-growing, short-lived plant species at one end and slow-growing, long-lived species at the other, and a reproductive strategy axis, with highly reproductive, iteroparous species at one extreme and poorly reproductive, semelparous plants with frequent shrinkage at the other. Our findings remain consistent across major habitats and are minimally affected by plant growth form and phylogenetic ancestry, suggesting that the relative independence of the fast-slow and reproduction strategy axes is general in the plant kingdom. Our findings have similarities with how life-history strategies are structured in mammals, birds, and reptiles. The position of plant species populations in the 2D space produced by both axes predicts their rate of recovery from disturbances and population growth rate. This life-history framework may complement trait-based frameworks on leaf and wood economics; together these frameworks may allow prediction of responses of plants to anthropogenic disturbances and changing environments.

Proactive pressure relief system management of life cycle and ageing in nuclear power plants

International Nuclear Information System (INIS)

Kolenc, J.; Ferrar, S.

2011-01-01

The last major power nuclear station built in North America was built when the Altair Company introduced the first microcomputer sparking the PC frenzy. It is safe to assume that there have been a great many changes since 1977 on both accounts. As the world's aging nuclear plants continue to be challenged with maintenance and replacement issues (obsolescence), as well making improvements within their facilities, proper pressure relief system management looms as a growing concern. This problem grows more acute as new engineering best practices are promulgated across industries and regulatory standards become more rigorous with much stricter enforcements. Unlike most pieces of operating equipment in a nuclear facility, pressure relief devices demand an extra level of consideration; as they form the 'last line of defense'. Combine the on-going obsolescence issue, with today's ever increasing demands for overall plant and public safety; pressure relief safety management will require increasing 'proactive' efforts to ensure safe facilities. This paper has been written to address some global pressure relief system management issues with respect the worlds aging nuclear facilities. This paper reflects findings we have discovered while conducting engineering pressure relief system audits on various nuclear power stations. It should be noted that these finding are not atypical of similar findings in pressure relief systems in the hydrocarbon processing world. (author)

UNIRAM modeling for increased nuclear-plant availability and life extension

International Nuclear Information System (INIS)

O'Mara, R.L.

1988-01-01

At the start of a nuclear-power plant's design life of 40 years, most parts of the plant are effectively brand new, but some subcomponents have already experienced significant wear and aging effects. In short, the spectrum of where each component is in its life cycle at any time is quite broad, and this makes the prediction of the future availability of the plant a complex issue. Predictive models that account for the differential effects of aging, wear, and functional failure on the plant are desirable as a means to represent this complex behavior. This paper addresses the task of using a computer model to account for the relationships between components, systems, and plant availability, in the context of current and future needs, including eventual life extension. The computer model is based on the Electric Power Research Institute's (EPRI) code, UNIRAM, which has a large and growing user base among utilities

Plant/life form considerations in the rangeland hydrology and erosion model (RHEM)

Science.gov (United States)

Resilience of rangeland to erosion has largely been attributed to adequate plant cover; however, plant life/growth form, and individual species presence can have a dramatic effect on hydrologic and erosion dynamics on rangelands. Plant life/growth form refers to genetic tendency of a plant to grow i...

Development of JOYO Plant Operation Management Expert Tool (JOYPET)

International Nuclear Information System (INIS)

Michino, Masanobu; Terano, Toshihiro; Hanawa, Mikio; Aoki, Hiroshi; Okubo, Toshiyuki

2000-03-01

The Operation and Maintenance Support Systems for JOYO are being developed, with the aim of ensuring the stable and safe operation of JOYO and improving operational reliability of future FBR plants. Plant Operation Management Expert Tool named JOYPET had been developed as one of the Operation and Maintenance Support Systems, which helps plant operation management. The following functions were developed and applied. (1) Papers management (Plant status management) function for maintenance activities, (2) Isolation management support function for plant operation, (3) Automatically drawing function of plant operation schedule, (4) Isolation judgment function for plant operation. By use this system, the plant management of JOYO was able to improved reliability and reduced manpower. (author)

Computerized management of plant intervention tasks

International Nuclear Information System (INIS)

Quoidbach, G.

2004-01-01

The main objective of the 'Computerized Management of Plant Intervention Tasks' is to help the staff of a nuclear or a conventional power plant or of any other complex industrial facility (chemical industries, refineries, and so on) in planning, organizing, and carrying out any (preventive or corrective) maintenance task. This 'Computerized Management of Plant Intervention Tasks' is organized around a data base of all plant components in the facility that might be subjected to maintenance or tagout. It allows to manage, by means of intelligent and configurable 'mail service', the course of the intervention requests as well as various treatments of those requests, in a safe and efficient way, adapted to each particular organization. The concept of 'Computerized Management' of plant intervention tasks was developed by BELGATOM in 1983 for the Belgian nuclear power plants of ELECTRABEL. A first implementation of this concept was made at that time for the Doel NPP under the name POPIT (Programming Of Plant Intervention Tasks). In 1988, it was decided to proceed to a functional upgrade of the application, using advanced software and hardware techniques and products, and to realize a second implementation in the Tihange NPP under the name ACM (Application Consignation Maintenance). (author)

Plant life management. Progress for structural integrity

International Nuclear Information System (INIS)

Solin, J.

2003-03-01

A joint project cluster of industry, VTT and other R and D suppliers is dealing with managing of lifetime of critical structures and components in energy and process industry. The research topics include systematic component lifetime management, data management, integrity and lifetime of pressure bearing components, non-destructive inspection, interactions of coolant and materials, environmentally assisted cracking and ageing of reactor internals. This Symposium is a compilation of selected papers describing an intermediate status of the projects after three years of research and development. (orig.)

Actions concerning nuclear power plant life evaluation

International Nuclear Information System (INIS)

Chocron, M.; Fabbri, S.; Mizrahi, R.; Savino, E.J.; Versaci, R.A.

1998-01-01

One of the main activities to be undertaken by CNEA will be to provide technological assistance to NASA in problems concerning NPP operation. Works on life extensions of NPP are included in these activities. To fulfill these requirements the Atomic Energy National Commission (CNEA) has constituted a technical committee for Nuclear Power Plants Support (CAPCEN). CAPCEN should be the knowledge reservoir of those issues concerning the performance, safety and life extension of Nuclear Power Plants. One of CAPCEN's most important activities is to promote research work connected with such issues. The main technical areas are: Pressure Vessel and Piping, Heat Exchanges and Fuel Channels and Reactor Inner Components. Efforts are focused on the identification of the main components susceptible of ageing, the study of their ageing mechanisms, the follow-up of their behaviour during operation, and the measures taken to extend their life. (author)

Lessons from plant management for achieving economic competitiveness for evolutionary reactors

International Nuclear Information System (INIS)

Andognini, G.

1999-01-01

Ontario Hydro, Canada's largest utility, has 20 nuclear power units of the CANDU design with a total design power of 15, 020 Electrical MW or about half of the total generating capacity. The performance of these plants, which were installed between the 1970s and early 1990s, was initially very good but worsened in recent years and the regulator expressed concerns about declining safety standards. In early 1997, an external Nuclear Performance Advisory Group led by Mr G. Carl Andognini was established and conducted an intensive assessment of the nuclear operation. That assessment ranked the operation of Ontario Hydro's plants as m inimally acceptable , noting a number of causes such as: lack of management leadership and accountability; poor safety culture; inadequate training; lack of configuration management; and, deficient organization. A recovery program is now underway, involving the laying-up of eight units to free resources to upgrade the remaining twelve. A number of lessons that can be drawn from the Ontario Hydro experience are presented. The key lessons include: the importance of having the light people, with the right qualifications in the right place, at the right time; the need for all staff to have a questioning attitude and to be committed to a s afety culture ; configuration management is essential - knowledge of the status of the plant must be maintained and all documentation kept up to date; maintenance must be given high priority and be provided adequate resources: defined standards are needed for the conduct of all work; the Directors (or equivalent) and senior management must understand the plant and appreciate the consequences of their decisions and actions. The paper concludes that good new designs are not sufficient by themselves to achieve economically competitive and safe nuclear plants - a high standard of operation and maintenance is also necessary throughout the life of the plants. (author)

Plant risk status information management system

International Nuclear Information System (INIS)

Campbell, D.J.; Ellison, B.C.; Glynn, J.C.; Flanagan, G.F.

1985-01-01

The Plant Risk Status Information Management System (PRISIMS) is a PC program that presents information about a nuclear power plant's design, its operation, its technical specifications, and the results of the plant's probabilistic risk assessment (PRA) in a logically and easily accessible format. PRISIMS provides its user with unique information for integrating safety concerns into day-to-day operational decisions and/or long-range management planning

Quality management of nuclear power plants

International Nuclear Information System (INIS)

Maxwell, D.A.; Hille, F.J.M.

1995-01-01

The paper discusses the various approaches to quality management and the progressive development from traditional quality assurance (QA) concepts through integrated and performance based quality management systems to total quality management. Experience has shown that in many cases the traditional implementation of QA in nuclear power plant life-cycle activities has resulted in limited benefits. The paper outlines the advantages of developing an integrated quality management system, which, besides satisfying the QA standards, focuses on the performance of an organization. This reflects the approach implicit in the proposed revisions of the IAEA QA standards (code and guides). Such a quality management system provides the framework within which processes are controlled to meet the business objectives and is capable of accommodating easily new requirements, such as environmental management. An integrated quality management system should not be focused specifically on regulatory (and hence nuclear safety) issues, but should constitute the whole management system of the organization, of which safety and the environment are of course important elements. The paper gives a practical example of this approach implemented company wide. This approach is similar to other approaches in place or being developed by many Foratom members. The paper also lists the components of total quality management, which is considered to constitute the future direction for the nuclear power industry. The quality management system is the primary vehicle to meet the fundamental objectives, but total quality can only be realized by developing the full potential of people through team work in order to continuously improve the system and the performance of the organization by focusing on internal as well as external customers. (author). 6 refs, 3 figs, 2 tab

The implications of plant design on the life-time costs for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Macphee, D.S.; Hexter, B.C.; Young, M.P.; Wilson, B.J.

1997-01-01

Utilising the experience gained during many years of design and project management of nuclear plant, BNFL is now approaching the final stages of the construction and commissioning of the Sellafield MOX Plant (SMP) in the UK. The paper uses the SMP project to highlight the benefits of these experiences, in particular addressing the implications of the approach to plant design on life time costs. In addition to providing BNFL with a state of the art, commercial scale MOX fuel fabrication facility, the construction of this 120 tHM/yr facility, which is currently in the advanced stages of commissioning, represents a significant demonstration of the design and project management skills of BNFL Engineering Ltd. As well as meeting the main process requirements, the plant design incorporates the highest standards of safety, together with input from the future plant operators and potential customers. As befits a commercial scale plutonium handling facility, SMP also incorporates material accountancy and security provisions that will meet all international requirements. Design, construction and commissioning of this complex and highly automated plant, has benefited from a totally integrated approach to design and documentation that considers not only project implementation but also overall lifetime costs. In addition, project management techniques, developed over many years of major project construction at Sellafield, have been utilised in order to ensure successful project implementation against a background of significant technical challenge and 'fast track' timescales. (author)

Near-term benefits of life extension planning for nuclear power plants

International Nuclear Information System (INIS)

Pickens, T.; Gregor, F.E.

1988-01-01

Life Extension of Nuclear Power Plants is now viewed as a realistic alternative to construction of new generating facilities. The subject has been under intensive study since 1984 and two comprehensive pilot plant programs have been completed under EPRI, U.S. Department of Energy and utility sponsorship. A major lesson learned from these studies is that planning for life extension must start early and that many activities must be implemented as early in life as possible to enhance the option for life extension through mitigate and preventive actions. It was also determined that achievement of a 40-year licensed life is by no means guaranteed without substantial effort during the remaining plant life. In examining these recommended actions, it becomes obvious that conscientious implementation also leads to realization of significant short-term benefits in the form of availability improvement, outage reduction, maintenance optimization and longer term planning decisions. In addition to the economic benefits, plant safety is also enhanced by reducing challenges to the safety systems and slowly switching from a corrective maintenance to a preventive maintenance program

Ageing management of nuclear power plant - the Tarapur experience

International Nuclear Information System (INIS)

Anilkumar, K.R.; Das, P.K.; Bhattacharjee, S.; Ramamurty, U.

2006-01-01

Tarapur Atomic Power Station, the longest serving Nuclear Power Plant in the Asian continent has completed 36 years of successful operation and generated more than 70,000 million units of electric power. Built in late sixties, with the state-of-the-art safety features prevailing then, TAPS through the process of evolution has become safer plant due to efforts of upgradation, renovation and refurbishment prompted by the station's operating experience, feed back from overseas reactors, lessons learnt from nuclear incidents, accidents and fresh review of design basis and safety analysis of the plant. All components of a Nuclear power plant experience some degradation with time. The Reactor Pressure Vessels (RPV) designed for 40 effective full power years (EFPY) of operation have operated for less than 20 EFPY and the material condition is assessed to be fit for some more years of service. The condition of the containment and main plant buildings was assessed to be satisfactory. The Ageing Management Programme (AMP) involved identification of key systems, structures and components (SSCs) that may experience degradation due to ageing, and take corrective measures through maintenance, repair and/or replacement. The identified components were classified as major critical components, important systems and other critical components. For each component mode of degradation was identified, ageing assessment was done and action plan was finalized. Replacement of some important equipment like 3 x 50 % capacity Emergency Diesel Generators (EDG) with 3 x 100 % capacity EDG, Salt Service Water (SSW) pumps, Control rod drive (CRD) pumps, Emergency Condenser tube bundles, Station battery has been done on the basis of condition monitoring and to obviate common cause failure and enhance the system reliability. Samples of Safety related cables were subjected to residual life assessment (RLA) and replacement action firmed up on the basis of the RLA findings. Condition survey of Main

Comparative life cycle assessment of biowaste to resource management systems - A Danish case study

DEFF Research Database (Denmark)

Thomsen, Marianne; Seghetta, Michele; Mikkelsen, Mette Hjorth

2017-01-01

Waste to Energy combustion plants currently process most of the organic fraction of the household waste. This study presents an assessment of the environmental performance of an increased circular bioresource management system obtained by reallocating the organic fraction of the household waste...... from combustion (Reference Scenario) to biogas and fertilizer production (Alternative Scenario). The goals defined in the Danish National resource action plan for waste management, i.e. 33% reduction of organic fraction household waste dry weight, is taken as a case study. A comparative life cycle...... assessment of the diverting of the organic fraction of the household waste away from a Waste to Energy combustion plant towards sludge- and manure-based biogas plants in North Zealand (Denmark) shows a net increase in renewable electricity production of 39% at the expense of a reduction in heat production...

Life Cycle Assessment of the MBT plant in Ano Liossia, Athens, Greece

International Nuclear Information System (INIS)

Abeliotis, Konstadinos; Kalogeropoulos, Alexandros; Lasaridi, Katia

2012-01-01

Highlights: ► We model the operation of an MBT plant in Greece based on LCA. ► We compare four different MBT operating scenarios (among them and with landfilling). ► Even the current operation of the MBT plant is preferable to landfilling. ► Utilization of the MBT compost and metals generates the most environmental gains. ► Thermal exploitation of RDF improves further the environmental performance of the plant. - Abstract: The aim of this paper is the application of Life Cycle Assessment to the operation of the MBT facility of Ano Liossia in the region of Attica in Greece. The region of Attica is home to almost half the population of Greece and the management of its waste is a major issue. In order to explicitly analyze the operation of the MBT plant, five scenarios were generated. Actual operation data of the MBT plant for the year 2008 were provided by the region of Attica and the LCA modeling was performed via the SimaPro 5.1 software while impact assessment was performed utilizing the Eco-indicator’99 method. The results of our analysis indicate that even the current operation of the MBT plant is preferable to landfilling. Among the scenarios of MBT operation, the one with complete utilization of the MBT outputs, i.e. compost, RDF, ferrous and non-ferrous metals, is the one that generates the most environmental gains. Our analysis indicates that the exploitation of RDF via incineration is the key factor towards improving the environmental performance of the MBT plant. Our findings provide a quantitative understanding of the MBT plant. Interpretation of results showed that proper operation of the modern waste management systems can lead to substantial reduction of environmental impacts and savings of resources.

Assessment and management of ageing of major nuclear power plant components important to safety: PWR pressure vessels. 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1120 documented ageing assessment and management practices for pressurized water reactor (PWR) reactor pressure vessels (RPVs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. primary water stress corrosion cracking (PWSCC) of Alloy 600 control rod drive mechanism (CRDM) penetrations and boric acid corrosion/wastage of RPV heads, which threatened the integrity of the RPV heads. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1120 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update IAEA-TECDOC-1120 in order to provide current ageing management guidance for PWR RPVs to all involved in the operation and regulation of PWRs and thus to help ensure PWR RPV integrity in IAEA Member States throughout their entire service life

Advanced chemistry management system for nuclear power plants

International Nuclear Information System (INIS)

Maeda, Katsuji; Kobayashi, Yasuhiro; Nagasawa, Katsumi

2000-01-01

Chemistry control in a boiling water reactor (BWR) plant has a close relationship with radiation field buildup, fuel reliability, integrity of plant components and materials, performance of the water treatment systems and radioactive waste generation. Chemistry management in BWR plants has become more important in order to maintain and enhance plant reliability. Adequate chemistry control and management are also essential to establish, maintain, and enhance plant availability. For these reasons, we have developed the advanced chemistry management system for nuclear power plants in order to effectively collect and evaluate a large number of plant operating and chemistry data. (author)

Integrated approach to knowledge acquisition and safety management of complex plants with emphasis on human factors

International Nuclear Information System (INIS)

Kosmowski, K.T.

1998-01-01

In this paper an integrated approach to the knowledge acquisition and safety management of complex industrial plants is proposed and outlined. The plant is considered within a man-technology-environment (MTE) system. The knowledge acquisition is aimed at the consequent reliability evaluation of human factor and probabilistic modeling of the plant. Properly structured initial knowledge is updated in life-time of the plant. The data and knowledge concerning the topology of safety related systems and their functions are created in a graphical CAD system and are object oriented. Safety oriented monitoring of the plant includes abnormal situations due to external and internal disturbances, failures of hard/software components and failures of human factor. The operation and safety related evidence is accumulated in special data bases. Data/knowledge bases are designed in such a way to support effectively the reliability and safety management of the plant. (author)

Fast-slow continuum and reproductive strategies structure plant life-history variation worldwide

DEFF Research Database (Denmark)

Salguero-Gómez, Roberto; Jones, Owen R; Jongejans, Eelke

2016-01-01

The identification of patterns in life-history strategies across the tree of life is essential to our prediction of population persistence, extinction, and diversification. Plants exhibit a wide range of patterns of longevity, growth, and reproduction, but the general determinants of this enormous...... variation in life history are poorly understood. We use demographic data from 418 plant species in the wild, from annual herbs to supercentennial trees, to examine how growth form, habitat, and phylogenetic relationships structure plant life histories and to develop a framework to predict population...

Complex investigations for the technical diagnosis and constructive optimization of the pipe systems from Rovinari power plant to extend their remaining life

Energy Technology Data Exchange (ETDEWEB)

Delamarian, C. [Technischer Ueberwachungs-Verein Sueddeutschland (TUeV), Muenchen (Germany); Lupescu, L.; Nicolescu, N. [Institutul de Studii si Proiectari Energetice, Bucharest (Romania); Pisc, I.; Botis, A. [ISIM, Timisoara (Romania)

2003-07-01

The remnant life assessment of power plant components is an issue of a high importance all over the Europe and not only. The need of power products, the environmental-related restrictions within this field as well as the task of lowering the fabrication costs led to and increased importance of maintenance and retrofit activities of old power equipment during the last decade. Replacement of pipe lines exceeding their designed life is no longer regarded as an option for power plant managers. Instead, life assessment techniques combined with state of the art design and fabrication methods focusing on the replacement of damaged components as well as redesign of pipe line systems in order to eliminate overloading and/or secondary stresses that usually lead to premature life exhaustion are only some of the issues discussed within this paper. It deals with the retrofit of a conventional power plant (Group no. 3 of Rovinari Power Plant) which reached its designed life after about 110.000 operating hours. The need of improvement of the boiler efficiency as well as the extension of the plant life, maintaining in the same time old, but still good components determined the three companies (ISPE, ISIM and TUeV) to gather their skills in order to reach this task. (orig.)

Life cycle management of analytical methods.

Science.gov (United States)

Parr, Maria Kristina; Schmidt, Alexander H

2018-01-05

In modern process management, the life cycle concept gains more and more importance. It focusses on the total costs of the process from invest to operation and finally retirement. Also for analytical procedures an increasing interest for this concept exists in the recent years. The life cycle of an analytical method consists of design, development, validation (including instrumental qualification, continuous method performance verification and method transfer) and finally retirement of the method. It appears, that also regulatory bodies have increased their awareness on life cycle management for analytical methods. Thus, the International Council for Harmonisation of Technical Requirements for Pharmaceuticals for Human Use (ICH), as well as the United States Pharmacopeial Forum discuss the enrollment of new guidelines that include life cycle management of analytical methods. The US Pharmacopeia (USP) Validation and Verification expert panel already proposed a new General Chapter 〈1220〉 "The Analytical Procedure Lifecycle" for integration into USP. Furthermore, also in the non-regulated environment a growing interest on life cycle management is seen. Quality-by-design based method development results in increased method robustness. Thereby a decreased effort is needed for method performance verification, and post-approval changes as well as minimized risk of method related out-of-specification results. This strongly contributes to reduced costs of the method during its life cycle. Copyright © 2017 Elsevier B.V. All rights reserved.

AVLIS Production Plant Project Management Plan

International Nuclear Information System (INIS)

1984-01-01

The AVLIS Production Plant is designated as a Major System Acquisition (in accordance with DOE Order 4240.IC) to deploy Atomic Vapor Laser Isotope Separation (AVLIS) technology at the Oak Ridge, Tennessee site, in support of the US Uranium Enrichment Program. The AVLIS Production Plant Project will deploy AVLIS technology by performing the design, construction, and startup of a production plant that will meet capacity production requirements of the Uranium Enrichment Program. The AVLIS Production Plant Project Management Plan has been developed to outline plans, baselines, and control systems to be employed in managing the AVLIS Production Plant Project and to define the roles and responsibilities of project participants. Participants will develop and maintain detailed procedures for implementing the management and control systems in agreement with this plan. This baseline document defines the system that measures work performed and costs incurred. This plan was developed by the AVLIS Production Plant Project staff of Martin Marietta Energy Systems, Inc. and Lawrence Livermore National Laboratory in accordance with applicable DOE directives, orders and notices. 38 figures, 19 tables

How to deal with financial risk under the life circles of nuclear power plant

International Nuclear Information System (INIS)

Chen Shilong

2010-01-01

Nuclear power plants don't necessarily form enterprise boundary, in the background of nuclear power booming, what characteristics of financial risk exist in nuclear power plant, how to deal with such financial risk and how to sustain a stable development of nuclear power ? Based on the enterprise boundary theory of transaction fees, the separate of the nuclear power plant owner, engineering company and operating company comply with the cost-efficient principle. The financial risk of the plant owner come from the cash flow characteristics under different life circles of its nuclear power plants, due to the passivation of the asset structure in the construction and early operation periods, considering the effects of asset structure on financial risk is meaningless. Based on the owners with single reactor or constructing reactors, big-scale investment holding company is needed to conduct professional asset management, and to diversify the financial risk, on the other hand, professional engineering and operation companies can realize the scale and the multi-reactor advantages. (author)

Development of life evaluation technology for nuclear power plant components

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

2001-03-15

This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

Principles for ecologically based invasive plant management

Science.gov (United States)

Jeremy J. James; Brenda S. Smith; Edward A. Vasquez; Roger L. Sheley

2010-01-01

Land managers have long identified a critical need for a practical and effective framework for designing restoration strategies, especially where invasive plants dominate. A holistic, ecologically based, invasive plant management (EBIPM) framework that integrates ecosystem health assessment, knowledge of ecological processes, and adaptive management into a successional...

Ecological life histories of the three aquatic nuisance plants, Myriophyllum spicatum, Potamogeton crispus and Elodea canadensis

Science.gov (United States)

Nichols, S.A.; Shaw, B.H.

1986-01-01

The life histories of Myriophyllum spicatum L., Elodea canadensis Michx., and Potamogeton crispus L., serious aquatic nuisances in many regions of the world, are reviewed to provide insights into the life style of successful aquatic nuisance plants. Specifically, their distribution and spread in North America; their life cycle, productive and reproductive potential; and their ecosystem relationships are reviewed. Hopefully this review will improve a manager's ability to deal with aquatic nuisance problems. It also provides suggestions for basic research needed to develop more effective management practices. It was found that all three species possess a number of adaptations, including an ability to rapidly propagate vegetatively, an opportunistic nature for obtaining nutrients, a life cycle that favors cool weather, and a number of mechanisms which enhance photosynthetic efficiency, which allow them to proliferate. These three species do provide benefits to the ecosystem through their roles in materials cycling and energy flow. Therefore, management of these species should take an integrated approach which recognizes these benefits. The life history information available about the three species varies tremendously; however, a better understanding of resource gain and allocation is needed to manage all three species. Specifically, more research is needed to provide a better understanding of: 1) the role bicarbonate plays in photosynthesis, 2) the role roots play in supplying CO2 to the plabts, 3) resource accumulation and allocation under different temperature and light regimes, 4) resource allocation on a seasonal basis, and 5) nutrient cycling under different management regimes. ?? 1986 Dr W. Junk Publishers.

Computerized management of plant intervention tasks

International Nuclear Information System (INIS)

Remacle, J.; Quoidbach, G.

1993-01-01

The concept of 'computerized management' of plant intervention tasks was developed by TRACTEBEL in 1983 for the Belgian power plants of ELECTRABEL. The main objective of the 'Computerized Management of Plant Intervention Tasks' is to help the staff of a nuclear or a conventional power plant in planning, organizing, and carrying out any (preventive or corrective) maintenance task. It consists of a group of interconnected functional modules acting on a unique and homogeneous data base. A short description of 3 modules is given, i.e., the 'User' Module, the 'Equipment' Module and the 'Periodic Procedure' Module. (Z.S.)

Nuclear power plants life extension and decommissioning its economic aspects

International Nuclear Information System (INIS)

Watanabe, Yoshiaki

1994-06-01

In USA where the development of nuclear power was started early, the life of nuclear power plants expires successively around the turn of century, and the serious hindrance to electric power supply is feared. Therefore, the research for extending 40 year approved period of operation is in progress. By the extension of life of nuclear power plants, huge cost reduction is estimated as compared with the construction of new plants. However, due to the rise of the cost for the life extension, there were the cases of forced decommissioning. In this book, the present state of the life extension of nuclear power stations, the economical assessment and analysis of the life extension by DOE, the economical assessment by MIDAS method of Electric Power Research Institute, the economical assessment by cost-benefit method of Northern States Power Co., the assessment of the long term operation possibility of nuclear power stations, the economical assessment system for the life extension in Japan, the present state of the decommissioning of nuclear power stations and that in USA, Canada and Europe, the assessment of the decommissioning cost by OECD/NEA, and the decommissioning cost for thermal power stations are described. (K.I.)

Combined cycle power plants: A comparison between two different dynamic models to evaluate transient behaviour and residual life

International Nuclear Information System (INIS)

Benato, Alberto; Stoppato, Anna; Bracco, Stefano

2014-01-01

Highlights: • Two procedures aimed at simulating the dynamic behaviour of power plants are compared. • They both are aimed at predicting the residual life of plant devices. • A single pressure gas-steam combined plant has been modelled. • A good correspondence has been found despite the different approaches used. - Abstract: The deregulated energy market and the increasing quota of electrical capacity covered by non-predictable renewable sources require strongly irregular and discontinuous operation of thermoelectric plants to satisfy users demand and compensate the variability of renewable sources. As a consequence, due to thermo-mechanical fatigue, creep and corrosion, a lifetime reduction of the most critical components occurs. The availability of a procedure able to predict the residual life of plant devices is necessary to assist the management decisions about power plants’ operation and maintenance scheduling. The first step of this procedure is the capability of simulating the plant behaviour versus time by evaluating the trends of the main thermodynamic parameters that describe the plant operation during different transient periods. In this context, the main contribution of the present paper is to propose a complete procedure able to simulate the plant dynamic behaviour and estimate the residual life reduction of some components. Indeed, two different models, developed by two different research groups, of the same single pressure heat recovery steam generator unit are presented and utilized to characterize the dynamic behaviour of the above mentioned power plant. The main thermodynamic variables during different transient operation conditions are predicted and good correspondence between the two methods is obtained. It can be also noted that, when the geometry and size of the devices are considered, the thermal inertia related to heat exchangers tubes, pipes and other physical masses causes a delay in the system response. Moreover, a residual life

Management strategies for nuclear power plant outages

International Nuclear Information System (INIS)

2006-01-01

More competitive energy markets have significant implications for nuclear power plant operations, including, among others, the need for more efficient use of resources and effective management of plant activities such as on-line maintenance and outages. Outage management is a key factor for safe, reliable and economic plant performance and involves many aspects: plant policy, coordination of available resources, nuclear safety, regulatory and technical requirements, and all activities and work hazards, before and during the outage. The IAEA has produced this report on nuclear power plant outage management strategies to provide both a summary and an update of a follow-up to a series of technical documents related to practices regarding outage management and cost effective maintenance. The aim of this publication is to identify good practices in outage management: outage planning and preparation, outage execution and post-outage review. As in in the related technical documents, this report aims to communicate these practices in such a way that they can be used by operating organizations and regulatory bodies in Member States. The report was prepared as part of an IAEA project on continuous process improvement. The objective of this project is to increase Member State capabilities in improving plant performance and competitiveness through the utilization of proven engineering and management practices developed and transferred by the IAEA

IAEA guidance on ageing management for nuclear power plants. Guidance on effective management of the physical ageing of systems, structures and components important to safety for nuclear power plants. Overview. Programmatic guidelines. Component specific guidelines. Review guidelines. Version 1, 2002

International Nuclear Information System (INIS)

2002-01-01

Operational experience shows that excellent plant safety and excellent performance go hand in hand, and that they are achieved by effective leadership and management that includes a unified approach to safety and production. This is also applicable to ageing management. Effective ageing management leads to both enhanced plant safety and enhanced performance and is a prerequisite for long service life. The IAEA project on Safety Aspects of NPP Ageing has produced since 1990 a comprehensive set of programmatic and component specific guidelines on managing ageing, while providing an interactive environment for information exchange and co-operation among practitioners, and has assisted Member States in the application of the guidelines through the provision of training and advice. The objective of the CD-ROM is to preserve the IAEA's guidance on ageing management and to facilitate its retrieval, updating, extension and dissemination in order to help increase the effectiveness of ageing management at nuclear power plants

Technology and testing for the extension of plant life

International Nuclear Information System (INIS)

Blumer, U.R.; Edelmann, X.

1988-01-01

This paper describes selected portions of a recommended program for the application of equipment-manufacturing-related technology and testing for the extension of life for operating nuclear power plants. It is appropriate to mention that the Swiss nuclear plants, their staffs, and the supporting Swiss nuclear industry are rightfully proud of their record of performance. Plant staffs have been intimately involved in system and equipment design and engineering from the very beginnings of their plants. Maintenance of the plant systems and equipment is referred to as engineering rather than maintenance, because it is viewed as a technical effort and an extension of the original plant and equipment design and construction effort. Care, competence, cleanliness, and attention to detail have been bywords for the Swiss plants. Success has been demonstrated through enviable availability performance. With operation and availability capability already demonstrated, the Swiss are now turning their attention to the extension of plant life. This summary describes some aspects of this work, which is fundamentally based on the application of technology and testing skills developed for equipment manufacture and the original installation of this equipment in the plants, but has been enhanced by research and development (R and D) and an ongoing effort to serve utilities in their maintenance activities

Computational models for residual creep life prediction of power plant components

International Nuclear Information System (INIS)

Grewal, G.S.; Singh, A.K.; Ramamoortry, M.

2006-01-01

All high temperature - high pressure power plant components are prone to irreversible visco-plastic deformation by the phenomenon of creep. The steady state creep response as well as the total creep life of a material is related to the operational component temperature through, respectively, the exponential and inverse exponential relationships. Minor increases in the component temperature can thus have serious consequences as far as the creep life and dimensional stability of a plant component are concerned. In high temperature steam tubing in power plants, one mechanism by which a significant temperature rise can occur is by the growth of a thermally insulating oxide film on its steam side surface. In the present paper, an elegantly simple and computationally efficient technique is presented for predicting the residual creep life of steel components subjected to continual steam side oxide film growth. Similarly, fabrication of high temperature power plant components involves extensive use of welding as the fabrication process of choice. Naturally, issues related to the creep life of weldments have to be seriously addressed for safe and continual operation of the welded plant component. Unfortunately, a typical weldment in an engineering structure is a zone of complex microstructural gradation comprising of a number of distinct sub-zones with distinct meso-scale and micro-scale morphology of the phases and (even) chemistry and its creep life prediction presents considerable challenges. The present paper presents a stochastic algorithm, which can be' used for developing experimental creep-cavitation intensity versus residual life correlations for welded structures. Apart from estimates of the residual life in a mean field sense, the model can be used for predicting the reliability of the plant component in a rigorous probabilistic setting. (author)

Swiss regulatory use of databanks for nuclear power plant life management, surveillance and safety analyses

International Nuclear Information System (INIS)

Tipping, Ph.; Beutler, R.; Schoen, G.; Noeggerath, J.

2002-01-01

the type of input required and the necessary quality assurance (QA) for the data. It is shown that record keeping and DBs on reportable incidents, PSA data and material degradation in NPPs have an increasingly important and integral role to play in increasing reliability, safety and maintaining NPP operational and life management goals. Lessons learned provide the foundation for creating vigilant and questioning attitudes, which are essential for maintaining safety. Safe operation of a NPP is clearly a prerequisite for optimum plant performance and life management. (author)

A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun [KHNP CRI, Daejeon (Korea, Republic of)

2012-10-15

Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS.

A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

International Nuclear Information System (INIS)

Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun

2012-01-01

Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS

Low-level radioactive waste associated with plant life extension

International Nuclear Information System (INIS)

Sciacca, F.; Zigler, G.; Walsh, R.

1992-01-01

Many utilities operating nuclear power plants are expected to seek to extend the useful life of their plants through license renewal. These US Nuclear Regulatory Commission (NRC) licensees are expected to implement enhanced inspection, surveillance, testing, and monitoring (ISTM) as needed to detect and mitigate age-related degradation of important structures, systems, and components (SSCs). In addition, utilities may undertake various refurbishment and upgrade activities at these plants to better assure economic and reliable power generation. These activities performed for safety and/or economic reasons can result in radioactive waste generation, which is incremental to that generated in the original licensing term. Work was performed for the NRC to help define and characterize potential environmental impacts associated with nuclear plant license renewal and plant life extension. As part of this work, projections were made of the types and quantities of low-level radioactive waste (LLRW) likely to be generated by licensee programs. These projections were needed to estimate environmental impacts related to the disposal of such wastes

Problems and Perspectives of Life Management Theory

OpenAIRE

Hirata, Michinori

2001-01-01

This paper examines the problems of life management theory and shows the directions of researches in this field. I examine the directions of research in home management theory, which is antecedents of life management theory. There are three directions of research in home management theory. The first direction is to make clear the problems of people's family lives in terms of time use, money expenditure, family relations and so on. The second direction is to examine the home management itself....

An approach to systematic structural lifetime management

International Nuclear Information System (INIS)

Talja, H.; Solin, J.; Rintamaa, R.

2000-01-01

Many utilities are currently developing preventive maintenance and plant life management systems for their own use. Consideration of plant specific design and integrity problems support use of tailored programs and/or data bases for plant life management. The final applications will be developed on plant type, utility, plant or system level. However, common features can be included in the systems. The project Plant life management XVO conducted at VTT deals - as a whole - with systematic component lifetime management, operational loads in normal steady state operation and in transients, especially piping vibrations and integrity, NDE, materials ageing, interactions of coolant and materials, environmentally assisted cracking and ageing of reactor internals. One of the major challenges in the project is to define, how these multidisciplinary results should be integrated such that quantitative assessments on remaining safe life and failure risks are possible. In this paper a brief overview on the project is given. The work performed on piping vibration and integrity management is presented in more detail. (author)

Life cycle analysis of photovoltaic cell and wind power plants

International Nuclear Information System (INIS)

Uchiyama, Yohji

1997-01-01

The paper presents life cycle analyses of net energy and CO 2 emissions on photovoltaic cell and wind power generation plants. Energy requirements associated with a plant are estimated for producing materials, manufacturing equipment, constructing facilities, acid operating plants. Energy ratio and net supplied energy are calculated by the process energy analysis that examines the entire energy inventory of input and output during life time of a plant. Life cycle CO 2 emission can also be calculated from the energy requirements obtained by the net energy analysis. The emission also includes greenhouse effect equivalent to CO 2 emission of methane gas leakage at a mining as well as CO 2 emissions from fossil fuel combustion during generating electricity, natural gas treatment at an extracting well and cement production in industry. The commercially available and future-commercial technologies are dealt with in the study. Regarding PV technologies, two different kinds of installation are investigated; roof-top typed installation of residential houses and ground installation of electric utilities. (author)

Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals: 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1119 documents ageing assessment and management practices for PWR Reactor Vessel Internals (RVIs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. irradiation assisted stress corrosion cracking (IASCC) of baffle-former bolts, which threatened the integrity of the vessel internals. In addition, concern of fretting wear of control rod guide tubes has been raised in Japan. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1119 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update relevant sections of the existing IAEA-TECDOC- 1119 in order to provide current ageing management guidance for PWR RVIs to all involved in the operation and regulation of PWRs and thus to help ensure PWR safety in IAEA Member States throughout their entire service life

Cost savings from extended life nuclear plants

International Nuclear Information System (INIS)

Forest, L.R. Jr.; Deutsch, T.R.; Schenler, W.W.

1988-09-01

This study assesses the costs and benefits of nuclear power plant life extension (NUPLEX) for the overall US under widely varying economic assumptions and compares these with alternative new coal- fired plants (NEWCOAL). It is found that NUPLEX saves future electricity consumers more than 3 cents/-kwh compared with NEWCOAL. The NUPLEX costs and benefits for existing individual US nuclear power plants under base-line, or most likely, assumptions are assessed to determine the effects of the basic plant design and plant age. While benefits vary widely, virtually all units would have a positive benefit from NUPLEX. The study also presents a cost-benefit analysis of the nuclear industry's planned advanced light water reactor (ALWR). It is concluded that ALWR offers electrical power at a substantially lower cost than NEWCOAL. 9 refs., 6 figs

Information management system for design, construction and operation of nuclear power plants

International Nuclear Information System (INIS)

Bolch, M.C.; Jones, C.R.

1990-01-01

This paper describes the principal requirements and features of a computerized information management system (IMS) believed to be a necessary part of the program to design, build and operate the next generation of nuclear power plants in the United States. This way a result of extensive review and input from an industry group studying future nuclear power plant construction improvements. The needs of the power plant constructor, owner and operator for such a computerized technical data base are described in terms of applications and scope and timing of turnover of the IMS by the plant designer. The applications cover the full life cycle of the plant including project control, construction activities, quality control, maintenance and operation. The scope of the IMS is also described in terms of the technical data to be included, hardware and software capabilities and training. The responsibilities of the plant designer for developing the IMS and generating the technical data base is defined as part of the plant process. The requirements to be met include a comprehensive plant data model and computer system hardware and software

Information management system for design, construction and operation of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Bolch, M.C. (Duke Power Co. (US)); Jones, C.R. (S. Levy Inc. (US))

1990-01-01

This paper describes the principal requirements and features of a computerized information management system (IMS) believed to be a necessary part of the program to design, build and operate the next generation of nuclear power plants in the United States. This way a result of extensive review and input from an industry group studying future nuclear power plant construction improvements. The needs of the power plant constructor, owner and operator for such a computerized technical data base are described in terms of applications and scope and timing of turnover of the IMS by the plant designer. The applications cover the full life cycle of the plant including project control, construction activities, quality control, maintenance and operation. The scope of the IMS is also described in terms of the technical data to be included, hardware and software capabilities and training. The responsibilities of the plant designer for developing the IMS and generating the technical data base is defined as part of the plant process. The requirements to be met include a comprehensive plant data model and computer system hardware and software.

Summary of Nuclear Power Plant Prognostics and Health Management Report: PNNL-21515

Energy Technology Data Exchange (ETDEWEB)

Coble, Jamie; Hines, Wesley; Upadhyaya; Belle [University of Tennessee, Knoxville (United States); Ramuhalli, Pradeep [Pacific Northwest National Laboratory, Richland (United States); Bond, Leonard [Iowa State University, Ames (United States)

2014-08-15

The recent changes in oil and gas production, as well as wider geo-political events are causing the economics for electricity generation to currently be in a state of some turbulence in the United States (USA). In spite of this, nuclear power continues to meet about a fifth of the electricity needs in the USA. Currently, three separate thrusts to ensure safe and economical nuclear power development to give energy security are being pursued in the USA: longer term operation for the legacy fleet, from 40.60 and possibly 60.80 years; four near-term new nuclear plants with a 60-year design life; and small modular reactors (SMR) design certification, which are expected to employ light water reactor technology, at least in the medium term. Within these activities, attention is turning to enhanced methods for plant component and structural health management. The state of the art in prognostic and health management systems for nuclear power plants was recently reviewed and presented in a report (PNNL-21515); this paper summarizes the key findings of that review.

Water cycle and its management for plant habitats at reduced pressures

Science.gov (United States)

Rygalov, Vadim Y.; Fowler, Philip A.; Wheeler, Raymond M.; Bucklin, Ray A.

2004-01-01

Experimental and mathematical models were developed for describing and testing temperature and humidity parameters for plant production in bioregenerative life support systems. A factor was included for analyzing systems operating at low (10-101.3 kPa) pressure to reduce gas leakage and structural mass (e.g., inflatable greenhouses for space application). The expected close relationship between temperature and relative humidity was observed, along with the importance of heat exchanger coil temperature and air circulation rate. The presence of plants in closed habitats results in increased water flux through the system. Changes in pressure affect gas diffusion rates and surface boundary layers, and change convective transfer capabilities and water evaporation rates. A consistent observation from studies with plants at reduced pressures is increased evapotranspiration rates, even at constant vapor pressure deficits. This suggests that plant water status is a critical factor for managing low-pressure production systems. The approach suggested should help space mission planners design artificial environments in closed habitats.

Life styles of Colletotrichum species and implications for plant biosecurity

NARCIS (Netherlands)

Silva, Dilani D. De; Crous, Pedro W.; Ades, Peter Kevin; Hyde, Kevin D.; Taylor, Paul W. J.

Colletotrichum is a genus of major plant pathogens causing anthracnose diseases in many plant crops worldwide. The genus comprises a highly diverse group of pathogens that infect a wide range of plant hosts. The life styles of Colletotrichum species can be broadly categorised as necrotrophic,

Pattern-recognition system application to EBR-II plant-life extension

International Nuclear Information System (INIS)

King, R.W.; Radtke, W.H.; Mott, J.E.

1988-01-01

A computer-based pattern-recognition system, the System State Analyzer (SSA), is being used as part of the EBR-II plant-life extension program for detection of degradation and other abnormalities in plant systems. The SSA is used for surveillance of the EBR-II primary system instrumentation, primary sodium pumps, and plant heat balances. Early results of this surveillance indicate that the SSA can detect instrumentation degradation and system performance degradation over varying time intervals, and can provide derived signal values to replace signals from failed critical sensors. These results are being used in planning for extended-life operation of EBR-II

Reactor coolant pump service life evaluation for current life cycle optimization and license renewal

International Nuclear Information System (INIS)

Doroshuk, B.W.; Berto, D.S.; Robles, M.

1990-01-01

This paper reports that as part of the plant life cycle management and license renewal program, Baltimore Gas and Electric Company (BG and E) has completed a service life evaluation of their reactor coolant pumps, funded jointly by EPRI and performed by ABB Combustion Engineering Nuclear Power. Two of the goals of the BG and E plant life cycle management and license renewal program, and of this current evaluation, are to identify actions which would optimize current plant operation, and ensure that license renewal remains a viable option. The reactor coolant pumps (RCPs) at BG and E's Calvert Cliffs Units 1 and 2 are Byron Jackson pumps with a diffuser and a single suction. This pump design is also used in many other nuclear plants. The RCP service life evaluation assessed the effect of all plausible age-related degradation mechanisms (ARDMs) on the RCP components. Cyclic fatigue and thermal embrittlement were two ARDMs identified as having a high potential to limit the service life of the pump case. The pump case is a primary pressure boundary component. Hence, ensuring its continued structural integrity is important

AVLIS production plant waste management plan

International Nuclear Information System (INIS)

1984-01-01

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables

Transparency and efficiency through plant operations management systems

International Nuclear Information System (INIS)

Ladage, L.

2001-01-01

Plant operations management systems, being IT application systems, provide integral support of the business processes making up plant operations management. The use of plant operations management systems improves mutually interdependent factors, such as high economic performance, high availability, and maximum safety. Since its commissioning in 1988, the Emsland nuclear power station (KKE) has been run with the IBFS plant operations management system. The work flow management system (WfMS), a module of IBFS, is described as an example of job order processing. IBFS-WfMS is to optimize all processes, thus cutting costs and ensuring that processes are run and documented reliably. Assessing the savings effect achieved through the use of IBFS-WfMS clearly reveals the savings in work/time achieved by the system. These savings are quoted as approx. 4 minutes and DM 10, respectively, per working step, which corresponds to several dozens of manyears or several million DM per annum in the KKE plant under consideration. This result can be extrapolated to other plants. (orig.) [de

Life cycle assessment of bagasse waste management options

International Nuclear Information System (INIS)

Kiatkittipong, Worapon; Wongsuchoto, Porntip; Pavasant, Prasert

2009-01-01

Bagasse is mostly utilized for steam and power production for domestic sugar mills. There have been a number of alternatives that could well be applied to manage bagasse, such as pulp production, conversion to biogas and electricity production. The selection of proper alternatives depends significantly on the appropriateness of the technology both from the technical and the environmental points of view. This work proposes a simple model based on the application of life cycle assessment (LCA) to evaluate the environmental impacts of various alternatives for dealing with bagasse waste. The environmental aspects of concern included global warming potential, acidification potential, eutrophication potential and photochemical oxidant creation. Four waste management scenarios for bagasse were evaluated: landfilling with utilization of landfill gas, anaerobic digestion with biogas production, incineration for power generation, and pulp production. In landfills, environmental impacts depended significantly on the biogas collection efficiency, whereas incineration of bagasse to electricity in the power plant showed better environmental performance than that of conventional low biogas collection efficiency landfills. Anaerobic digestion of bagasse in a control biogas reactor was superior to the other two energy generation options in all environmental aspects. Although the use of bagasse in pulp mills created relatively high environmental burdens, the results from the LCA revealed that other stages of the life cycle produced relatively small impacts and that this option might be the most environmentally benign alternative

Plant life extension and ageing mechanisms: an ANSALDO proposal for the application to Kozloduy NPPs

International Nuclear Information System (INIS)

Orlandi, S.; Macco, A.; Zanaboni, P.

1999-01-01

In the frame of extension of NPP's installations lifetime, ageing management has become a topical subject to obtain the items: - Evaluation of residual life of the plant through the investigation of the residual life of well identified Safety Related Equipment in the as built configuration; - Organization of identified representative equipment per typological Classes (as Piping Systems, Tanks, Valves, Pumps, Electrical Equipment, Pressurized Components) in order to define for each High Level Class a set of elementary families capable to have, within each family, a common ageing mechanism and methodological investigation and potential common on-line monitoring; Application of a consistent methodology for residual life evaluation at each High Level Class (and subsequent elementary family and group if any) in order to assess an integral approach to backfitting and ageing management, taking also into account the economical investment effort required to the utility. In this report, a technical proposal for the application of the ANSALDO standard methodology approach, applied to the re-evaluation of the Kozloduy NPP's (Unit 1 - to 4) is presented. (authors)

Development of JOYO plant operation management expert tool

Energy Technology Data Exchange (ETDEWEB)

Michino, Masanobu; Sawada, Makoto [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

1995-03-01

Operation and maintenance support systems for JOYO are being developed in order to keep the stable and safe operation of JOYO and to improve operational reliability of future FBR plants. As one of the systems, an operation support system named JOYPET has been developing and applied. The system supports the plant management works of JOYO which are necessary for much manpower and knowledge of the plant. The plant management of JOYO was able to improve its reliability and reduce manpower by using this system. As a final step, a judgment function based on the accumulated plant management rule of JOYO will be developed and applied. The function judges the plant condition which allows to start the maintenance works or not. (author).

The role of NOSA five-star management system for occupational management of nuclear power plants

International Nuclear Information System (INIS)

Zhang Qin

2011-01-01

The occupational safety management of nuclear power plant is developed towards integrated management, risk management, process management, all-round and full staff participation. Appropriate management method integrated with nuclear power plant safety, health and environmental protection could be organically combined with the nuclear safety operation management system, and could jointly lay a solid foundation for building up good nuclear safety culture. NOSA five-star management system is such a kind of risk management based on safety, health and environmental management system, with an aim to protect the personal safety. The concepts of NOSA management and nuclear safety culture are coincident, with strong workability, and meeting the need of nuclear power plant occupational safety management. Adopting NOSA five-star management system and keeping continuous improvement is one of the effective ways to improve the level of occupational safety management of nuclear power plant. It can be organically combined with nuclear safety operation management system and continuously improved safety culture to play an important role in improving the safety and economics of nuclear power plant. (author)

Systems Modeling For The Laser Fusion-Fission Energy (LIFE) Power Plant

International Nuclear Information System (INIS)

Meier, W.R.; Abbott, R.; Beach, R.; Blink, J.; Caird, J.; Erlandson, A.; Farmer, J.; Halsey, W.; Ladran, T.; Latkowski, J.; MacIntyre, A.; Miles, R.; Storm, E.

2008-01-01

A systems model has been developed for the Laser Inertial Fusion-Fission Energy (LIFE) power plant. It combines cost-performance scaling models for the major subsystems of the plant including the laser, inertial fusion target factory, engine (i.e., the chamber including the fission and tritium breeding blankets), energy conversion systems and balance of plant. The LIFE plant model is being used to evaluate design trade-offs and to identify high-leverage R and D. At this point, we are focused more on doing self consistent design trades and optimization as opposed to trying to predict a cost of electricity with a high degree of certainty. Key results show the advantage of large scale (>1000 MWe) plants and the importance of minimizing the cost of diodes and balance of plant cost

Development of management system for plant repairing work

International Nuclear Information System (INIS)

Terauchi, Makoto

1999-01-01

In the fast breeder reactor, ''Monju'', in order to conduct nuclear plant repairing works securely and effectively, development of a computer system to assist management business on plant repairing work was begun on 1993. The system has been applied to about 5,000 times of operational management through past four times of plant inspection and to daily inspections and maintenance, and is daily used at working places of ''Monju'' such as issue/management of about 110,000 times of operational prohibition tag in isolated management. And, by automation of issue/management on working sheets and operational prohibition tag and others conducted hitherto by hand, the management business has been largely rationalized. (G.K.)

Life-cycle cost assessment of seismically base-isolated structures in nuclear power plants

International Nuclear Information System (INIS)

Wang, Hao; Weng, Dagen; Lu, Xilin; Lu, Liang

2013-01-01

Highlights: • The life-cycle cost of seismic base-isolated nuclear power plants is modeled. • The change law of life-cycle cost with seismic fortification intensity is studied. • The initial cost of laminated lead rubber bearings can be expressed as the function of volume. • The initial cost of a damper can be expressed as the function of its maximum displacement and tonnage. • The use of base-isolation can greatly reduce the expected damage cost, which leads to the reduction of the life-cycle cost. -- Abstract: Evaluation of seismically base-isolated structural life-cycle cost is the key problem in performance based seismic design. A method is being introduced to address the life-cycle cost of base-isolated reinforced concrete structures in nuclear power plants. Each composition of life-cycle cost is analyzed including the initial construction cost, the isolators cost and the excepted damage cost over life-cycle of the structure. The concept of seismic intensity is being used to estimate the expected damage cost, greatly simplifying the calculation. Moreover, French Cruas nuclear power plant is employed as an example to assess its life-cycle cost, compared to the cost of non-isolated plant at the same time. The results show that the proposed method is efficient and the expected damage cost is enormously reduced because of the application of isolators, which leads to the reduction of the life-cycle cost of nuclear power plants

Invasive Plant Management Plan for the Oak Ridge Reservation

Energy Technology Data Exchange (ETDEWEB)

Giffen, Neil R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McCracken, Kitty [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

Invasive non-native plant species have become one of the greatest ecological threats across the country and around the world. Actively managing incursions of invasive plants is crucial to maintaining ecosystems, protecting natural resources, and ensuring proper function of facilities and their support infrastructures, power lines and other utility rights-of-way (ROWs), communications structures, roadways, and waterways. Invasive plants can threaten cultural resources, public and private properties, forests, wetlands, and other natural areas through increased risks of fire and storm damage, as well as decrease native plant diversity, particularly disrupting vital habitats of threatened and endangered species, both plant and animal. In 2000, the Federal Plant Protection Act came into effect. Under this Act, federal agencies are required to develop and coordinate an undesirable plants management program for control of invasive plants on federal lands under each agency’s respective jurisdiction. The agency must adequately fund the undesirable plants management program using an Integrated Pest Management Plan. Additionally, each agency is required to implement cooperative agreements with local and state agencies, as well as other federal agencies, to manage undesirable plants on federal lands under the agency’s jurisdiction. The US Department of Energy (DOE) takes its responsibility for addressing invasive and undesirable plant issues very seriously. Many DOE sites have programs to control invasive pest plant species. DOE has taken a proactive stance toward invasive plant control, and the Invasive Plant Management Plan— created to meet regulatory requirements of federal laws, executive orders, presidential memos, contracts, and agreements on DOE’s Oak Ridge Reservation (ORR)—has been in effect since 2004. This document represents the second revision of this plan.

Nuclear power plant Angra integrated enterprise management system

International Nuclear Information System (INIS)