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Sample records for npp life management

  1. 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

  2. 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

  3. Integrated NPP life cycle management - Agency's approach

    International Nuclear Information System (INIS)

    Gueorguiev, B.

    2002-01-01

    administrative - managerial or/and social - political activities aimed at the achievement of an optimised long term save and reliable operation of the plant including its decommissioning. Optimisation of the plant operational life is the most economical option equivalent to providing additional generating capacity. In its turn optimisation of operational or service life means extension of the operational license to the extent possible having in mind that the plant performance continues to maintain its safety and competitiveness on the market. To meet these requirements the need for an integrated NPP life management approach is becoming more and more evident. The IAEA in response to the needs of the Member states is implementing several programmes including the project on engineering and management practices for optimisation of nuclear power plant service life including decommissioning. The Project scope includes different possible modes of IAEA operations for the purposes of information exchange and technology transfer. It means arrangements for technical, advisory and consultant group meetings, development of databases and guidance documents on proven practices, co-ordinated research projects, technical co-operation projects, expert services, training activities, co-operation with other International organizations and some others. A number of issues are under consideration. They include economic analysis and considerations related to decision on continued operation versus decommissioning, optimisation of operation/maintenance/In-service inspection regimes to facilitate life management programmes, aging management and mitigation measures with regard to control and instrumentation, primary and secondary circuit equipment integrity, assessment of structural materials, creation and development of supporting databases, preservation of knowledge including aspects of training and qualification of NPP personnel, work force aging, pre-shut down and decommissioning activities

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. Russian normative approach to the question of management of NPP life time

    International Nuclear Information System (INIS)

    Karpunin, N.I.

    2002-01-01

    Full text: In Russia, the designated service life of a nuclear power plant (NPP) is 30 years. During the period 2001-2010, 15 Russian NPP units will reach the end of their service life. The 'Basic Provisions of NPP Safety Assurance', OPB-88/97, Item 5.1.14, provide for a possible extension of NPP operation beyond the designated service life. For such an extension, the NPP operating organization must apply for a license renewal to Gosatomnadzor, which needs to specify the relevant requirements. GAN is developing regulatory documents to provide a basis for NPP license renewal/extension of NPP operation, which would benefit from international experience. In accordance with 'The program of Atomic Energy Development in the Russian Federation for 1998-2005 and up to 2010' adopted by Decree No. 815 of the Government of the Russian Federation on 21 July 1998, priority is placed on the preparation of NPPs for extension of service life and on ensuring safety in the extended operating period. The length of the extension beyond the designated service life is to be determined on the basis of a range of technical and economic considerations, including: The ability to ensure and maintain operational safety; Sufficient residual service life of the unit's non-repairable components; The availability of temporary storage facilities for the additional spent nuclear fuel and radioactive waste, or the possibility of its transport off-site; The ability to ensure safe handling of the radioactive waste generated during the extension period; To extend the lifetime of an NPP unit, the plant Operator is required to perform the following tasks: Carry out a comprehensive survey of the NPP unit; Draw up a programme of preparation for lifetime extension; Prepare the NPP unit for operation in the extended period; Carry out the necessary tests. There are also some normative documents, which regulate management of NPP life time. (author)

  9. Programs of plant life management at NPP Dukovany

    International Nuclear Information System (INIS)

    Pochman, K.; Ruscak, M.; Brumovsky, M.

    2000-01-01

    The program of lifetime management at NPP Dukovany is oriented towards an effective usage of facilities while keeping their safety parameters, mainly concerning nuclear safety. The goal is to achieve maximum usage of the design lifetime under the condition of fulfilling above mentioned requirements. Evaluation procedures have been prepared for selected components. These are subsequently discussed and approved by the State Office of Nuclear Safety. The databases of original data are built up regarding the evaluated components. The input data are completed as well according to the approved procedures. Generally valid approaches based on the evaluation of all possible degradation mechanisms are modified regarding the original status of particular component. The procedures are oriented towards a quantification of residual lifetime. They employ knowledge of initiation and kinetics of degradation mechanisms. They also define mechanisms, which should be quantified. For irreplaceable components or components whose replacement is difficult, the program is focused to the control of operation conditions and inspection of facilities. However, they are again based on the knowledge of degradation kinetics. If at least some parts of the facility could be replaced, better material selection regarding the operation conditions is an option. Systems included into the ageing management system will be specified in the paper. Also, the measures will be identified which serve as a check of implementation of all possible stressors and degradation mechanisms into the first screening. The examples of lifetime evaluation of some systems and components will be given in the paper: reactor pressure vessel, reactor internals, steam generator tubes and feedwater piping. Specific approaches will be shown fro different original status of components and different operation conditions. (author)

  10. 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

  11. 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.

  12. Improvement of Structural Life Management System(SLMS) for N.P.P. Structures

    International Nuclear Information System (INIS)

    Cho, Myung Sug; Noh, Jae Myung; Lee, Jong Suk; Kim, Do Gyeum

    2009-01-01

    The first investigation on the degradation mechanism and establishment of systematic inspection procedure for nuclear power plant (NPP) structures in Korea were conducted through a research project performed from 1993 to 19961). Accordingly, the Structural Life Management System (SLMS) was developed in 1998. Currently, SLMS is still operating for the lifetime management of NPP structures. However, the function of currently operating SLMS is focusing essentially on the management of degradation data detected during periodical inspections. Such limited function is today stressing the necessity to supplement its functions by improving the inefficiency of D/B due to the huge volume of data as well as by reflecting additional requirements. Accordingly, this research intends to develop a system improving the former SLMS so as to accommodate to the various demands of the users like integrated D/B system exploiting web-server, integrity assessment and durability management

  13. Euratom community cosponsored research in NPP life management

    International Nuclear Information System (INIS)

    Manolatos, P.; Goethem, G. van

    2002-01-01

    At the end of 2000, in the EU, in 8 of the 15 Member States, a total of 143 reactor units were in operation with a total capacity of 123 net GWe and a total gross generation of 863 TWh (i.e. 35 % of the EU electricity generation). Most of them have been operating for longer than 20 years (65 reactor units were put in commercial operation before 1980). As a consequence, the nuclear industry is increasingly interested in research activities aimed at better understanding and managing ageing phenomena. Despite the historical safety record of NPPs of Western design, the key players believe that research is still needed to further increase both the safety and the performances of these power plants in line with the steadily growing pressure of regulatory and market forces as well as of the public opinion

  14. Dukovany NPP maintenance management

    International Nuclear Information System (INIS)

    Siegel, F.

    2005-01-01

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

  15. Considerations related to Cernavoda NPP lifetime management

    International Nuclear Information System (INIS)

    Cojan, Mihail

    2007-01-01

    Cernavoda NPP, the first CANDU in Europe, is one of the original CANDU 6 plants and the first CANDU 6 producing over 706 MWe. While the first series of CANDU 6 plants (which entered service in the early 1980 s) have now reached the 2/3 of their 30 years design life, the Cernavoda NPP was put into service on the 2nd December 1996. After 10 years of operation the Plant Life Management (PLiM) Program for Cernavoda should be an increasingly important program to Utility ('CNE - Prod') in order to protect the investment and the continued success of plant operation. The goal of the paper is to present some considerations related to Cernavoda NPP lifetime management. The Plant Life Management Program, known as PLiM Program is concerned with the analysis of technical limits of the safe operation - from the point of view of nuclear safety - in NPP units, aiming at attaining the planned 30 years life duration and its extension to 40 or even 50 years of safe and economical operation. For the CANDU reactors the so-called PLiM and PLEX Programs are just applied. These are applied research programs that approach with priority the current practices for assessing the capability of safe operation within the limits of nuclear safety (fitness-for-service assessment). These programs also approach inspection, monitoring are prevention of degrading due to the ageing of critical systems, structures and components (CSSCs). As each nuclear plant is somewhat different in its components and systems, materials composition, procurement, construction, and operational history, directed research and development programs into materials behavior, monitoring techniques, and methods to mitigate ageing are required to support the lifetime management. Over the past 6 years, INR Pitesti (Institute for Nuclear Research - Romania) has been working on R and D Programs to support a comprehensive and integrated Cernavoda NPP Life Management Program (PLiM) that will see the Cernavoda NPP successfully and

  16. Radioactive wastes management of NPP

    International Nuclear Information System (INIS)

    Klyuchnikov, A.A.; Pazukhin, Eh.M.; Shigera, Yu. M.; Shigera, V.Yu.

    2005-01-01

    Modern knowledge in the field of radiation waste management on example of the most serious man-made accident at Chernobyl NPP are illuminated. This nuclear power plant that after accident in 1986 became in definite aspect an experimental scientific ground, includes all variety of problems which have to be solved by NPP personnel and specialists from scientific organizations. This book is aimed for large sphere of readers. It will be useful for students, engineers, specialists and those working in the field of nuclear power, ionizing source and radiation technology use for acquiring modern experience in nuclear material management

  17. The main trends of work on lifetime management of NPP

    International Nuclear Information System (INIS)

    Dragunov, Yu.; Kurakov, Yu.

    1995-01-01

    The major trends of works on NPP lifetime management are discussed: Co-ordinating and organizational activities; studying the degradation processes and residual life; elaboration and implementation of the measures to maintain/enhance safety level of NPPs operating within design life; development of control principals of advanced NPPs aging and safe life; creation and development of regulations in the field of NPP aging and life management. 7 figs

  18. 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

  19. The life cycle management of the analogical I and C in NPP modernization project

    International Nuclear Information System (INIS)

    Wang Hongtao

    2014-01-01

    The existing NPPS (nuclear power plants) are subject for the ageing and obsolete problems of the analogue I and C systems. The large scope I and C upgrade project based on the DCS technology has the following challenged characteristics: the complicated technology, the broad impacts, the big investment and the long implementation period. This document gives a preliminary introduction and analysis from the aspects including the motives for the upgrade, I and C design base, the digital technology characteristics, I and C function analysis, I and C safety classification, I and C architecture, life-cycle-management mission for the related stages. Considering the experiences and lessons learned from the similar I and C upgrade projects in foreign NPPS, the conclusion and recommendation is given for I and C modernization based on the digital technology. (author)

  20. The NPP Isar comprehensive Aging Management Program

    International Nuclear Information System (INIS)

    Zander, Andre; Ertl, Stefan

    2012-01-01

    The majority of System, Structure and Components (SSC) in a nuclear power plants are designed to experience a service life, which is far above the intended design life. In most cases, only a small percentage of SSCs are subject to significant aging effects, which may affect the integrity or the function of the component. The process of aging management (AM) has the objective to monitor and control degradation effects which may compromise safety functions of the plant. And furthermore, to ensure, that testing and maintenance programs sufficiently provide preventive measures to control degradation effects. Safety-related aspects and the targeted high availability of the power plant as well as the requirements stipulated by German regulatory authorities prompted the operator of NPP ISAR to introduce an aging surveillance program. The NPP Isar as well as the German NPPs has to be following in the scope of aging management the KTA 1403 guideline. The NPP Isar surveillance program based on the KTA 1403 guideline covers the following aspects: - Scoping and screening of safety relevant Systems, Structures and Components (SSC); - Identification of possible degradation mechanisms for safety relevant SSC; - Ensure, that testing and maintenance programs sufficiently provide preventive measures to control degradation effects; - Transferability check of industry experience (internal and external events); - Annual preparation of an AM status report. (author)

  1. Life management and operational experience feedback - tools to enhance safety and reliability of the NPP

    International Nuclear Information System (INIS)

    Mach, P.

    1997-01-01

    Preparation has started of the Temelin power plant centralized equipment database. Principles of reliability centered maintenance are studied, and use of these activities will be made in the Plant Ageing Management Programme. The aims of the Programme are as follows: selection of important components subject to ageing, data collection, determination of dominant stressors, development, selection and validation of ageing evaluation methods, setup of experience feedback, determination of responsibilities, methodologies and strategy, elaboration of programme procedures and documentation, and maintenance of programme flexibility. Pilot studies of component ageing are under way: for the reactor pressure vessel, steam generator, pressurizer, piping, ECCS and cables. The organizational structure of the Operational Experience Feedback system is described, as are the responsibility of staff and sources of information. (M.D.)

  2. Life extension program of KORI Unit 1 NPP in Korea

    International Nuclear Information System (INIS)

    Hong, Sun-Yull

    1998-01-01

    The two phases of Life extension program for KORI Unit 1 NPP are presented. Phase I is completed. It was concluded that life extension is a feasible option in technical and economic aspects. Detailed analysis of RPV is underway, plan for Phase II is finished. It deals with screening and sorting of all relevant SSCs, detailed life evaluation of SSCs, ageing management program and documentation for license renewal application

  3. Radioactive source management in Daya Bay NPP

    International Nuclear Information System (INIS)

    Mao Chun Yang

    2000-01-01

    'Small sources causes big accidents' had occurred worldwide many times. Radioactive source management in Nuclear Power Plant in very important for its safety record. This paper introduces the way and experience of radioactive source management in Daya Bay NPP from aspects of clarifying the responsibilities, centralizing the management of high radioactivity sources, work process management and experience feedback etc. (author)

  4. Knowledge Management and Organizational Proficiency with NPP

    International Nuclear Information System (INIS)

    Marler, M.

    2016-01-01

    Full text: The pace of new NPP construction, startup, and operation is straining the supply of proficient operators, technicians, and engineers. This technical brief explains an approach implemented by a US nuclear utility to capture and transfer knowledge possessed by proficient workers to new workers using the VISION learning content management system. This approach could also be used to accelerate worker proficiency in new NPP organizations. (author

  5. Integrated ageing management of Atucha NPP

    International Nuclear Information System (INIS)

    Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos; Sabransky, Mario

    2013-01-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

  6. Integrated Ageing Management of Atucha NPP

    International Nuclear Information System (INIS)

    Ranalli, J.M.; Marchena, M.H.; Zorrilla, J.R.; Sabransky, M.

    2012-01-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor twice as big as Atucha I finishing a delayed construction . With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

  7. Integrated ageing management of Atucha NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos, E-mail: ranalli@cnea.gov.ar [Gerencia Coordinacion Proyectos CNEA-NASA, Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Sabransky, Mario, E-mail: msabransky@na-sa.com.ar [Departamento Gestion de Envejecimiento, Central Nuclear Atucha I-II Nucleoelectrica Argentina S.A., Provincia de Buenos Aires (Argentina)

    2013-07-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

  8. NPP Krsko Aging Management Program

    International Nuclear Information System (INIS)

    Glaser, B.; Spiler, J.

    2002-01-01

    As a part of Periodic Safety Review Program (PSR) NEK will review and perform some activities related to Equipment Qualification (EQ) and Aging Management Program (AMP). (EQ) and AMP are safety factors, which need to be assessed during PSR. The goal of PSR and AMP is to determine aging effects and give the conclusion whether the plant has been managed to control aging related degradations and that safety margins are maintained. The parallel goal is also to establish AMP for future plant operation and provide basis for possible Life Extension Program. NEK will develop NEK Aging and Life Cycle Management Program, similar by format and content to one determined by License Renewal program. The bases are in 10CFR54, and NEI 95-10 Industry Guidelines for 10 CFR 54 implementation. The process of establishment the AMP is to be done in two steps. The first step is dealing with SSC's (Systems Structures and Components) scoping and screening and identification of TLAA's (Time Limited Aging Analyses). That means, that a database of all SSC's and TLAA's will be created and then evaluated within AMP program. Based on the scope in first phase an evaluation will be performed in step two. NEK will maintain AMP program as a living program that may be also used for Life Extension and Life Cycle Management. This paper will present and describe AMP, scoping and screening process and the results achieved through the first phase of the project.(author)

  9. NPP Evaluation, backfitting and life extension. An engineering viewpoint

    International Nuclear Information System (INIS)

    Gonzalez Lopez, A.

    1993-01-01

    During the decade of the 80s, the Owners of the two oldest operating plants in Spain designed and built during the 60s - namely, Jose Cabrera NPP, a Westinghouse PWR, and Santa Maria de Garona NPP, a GE BWR- undertook the following important programs: 1. A far-reaching Systematic Evaluation Program (SEP) for the Jose Cabrera NPP consisting in the systematic safety review of the plant design, followed by the necessary hardware modifications, to upgrade it and make it comply with current safety criteria, and a Plant Upgrading Program for the Garona Nuclear Station focusing on specific topics affecting GE BWR Mark-I type plants of the same vintage. 2. A Remaining Life Management Program to ensure that the units, after extensive backfittings and high capital investment, would complete their design life, leaving open the option for plant life extension. These two units are today considered by the Spanish nuclear industry as the pilot plants for Plant Life Extension (PLEX) programs for PWRs and BWRs in our country The purpose of this paper is to summarize the principal lessons learned from EMPRESARIOS AGRUPADOS' participation as an architect-engineering organization in the engineering, design and implementation of these Programs. They are practical examples of positive experience which could be considered as a reference when carrying out similar programs for other plants. (author)

  10. NPP Evaluation, backfitting and life extension. An engineering viewpoint

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    During the decade of the 80s, the Owners of the two oldest operating plants in Spain designed and built during the 60s - namely, Jose Cabrera NPP, a Westinghouse PWR, and Santa Maria de Garona NPP, a GE BWR- undertook the following important programs: 1. A far-reaching Systematic Evaluation Program (SEP) for the Jose Cabrera NPP consisting in the systematic safety review of the plant design, followed by the necessary hardware modifications, to upgrade it and make it comply with current safety criteria, and a Plant Upgrading Program for the Garona Nuclear Station focusing on specific topics affecting GE BWR Mark-I type plants of the same vintage. 2. A Remaining Life Management Program to ensure that the units, after extensive backfittings and high capital investment, would complete their design life, leaving open the option for plant life extension. These two units are today considered by the Spanish nuclear industry as the pilot plants for Plant Life Extension (PLEX) programs for PWRs and BWRs in our country The purpose of this paper is to summarize the principal lessons learned from EMPRESARIOS AGRUPADOS' participation as an architect-engineering organization in the engineering, design and implementation of these Programs. They are practical examples of positive experience which could be considered as a reference when carrying out similar programs for other plants. (author)

  11. Knowledge management during decommissioning of Chornobyl NPP

    International Nuclear Information System (INIS)

    Gora, A.D.; Kuchinskij, V.K.; Stel'makh, D.A.; Tsivun, T.A.

    2010-01-01

    The article deals with issues on knowledge management during decommissioning by the example of the Chornobyl NPP. This includes how the duration of decommissioning stage, change in organization goal and final state of the site influence on human resources and knowledge management system. The main attention is focused on human assets and intellectual strength of Chornobyl NPP. Mathematical dependencies are proposed to substantiate numerical values. An analysis is given for the current situation, and forecast estimates for values dynamics is performed. The conclusion gives solutions on providing experienced staff in the future.

  12. Remanent life management of nuclear power plants

    International Nuclear Information System (INIS)

    Pinedo, J.; Gomez Santamaria, J.

    1995-01-01

    The concept of life in the nuclear power plants is very special. The main aceptions are: design life, economic life and useful life. The good management of NPP will do the prolongation of the life in the NPP. The remanent of management life summarizes certain activities in order to prolong the lifetime of the NPP. This article presents the activities of the RML program, the technological program and its benefits

  13. Jose Cabrera NPP severe accident management activities

    International Nuclear Information System (INIS)

    Blanco, J.; Almeida, P.; Saiz, J.; Sastre, J.L.; Delgado, R.

    1998-01-01

    To prepare a common acting plan with respect to Severe Accident Management, in 1994 was founded the severe accident management ''ad-hoc'' working group from the Spanish Westinghouse PWR Nuclear Power Plant Owners Group. In this group actively collaborated the Jose Cabrera NPP Training Centre and the Department of Nuclear Engineering of UNION FENOSA. From this moment, Jose Cabrera NPP began the planning of its specific Severe Accident Management Program, which main point are Severe Accident Management Guidelines (SAMG). To elaborate this guidelines, the Spanish translation of Westinghouse Owners Group (WOG) Severe Accident Management Guidelines were considered the reference documents. The implementation of this Guidelines to Jose Cabrera NPP started on January 1997. Once the specific guidelines have been implemented to the plant, training activities for the personnel involved in severe accident issues will be developed. To prepare the training exercises MAAP4 code will be used, and with this intention, a specific Jose Cabrera NPP MAAP-GRAAPH screen has been developed. Furthermore, a wide selection of MAAP input files for the simulation of different scenarios and accidental events is available. (Author)

  14. Policy and methodology on NPP lifetime management in Spain

    International Nuclear Information System (INIS)

    Francia, L.

    1998-01-01

    The objectives for Spanish electricity sector are to extend the life cycle of NPPs beyond 40 years, maintaining safety and efficiency level, and to monitor and control ageing of important components to guarantee the prolonged lifetime. A plan for plant life management including licensing and regulatory aspects is proposed together with the methodology for achieving the proposed goals. The expected results are: life management integrated system for follow-up and monitoring of degradation and ageing mechanisms of important NPP components; modular system which will enable incorporation of additional components, degradation and/or performances; interrelation and support tool for other needs of NPPs (periodic safety reviews, maintenance, optimization, etc.)

  15. The main trends of work on ageing and lifetime management of NPP

    International Nuclear Information System (INIS)

    Dragunov, Yu.

    1994-01-01

    The main trends of work on aging and lifetime management of nuclear power plants(NPP) in Russia are described including Russian research programs on NPP components lifetime assurance, technical assistance program for CIS, measures for life extension of reactor pressure vessels, steam generator collectors and components for advances reactor plants. Figs and tabs

  16. Knowledge management in the NPP domain

    International Nuclear Information System (INIS)

    Nilsen, Svein; Bisio, Rossella; Ludvigsen, Jan Tore

    2004-03-01

    This report gives an outlook on Knowledge Management (KM) activities within NPP related establishments as of today. There may be less activity in the NPP world as compared to many other industrial sectors. Still there is an awakening within the NPP industry demanding that KM should be attended to at a larger scale. The most notable reason for this is maybe an imminent increase in the number of people going into retirement. The types of establishments involved cover the major kinds such as utilities, research institutes and worldwide nuclear organizations. The report sums up a few of those efforts that are presently being implemented. Moreover the report looks at general advancements within the field of knowledge management. Simply stated the endeavours belong to either one of two classes. The first class emphasize the use of technology to solve knowledge management problems. The second class regard knowledge management as a problem pertaining to human factors and organizational issues. This report maintain that knowledge management initiatives should make due considerations to both perspectives. This report also sums up the Halden Reactor Project short term KM initiative. (Author)

  17. Aspects of accident management in Cernavoda NPP

    International Nuclear Information System (INIS)

    Dascalu, N.

    1999-01-01

    As a general conclusion, the accident management system as implemented at Cerna voda NPP is expected to be appropriate for handling a severe accident, should it occur, in such a way that the environmental radiological consequences would be insignificant and radiation exposure of the personnel be within recommendations. It is recognized, however, that continued development and verification of the system as well as effective personnel training programs are essential to maintain the safety level achieved. (author)

  18. Belene NPP project configuration management

    International Nuclear Information System (INIS)

    Matveev, A.

    2009-01-01

    The configuration management includes: change identification; change assessment; change coordination; change approval or rejection; Change introduction. One of the main tasks while implementing the above processes is the analysis of the effect of one change upon all the related elements

  19. Cofrentes NPP Knowledge management plan

    International Nuclear Information System (INIS)

    Pardo Gonzalez, F.

    2016-01-01

    The main objective of the Knowledge Management Plan at Cofrentes Nuclear Power Plant is therefore to establish the steps to be followed for distributing and sharing the existing knowledge at the Plant through collaboration and continuous learning and exchanges with internal and external groups. It is also very important that staff and organisational learning is closely in line with Plant expectations. (Author)

  20. Optimization of NPP performance and service life in a competitive electricity market

    International Nuclear Information System (INIS)

    Gueorguiev, B.; Spielgelberg - Planner, R.

    2000-01-01

    This paper discusses how the competitive electricity market has influenced nuclear power plant operations, with a focus on optimisation of NPP performance and plant service life, and how the IAEA programme has addressed some of this issues. The definitions of Plant Life, Operational Life, Design Life and Periodical Safety Reviews are developed in the paper in order to differentiate between the terms and to show the significance in terms of Plant Life Management

  1. Plant lifetime management at Jose Cabrera NPP

    International Nuclear Information System (INIS)

    Martin, Jorge; Garcia, Piedad

    1998-01-01

    This paper presents the results obtained during the development and implementation of the Jose Cabrera NPP Lifetime Management Program according to the methodology applied in the Plant. The implementation of the Lifetime Management Program began in 1995 with the elaboration of the annual revision document 'Lifetime Management Plan', which describes the level of development of the Lifetime Management activities, the results that have been obtained during the implementation of the Program, and the schedule of the upcoming activities. The drawing up of a weighted list of 135 important components and the elaboration of 17 dossiers integrating the ageing mechanisms analysis and its corresponding evaluation, control and mitigation methods, were the result of the activities completed during 1996. A group of 62 component/degradation phenomena pairs with a high degradation risk classification has been considered within the scope of the activity 'Assessment of Maintenance Practices. Improvement Proposal', performed by the plant during 1997 and the first term of 1998 in parallel with other Lifetime Management related activities. The results obtained within this activity have revealed for the components included in the scope of the assessment that the associated degradation phenomena are practically covered by the current maintenance, inspection and testing practices. Recommendations and improvements of the maintenance practices have been particularly proposed from a technical, supporting, proceeding and documentary point of view, and currently an analysis is being made in relation to the feasibility of implementing them at the Jose Cabrera NPP. (author)

  2. Specific aspects for Cernavoda - Unit 1 NPP life assurance

    International Nuclear Information System (INIS)

    Rucareanu, R.

    2002-01-01

    Full text: The main scope of a Plant Life Management Program is to operate the NPP in a safe manner and at a competitive cost during the reactor life. To achieve this goal, it is important to continuously evaluate the degradation of the main structures and components of the NPP. Background -Cernavoda NPP design life is 30 years. Compared with this target, the operation history is not long (Unit 1 is in commercial operation since 1997). It is still important to begin a plant life management program early to identify the critical components and structures, to establish the data needed for their monitoring and to find methods to mitigate their degradation. A specific aspect for Cernavoda NPP - Unit 1 is the long delay between the fabrication of the main components and the start-up. Most components were procured 10-15 years before start-up. First criticality was achieved in 1996, but the containment perimeter wall sliding was complete in 1983, the Calandria vessel was installed in 1985, the Steam Generators were in position in 1987, the fuel channels were installed in 1989. In evaluating the history of these components, the preservation period must be observed. For Unit 2, which will be in service around 2005, the delay will be longer. For this reason, CNCAN (the Romanian Regulatory Authority) imposed, as a condition to resume the work, to evaluate the ageing of the existing components and structures in order to establish their acceptability for use in the plant. The results of this evaluation can be used as references for subsequent evaluations. Plant Life Assurance Programme - The first step of a PLIM programme is to identify the components and structures that are important for the plant life management. Critical components and structures selection is done using the following criteria: safety criteria - components and structures whose failure can cause a release of radioactivity or which have to mitigate the release of radioactivity in case of a failure of other

  3. Features of the Kozloduy NPP management system

    International Nuclear Information System (INIS)

    2016-01-01

    The Kozloduy NPP management system was built taking into account the specifics of the organizational structure and management of the Company, actual processes and practices, and is oriented towards future development, with the participation of all staff. Additional requirements integrated in the system that distinguish it from general industrial requirements of management systems are: priority of nuclear safety; safety culture; knowledge management including extraction and storage of 'hidden knowledge'; periodic self-assessments; use of graded response to the products and activities; use of 'conservative approach' in decision making;; possibilities for self learning and creating of a vision of 'leaders' and 'professional workers in nuclear energy

  4. Ageing management database development for PWR NPP steam generator

    International Nuclear Information System (INIS)

    Liu Hongyun; Xu Liangjun; Xiong Changhuai; Wang Xianyuan

    2005-01-01

    Steam generator (SG) is one of the key safe important equipment of NPP, which is covered by NPP aging management program. Steam Generator Aging Management Dabatase (SGAMDB) is developed to provide necessary information for SG aging management. RINPO is developing SGAMDB for domestic NPP. This system contains information and data about SG design, manufacture, operation and maintenance. The information include NPP fundamental data, SG design data, SG aging mechanism, SG operation data, SG ISI data, SG maintenance data and SG evaluation interface. The system runs at the intranet of Qinshan-1 NPP with B/S mode. It can provide information inquire and fundamental analysis for NPP SG aging team and SG aging researcher's. In addition, it provides necessary information and data for SG aging analysis and evaluation, such as all pressure test process and flaws of tubes, and collects the analysis results. (authors)

  5. Transition cycle fuel management problems of NPP Krsko

    International Nuclear Information System (INIS)

    Petrovic, B.; Pevec, D.; Smuc, T.; Urli, N.

    1989-01-01

    Transition cycle fuel management problems are described and illustrated using results and experience attained during core reload design of NPP Krsko. Improved version of computer code package PSU-LEOPARD/Mcrac is successfully applied to NPP Krsko loading pattern design. (author)

  6. Engineering Center contribution to the Russian NPP aging management

    International Nuclear Information System (INIS)

    Bougaenko, S.

    1993-01-01

    The Engineering Center of strength, reliability and life of the nuclear equipment of the Minatom, Russia, has been set up by the decision of the management of the Russian Federation Ministry on the nuclear power (Russia Minatom) within the framework of the Research and Development Institute of Power Engineering (RDIPE). The Engineering Center is responsible for fulfilling the functions of the leading Institution of the Ministry concerning these issues and it is in charge of the development of the appropriate rules and standards package as well as their compliance with analogous international regulating documents. To put forward the national program on NPP aging management, and to implement it is one of the crucial tasks of the Engineering Center. This activity is conducted by both the cooperation between Russian Institution and experts and within the framework of the international collaboration. In the latter case it is worthy of noting the activity with respect to the American-Russian Working Group 12 ''NPP Aging and Life Extension'' and participation in appropriate programs of the IAEA. The major trends of the above activity are considered in this paper

  7. NPP Krsko Severe Accident Management Guidelines Implementation

    International Nuclear Information System (INIS)

    Basic, I.; Krajnc, B.; Bilic-Zabric, T.; Spiler, J.

    2002-01-01

    Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. The USA NRC has indicated that the development of a licensee plant specific accident management program will be required in order to close out the severe accident regulatory issue (Ref. SECY-88-147). Generic Letter 88-20 ties the Accident management Program to IPE for each plant. The SECY-89-012 defines those actions taken during the course of an accident by the plant operating and technical staff to: 1) prevent core damage, 2) terminate the progress of core damage if it begins and retain the core within the reactor vessel, 3) maintain containment integrity as long as possible, and 4) minimize offsite releases. The subject of this paper is to document the severe accident management activities, which resulted in a plant specific Severe Accident Management Guidelines implementation. They have been developed based on the Krsko IPE (Individual Plant Examination) insights, Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidances) and plant specific documents developed within this effort. Among the required plant specific actions the following are the most important ones: Identification and documentation of those Krsko plant specific severe accident management features (which also resulted from the IPE investigations). The development of the Krsko plant specific background documents (Severe Accident Plant Specific Strategies and SAMG Setpoint Calculation). Also, paper discusses effort done in the areas of NPP Krsko SAMG review (internal and external ), validation on Krsko Full Scope Simulator (Severe Accident sequences are simulated by MAAP4 in real time) and world 1st IAEA Review of Accident Management Programmes (RAMP). (author)

  8. The Service Life Evaluation for Concrete Structure of NPP

    International Nuclear Information System (INIS)

    Lee, Choon Min; Kim, Seong Soo; Bae, Sung Hwan; Sik, Yoon Eui

    2014-01-01

    Prolonged exposure to the marine environment degrades the durability of concrete and shortens the service life of concrete due to degradation factors such as chloride, carbonation, freezing and thawing, sulfate. Therefore, many country's organizations like the Korea Concrete Institute (KCI), the American Concrete Institute (ACI), the International Federation for Structural Concrete (FIB), the American Society for Testing and Material (ASTM) which recognized the seriousness of this deterioration proposed equation models to evaluate the service life for the concrete structures. As a result, this paper is to especially consider the service life evaluation using these equation models for concrete structure of NPP in Korea compared with 60 years as a design service life. The concrete durability evaluation for Shin-Hanul NPP units 1 and 2 is carried out by using typically proposed assessment models in domestic and foreign standard. It is confirmed that the service life of concrete durability for each of deterioration factors is significantly higher than 60 years as a design service life. As a result, the study of combined deterioration for the concrete structures of NPP in future is positively necessary and maintenance control through regular monitoring should be conducted to secure safety margin basis

  9. Safe management of NPP ageing in European union

    International Nuclear Information System (INIS)

    Grandemange, J.M.; Saurin, P.; Morel, A.; Delaye, D.; Francia, L.; Wacquier, W.; Morlent, O.

    2001-01-01

    The paper presents the results of a study conducted by Framatome, EDF, Belgatom, Unesa and IPSN, with the support of the European Commission in order to evaluate the practices and provide recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle. The study includes a synthesis of available European and International reports, the identification of potential ageing mechanisms, their effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents. Recommendations are proposed on regulatory aspects, management, prediction, detection, follow, mitigation of physical ageing, human management and adaptation of safety culture and procedures. (author)

  10. Asset management methodology in NPP Cofrentes

    International Nuclear Information System (INIS)

    Galbally, D.; Feijo, J. P.; Sierra, M.

    2011-01-01

    The Cofrentes asset management plan is articulated around the tool SIGAN (computer management system of nuclear assets), this tool allows you to structure in an objective and documented the investment plan aimed at modernization and management of the plant life, achieving a consensus among the parties involved in terms of planning development and implementation.

  11. Plant life management in Hungary

    International Nuclear Information System (INIS)

    Gillemot, F.

    1998-01-01

    The life management in Hungary is in an early stage. The preparation of a suitable database, development of maintenance systems and education of the plant and consultant staff is essential. The Act of Nuclear Safety, the introduction of the 10 years periodic safety review system (periodic licence extension) is a good basis for life management. At the same time the economic changes in the country make the life management difficult. Presently most important task is to prepare the technical environment and the methodology for NPP Life management, and within a few years, when the economy would be consolidated, a real life management will be performed

  12. Safe management of NPP ageing in the European Union

    Energy Technology Data Exchange (ETDEWEB)

    Grandemange, M; Saurin, P [FRAMATOME, 92 - Paris-La-Defence (France); Morel, A; Delaye, D; Petit, R [Electricite de France (EDF), 75 - Paris (France); Francia, L [UNESA (Spain); Wacquier, W [Belgatom, Brussels (Belgium); Morlent, O [Institut de Protection et Surete Nucleaire, 92 - Fontenay aux Roses (France)

    2001-05-01

    The objectives of the study covered by this report consist of providing recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle. This is obtained through a synthesis of the potential ageing mechanisms, their potential effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents. The aspects covered include, in particular, classification of component priorities, identification of degradation phenomena, surveillance methods and preventive maintenance and repair / replacement programs. This synthesis comparison work is the basis for the recommendations issued at the end of the study. (author)

  13. Cernavoda NPP environmental management system - tool for managing the impact on the environment

    International Nuclear Information System (INIS)

    Gabriel, B.; Adrian, J.

    2009-01-01

    Nuclearelectrica SA (SNN SA) is a state owned company which produces nuclear-generated electricity, heat and CANDU 6 type nuclear fuel. The company has also an active participation in the power development program in Romania. The Cernavovoda NPP, one of the SNN branches is situated at 180 km east of Bucharest, in Constanta County at about 2 km SE from Cernavoda town is a CANDU 6 type. Cernavoda Nuclear Power Plant (NPP) is dedicated to generate electrical and thermal power, safely and efficiently for at least 30 years. Having an annual gross output of 5.2 - 5.4 MWh, the Cernavoda Unit 1 NPP provides 10% of the Romanian electric power production. Starting January 01 2007, the Cernavoda Unit 1 NPP supplied into the grid 5518346 MWh electric power and during 1997 - 2007 the Cernavoda Unit 1 NPP supplied into the grid 55769213 MWh electric powers. Over the same period Unit 1 also provided the partial district heating of the town of the Cernavoda supplying about 601517.9 Gcal. Romania second CANDU nuclear power plant, Cernavoda Unit 2, was officially placed in service on Friday, October 5, 2007 together with Unit 1, the CNE-Cernavoda Station is the largest power producer in the country. It now accounts for about 18 per cent of Romania energy supply and significantly reduces its dependency on expensive energy resources from outside of Europe. It provides a structured approach to planning and implementing environmental protection measures. It also establishes a framework for tracking, evaluating and communicating environmental performance. SNN SA mission is to operate the Cernavoda NPP - in a competitive, safe and environmental friendly manner so that the production is optimized and the economic life time of the plant is as long as possible. One major accomplishment is the achievement of ISO 14001 certification for our Environmental Management System (EMS) at Cernavoda NPP. The aim of this paper is to present the EMS implemented and to emphasize the outcomes of the

  14. Project No. 7 - Decommissioning unit at Ignalina NPP. (Engineering and project management)

    International Nuclear Information System (INIS)

    2000-01-01

    In order to manage decommissioning process at Ignalina NPP, a new unit should be established in the framework of the Ignalina NPP organizational structure. The on-site Engineering Project Management Unit (PMU) will adopt an integrated approach to project management , engineering design, planning, procurement, safety and licensing activities at Ignalina NPP site. The PMU will assist the Ignalina NPP management in the development of an integrated decommissioning and waste management strategy

  15. Automated system for management of cementation line at Kursk NPP

    International Nuclear Information System (INIS)

    Petukhov, K.S.; Troshchenko, V.G.; Osintsev, V.V.; Molotkov, V.P.

    2005-01-01

    At Kursk NPP technological scheme of radioactive wastes tempering by dry cement mixture in continuously working mixer with continuous dosing of cement mixture components is accepted. The automated system designed for control and management of liquid radioactive wastes cementation in real time is represented [ru

  16. Decommissioning of the NPP A-1 heavy water management system

    International Nuclear Information System (INIS)

    Medved, J.; Rezbarik, J.; Vargovcik, L.; Vykukel, I.

    2015-01-01

    The paper deals with experience and techniques in the application of decontamination technology and remotely controlled robotic devices for the decontamination and dismantling of the heavy water management system during undergoing decommissioning process of the A-1 NPP as well as treatment of arising liquid waste All of these activities are characterized by high level of radioactivity and contamination. (authors)

  17. Plant life management

    International Nuclear Information System (INIS)

    Charbonneau, S.; Framatome, J.B.

    1992-01-01

    Plant life assessment and extension studies have been performed by numerous companies all over the world. Critical equipment has been identified as well as various degradation mechanisms involved in the plant aging process. Nowadays one has to think what to implement to improve the existing situation in the Nuclear Power Plant (NPP). FRAMATOME has undertaken this thought process in order to find the right answers and bring them to utilities facing either critical concern for plant life extension or the problem of management of power plant potential longevity. This is why we prepared a Plant Life Improvement Action Plan, comprising 10 (ten) major items described hereafter using examples of work performed by FRAMATOME for its utility customers desiring to manage the lives of their plants, both in France with EDF and abroad

  18. Prospects for the NPP Krsko Radioactive Waste Management

    International Nuclear Information System (INIS)

    Knapp, A.; Levanat, I.; Saponja-Milutinovic, D.

    2016-01-01

    Croatia adopted Strategy of radioactive waste, used sources and spent fuel management in 2014, and its Law on radiological and nuclear safety was accordingly modified in 2015. The Strategy foresees (though with some flexibility) and the Law declares decidedly that Croatia will establish a Center for radioactive waste management, in which all necessary facilities for storage and subsequent disposal of the Croatian share of the NPP Krsko radioactive waste and spent fuel will be developed. However, Slovenia and Croatia have recently agreed that a long-term dry storage for spent fuel will be established on the NPP premises by the year 2019. Therefore, only the issues of low and intermediate level waste (LILW) are addressed here. In Slovenia, the LILW repository site Vrbina in Krsko municipality was officially confirmed in 2009. Based on the 2013 investment program for a silo-type disposal facility, preparation of the repository project documentation was contracted with a national engineering company in 2014. Slovenian repository concept has been developed in two variants: one for the Slovenian LILW only, and the other intended to accept the Croatian share of LILW from the NPP as well. In the summer of 2015 Slovenia for the first time made an official offer to Croatia to use Vrbina repository for that purpose. However, the Croatian Strategy also does not preclude the option of management of all LILW from the NPP in Croatia. Therefore, present plan of activities for the third revision of the NPP radioactive waste and spent fuel management program outlines hypothetically symmetrical LILW management options: all in Slovenia, or all in Croatia, or one half in each country. So, what shall it be? This paper discusses the prospects for each of the three above mentioned options. The major problem of the Slovenian disposal plan is its high cost, mostly due to high compensations to the local community, which will be hard to finance without Croatian participation. The simplest

  19. Elements and strategies of Knowledge Management at Cernavoda NPP

    International Nuclear Information System (INIS)

    Valache, C.

    2010-01-01

    The paper highlights that there are Knowledge Management (KM) elements already implemented at Cernavoda NPP, ensuring the safe operation of the plant. The KM process is not formalized yet, but the following elements are part of existing KM practices for Cernavoda NPP organization: Plant policies and procedures are in place; Document control is in place using Document Management system; Configuration management is a complex and well structured process; Training and qualification is based on SAT; Learning from operating experience internal and external is a day by day practice, (procedures, PJB, PROEM, Simulator, RCA, Training, etc.); Work control system is implemented via Ventrix Work Management System; Corrective action tracking is implemented; Workforce planning and human resources management is a continuous process; Communications are implemented by the plant personnel; Company intranet and other web-based solutions (CBT) are put in place; Human performance improvement programme is on going. Also, it is reinforced the need to develop and implement a structured knowledge transfer and retention process for the Cernavoda NPP in order to preserve unique knowledge and skills that could be lost through attrition or planned staffing changes. (author)

  20. Enhancing NPP Safety Through an Effective Dependability Management

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

  1. Integrated tool for NPP lifetime management in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Francia, L. [UNESA, Madrid (Spain); Lopez de Santa Maria, J. [ASCO-Vandellos 2 NPPs l' Hospitalet de l' Infant, Tarragona (Spain); Cardoso, A. [Tecnatom SA, Madrid (Spain)

    2001-07-01

    The project for the Integrated Nuclear Power Plant Lifetime Management System SIGEVI (Sistema Integrado de GEstion de VIda de Centrales Nucleares) was initiated in April 1998 and finalized in December 2000, the main objective of the project being to develop a computer application facilitating the assessment of the condition and lifetime of nuclear power plant components. This constituted the second phase of a further-reaching project on NPP Lifetime Management. During the first phase of this project, carried out between 1992 and 1995, the methodology and strategy for the lifetime management of the Spanish NPP's were developed. Among others, degradation phenomena were assessed and the most adequate methods for their monitoring were defined. The SIGEVI Project has been performed under the management of UNESA (Spanish Electricity Association) and with the collaboration of different engineering firms and research institutes (Tecnatom, Empresarios Agrupados, Ufisa, Initec and IIT), with Vandellos II as the pilot plant. The rest of the Spanish NPP's have also actively participated through the Project Steering Committee. The following sections describe the scope, the structure and the main functionalities of the system SIGEVI. (authors)

  2. Integrated tool for NPP lifetime management in Spain

    International Nuclear Information System (INIS)

    Francia, L.; Lopez de Santa Maria, J.; Cardoso, A.

    2001-01-01

    The project for the Integrated Nuclear Power Plant Lifetime Management System SIGEVI (Sistema Integrado de GEstion de VIda de Centrales Nucleares) was initiated in April 1998 and finalized in December 2000, the main objective of the project being to develop a computer application facilitating the assessment of the condition and lifetime of nuclear power plant components. This constituted the second phase of a further-reaching project on NPP Lifetime Management. During the first phase of this project, carried out between 1992 and 1995, the methodology and strategy for the lifetime management of the Spanish NPP's were developed. Among others, degradation phenomena were assessed and the most adequate methods for their monitoring were defined. The SIGEVI Project has been performed under the management of UNESA (Spanish Electricity Association) and with the collaboration of different engineering firms and research institutes (Tecnatom, Empresarios Agrupados, Ufisa, Initec and IIT), with Vandellos II as the pilot plant. The rest of the Spanish NPP's have also actively participated through the Project Steering Committee. The following sections describe the scope, the structure and the main functionalities of the system SIGEVI. (authors)

  3. Planning and management support for NPP personnel SAT-based training programmes

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

    This paper deals with planning and management support for NPP personnel SAT based training programmes based on IAEA TC Project SLR/0/003 on upgrading NPP personnel training, with the aim of upgrading NPP safety and reliability of NPP operation and maintenance. The costs needed include both Slovak and IAEA sources. Five stages of the Project are defined: planning; organizing; motivating; implementation; control, review and accountability

  4. Hydrogen management strategy for the Loviisa NPP

    International Nuclear Information System (INIS)

    Lundstrom, P.; Routamo, T.; Tuomisto, H.; Theofanous, T.G.

    1997-01-01

    A new hydrogen management scheme has been developed for the Loviisa ice condenser containment as a part of a comprehensive severe accident management (SAM) strategy. The scheme is based on providing sufficient mixing of the containment atmosphere, effective energy removal from the containment, and controlled removal of hydrogen through passive catalytic recombination. The objective of the paper is to demonstrate how this hydrogen management scheme works for a range of relevant severe accident scenarios. (author)

  5. 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.)

  6. Operational risk management for a NPP

    Energy Technology Data Exchange (ETDEWEB)

    Scott, C.K., E-mail: KScott@AtlanticNuclear.ca [Atlantic Nuclear Services Inc., Fredericton, New Brunswick (Canada)

    2013-07-01

    Organizational failures are a hazard to the successful operation of a nuclear power plant. Risk reduction strategies have been developed around two themes: using an understanding of the nature and mechanism of human failures to eliminate them by modifying work processes; or, modifying human behaviour by creating a strong safety culture that overrides the tendency to fail. This paper examines the problem from the perspective of operational risk management. It includes the internal management of operations and the influence of the external environment on the organization. A model is proposed that encompasses all the operational risk factors in the organization's decision making process. To prevent failure the organization must have the capability to adapt and the capacity to evolve. The hazards that would lead to an organizational failure are developed from this evolutionary model. The operational risk management program would include these hazards as well as the conventional nuclear safety hazards. (author)

  7. Accident management insights after the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Degueldre, Didier; Viktorov, Alexandre; Tuomainen, Minna; Ducamp, Francois; Chevalier, Sophie; Guigueno, Yves; Tasset, Daniel; Heinrich, Marcus; Schneider, Matthias; Funahashi, Toshihiro; Hotta, Akitoshi; Kajimoto, Mitsuhiro; Chung, Dae-Wook; Kuriene, Laima; Kozlova, Nadezhda; Zivko, Tomi; Aleza, Santiago; Jones, John; McHale, Jack; Nieh, Ho; Pascal, Ghislain; ); Nakoski, John; Neretin, Victor; Nezuka, Takayoshi; )

    2014-01-01

    The Fukushima Daiichi nuclear power plant (NPP) accident, that took place on 11 March 2011, initiated a significant number of activities at the national and international levels to reassess the safety of existing NPPs, evaluate the sufficiency of technical means and administrative measures available for emergency response, and develop recommendations for increasing the robustness of NPPs to withstand extreme external events and beyond design basis accidents. The OECD Nuclear Energy Agency (NEA) is working closely with its member and partner countries to examine the causes of the accident and to identify lessons learnt with a view to the appropriate follow-up actions to be taken by the nuclear safety community. Accident management is a priority area of work for the NEA to address lessons being learnt from the accident at the Fukushima Daiichi NPP following the recommendations of Committee on Nuclear Regulatory Activities (CNRA), Committee on the Safety of Nuclear Installations (CSNI), and Committee on Radiation Protection and Public Health (CRPPH). Considering the importance of these issues, the CNRA authorised the formation of a task group on accident management (TGAM) in June 2012 to review the regulatory framework for accident management following the Fukushima Daiichi NPP accident. The task group was requested to assess the NEA member countries needs and challenges in light of the accident from a regulatory point of view. The general objectives of the TGAM review were to consider: - enhancements of on-site accident management procedures and guidelines based on lessons learnt from the Fukushima Daiichi NPP accident; - decision-making and guiding principles in emergency situations; - guidance for instrumentation, equipment and supplies for addressing long-term aspects of accident management; - guidance and implementation when taking extreme measures for accident management. The report is built on the existing bases for capabilities to respond to design basis

  8. NPP Krsko Severe Accident Management Guidelines Upgrade

    International Nuclear Information System (INIS)

    Mihalina, Mario; Spalj, Srdjan; Glaser, Bruno; Jalovec, Robi; Jankovic, Gordan

    2014-01-01

    Nuclear Power Plant Krsko (NEK) has decided to take steps for upgrade of safety measures to prevent severe accidents, and to improve the means to successfully mitigate their consequences. The content of the program for the NEK Safety Upgrade is consistent with the nuclear industry response to Fukushima accident, which revealed many new insights into severe accidents. Therefore, new strategies and usage of new systems and components should be integrated into current NEK Severe Accident Management Guidelines (SAMG's). SAMG's are developed to arrest the progression of a core damage accident and to limit the extent of resulting releases of fission products. NEK new SAMG's revision major changes are made due to: replacement of Electrical Recombiners by Passive Autocatalytic Recombiners (PARs) and the installation of Passive Containment Filtered Vent System (PCFV); to handle a fuel damage situation in Spent Fuel Pool (SFP) and to assess risk of core damage situation during shutdown operation. (authors)

  9. Waste management concept during dismantling of KKS NPP in Germany

    International Nuclear Information System (INIS)

    Bacmeister, Georg U.

    2008-01-01

    Full text: This paper gives an overview on the waste management of NPP Stade during dismantling. The general idea is to reduce the radioactive waste to about three percentage of the complete dismantling mass. The NPP Stade in Germany was shut down in November 2003. After a transient phase the license for dismantling was given in 2005. In the following 8 years about 20.000 tones of steel and 120.000 tones of concrete will be put out by the dismantling. The yearly output of steel will by about 100 times higher than during the running time of the NNP. For this a new processes for waste management had to be installed. The waste management during dismantling focus on free release (about 97%). Beside some minor exception, the rest is deemed to be radioactive waste. This will be collected in 1000 packages, which are ready to be sent to a final storage. As until now in Germany no final storage is open (and sending of radioactive waste to another country is forbidden), the NNP Stade build an intermediate storage, where the packages may by saved for longest 40 years. The clearance procedure in Germany is regulated in the radiation protection ordinances. It is based on a nuclide specific set of clearance levels. To fulfil these demands the NNP Stade chose a semi automated system for characterization and documentation, which we develop in accordance to our release license. It guaranties a most accurate determination of the relevant nuclides for a set of dismantling material (some 10 to 100 tones). After the characterization only the gamma-activity of the material is measured in boxes of about 500 kg. A short comparison of the chosen procedure with other options, possible in Germany will be given and the decision from the collaboration with the NPP in Barsebaeck, Sweden, will be withdrawn. Beside the free release different options are used for waste management, like incineration, sending to landfill or reuse in nuclear industry. The waste management of the NNP Stade take

  10. Implementing the Environmental Management System ISO 14001 at the Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Jelev, Adrian

    2003-01-01

    An environmental management plan (EMP) has been developed for the Cernavoda NPP Unit 1. It contains the necessary components for identification and management of the environmental aspects of NPP. The environmental policy of the 'Nuclearelectrica' National Society and the associated EMP are the basis for the Environment Management System that will be implemented at Cernavoda NPP. The final step of this process will be the ISO 14001 certification. This paper points out to the main aspects concerning the implementation of the ISO 14001 system at Cernavoda NPP Unit 1. (author)

  11. Problems of improving the investing process management in NPP construction

    International Nuclear Information System (INIS)

    Denisov, G.A.

    1986-01-01

    Problems of development of the optimal system for the investing process management in NPP construction are discussed. It includes 3 steps: design construction ( including building structure and equipment production ), and achievement of designed technical and economical indices, during reactor start-up. The method for estimating the interest of each participator of the intensing process and developing the optimal solution, that is capable to approach these interests, is suggested. The conclusion is made that it is necessary to develop and confirm the branch standard, which should include a complex amalgamated network of works to improve the organization of the investing process

  12. Croatian Capacity for Management of the NPP Krsko Radioactive Waste

    International Nuclear Information System (INIS)

    Levanat, Ivica; Lokner, Vladimir

    2014-01-01

    Together with Slovenia, Croatia is responsible for management of the NPP Krsko radioactive waste and spent fuel. So far, no firm agreement on specific solutions has been reached between the two countries. On the contrary, all activities related to revision and development of the joint Program of the NPP decommissioning and spent fuel and radioactive waste management were discontinued several years ago. Unless Slovenia and Croatia definitely agree on joint solutions in the meantime, Croatia will have to begin transfer of one half of the NPP Krsko spent fuel and radioactive waste into its territory in about nine years. Presently, however, Croatian capacities for such an undertaking are seriously inadequate in several respects, and they are not developing in any promising way. For no rational reason, this state of the Croatian capacities has been maintained (recently even deteriorating in some respects) for at least a decade, disregarding also for at least two years the explicit requirements of the EU Directive 2011/70/EURATOM aimed at establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste. In fall of 2012, Fund for financing the NPP Krsko decommissioning and spent fuel and radioactive waste disposal was appointed as the Croatian expert organization for revision and development of the program of these same activities it had originally been supposed only to finance. In 2013 the Fund expanded its activities to a low-profile attempt at revitalization of the Croatian radioactive waste repository project, although the Fund is not yet properly capacitated for either of these tasks. The above is hardly in compliance with the Directive requirements, such as to establish 'a national legislative, regulatory and organisational framework' 'that allocates responsibility... between relevant competent bodies'. The lack of competent experts in the field appears to affect the quality of Croatian legislative

  13. NPP capital equipment life control facilities and tools

    International Nuclear Information System (INIS)

    Nekrasov, A.V.; Proskuryakov, K.N.

    2009-01-01

    Algorithms and simulation package for calculation of eigen modes of coolant pressure oscillations in equipment of primary coolant circuit of WWER-1000 NPP, tuned-circuit Q-factor of an oscillating contour of the coolant, fluctuation frequencies pass band and attenuation factors of were developed. Calculation results for cases of presence and absence of gaseous state radiolysis products in the coolant were obtained. Results analysis makes it possible to disclose operating conditions which result in raised vibrations, and to develop control response in NPP industrial control system for their prevention [ru

  14. Approaches to the mathematical description of NPP operational safety management and oversight

    International Nuclear Information System (INIS)

    Bilej, D.V.; Berzhanskij, S.V.

    2014-01-01

    The paper presents analysis of features related to NPP operational safety management and oversight. According to analysis results, approaches are proposed to perform mathematical description of specific processes and to develop a scale for management to the current safety level as regards NPP power generation. Proposed approaches are making experimental equations and process approach of ISO-9001 quality system

  15. MORE: Management of Requirements in NPP Modernisation Projects, final report

    International Nuclear Information System (INIS)

    Fredriksen, R.; Katta, V.; Raspotnig, C.; Valkonen, J.

    2008-09-01

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  16. MORE: Management of Requirements in NPP Modernisation Projects, final report

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. (Inst. for energiteknikk (IFE) (Norway)); Valkonen, J. (Technical Research Centre of Finland (VTT) (Finland))

    2008-09-15

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (author)

  17. Performance indicator system with application to NPP management

    International Nuclear Information System (INIS)

    Gomez, J.; Roldan, J.

    2001-01-01

    The objective of the paper is to present the work that is being conducted in the scope of a research project between Cofrentes NPP and the polytechnic university of Valencia aimed to the development and implementation of a performance indicators system to support plant management. In developing this system, attention is being paid to the areas of safety, production and dependability. The first step in the project was the development of the performance indicator system (PIS), in order to help in assessing the effectiveness of the different activities in plant (i.e. maintenance, inspections, tests, etc.). It is suggested establishing the operational indicators set in 3 levels. The lowest level concerns indicators monitoring performance and maintenance characteristics of components. The next one involves a subset of indicators placed at system level with a similar goal. And finally, the highest level summarizes the impact of the global policy in the whole plant from safety and performance point of view. The definition of an indicator should comprise, at least, the following items: indicator's name, performance area, definition and data needed. A strategy should define what, when and how indicators have to be evaluated, analyzed and reported. This article gives an example application of the methodology at the Cofrentes NPP, collective dose as safety indicator, power production as production indicator and the number of work orders as maintenance indicator are considered and their time evolution is given. (A.C.)

  18. The analysis of financial risk management application for NPP project in Indonesia

    International Nuclear Information System (INIS)

    Imam Bastori; Moch Djoko Birmano

    2012-01-01

    NPP Project is one of full dynamic, risky and challenging business. Application of financial risk management t in Nuclear Power Plant (NPP) project becomes one alternative to be considered carefully. This paper explains an analysis to make a decision in the risk management application so that it can be applied in the NPP's construction in Indonesia. As case study, is NPP of conventional PWR type of class 1150 MWe. To calculate the economics and financing of NPP is used Spreadsheet INOVASI, further the decision of financial risk management were analyzed using a Model of Cash Flow Adjustment, which developed by Richard Fairchild. The analysis showed that the Method of Cash Flow Adjustment developed by Richard Fairchild is better than the method of NPV Adjustment on a NPP project, because it have included the aspects of financial risk management. NPP project can only be executed if the NPV 2 0 and decision to execute the financial risk management should be based on NPVrm > NPV. The application of financial risk management in NPP project is not needed if an insurance premium more expensive than all costs of financial distress, unless the insurance company can give discount of at least 20%. (author)

  19. Transition cycle fuel management problems of NPP Krsko; Problemi gospodarenje gorivom u prijelaznim ciklusima NE Krsko

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, B [Institut ' Rudjer Boskovic' , Zagreb (Yugoslavia); Pevec, D [Elektrotehnicki fakultet, Zagreb (Yugoslavia); Smuc, T; Urli, N [Institut ' Rudjer Boskovic' , Zagreb (Yugoslavia)

    1989-07-01

    Transition cycle fuel management problems are described and illustrated using results and experience attained during core reload design of NPP Krsko. Improved version of computer code package PSU-LEOPARD/Mcrac is successfully applied to NPP Krsko loading pattern design. (author)

  20. Principles of Defense-in-depth philosophy applied in NPP engineering management

    International Nuclear Information System (INIS)

    Wu Guangwei

    2011-01-01

    Based on the Defense-in-depth Concept in nuclear and radiation safety, Defense-in-depth Concept for design management of Nuclear Power Plant (NPP) is developed in this paper to analyze the feasibility and importance of the application of the basic principle: Defense-in-depth concept in NPP systems performed during the design control of NPP. This paper focuses on the NPP engineering management process, and according to the analysis of such process, 5 principles of Defense-in-depth Concept applied in NPP design management are raised: (1) preventing the non-conformities of design via effective design quality management system; (2) discovering and correcting non-conformities of design quality in time via design checkup and design review meeting; (3) carrying out timely analysis and treatment against design non-conformities which have been transferred to construction phase; (4) Assessing and judging the severe non-conformities in construction phase, putting forward treatment opinions and remedies accordingly so as to avoid the existence of such non-conformities in physical construction of NPP; (5) Paying 'return-visit' and performing 'post-assessment' for NPP design to assess the designed functions and safety of NPP comprehensively. (author)

  1. Risk management solutions for Cernavoda Unit #2 NPP completion

    International Nuclear Information System (INIS)

    Chirica, T.; Pall, S.

    2002-01-01

    The greatest risk facing today's electric utilities is change. Utility risk managers are being challenged to address the changes of deregulation, new technologies and changing work force. The utilities must be more aware of where all its costs are located to face with the challenge of competition, forcing them to respond with lower prices and innovative services. For completion of large projects, like Cernavoda NPP, Unit 2, the utilities are facing also with certain specific risks: politic, economic, social. The natural perils or machinery breakdown are common risks for operation as well as for construction-commissioning projects. Beyond the explicit challenges associated with the completion of a nuclear power plant in a transition economy environment, the utilities are facing with new risk factors such as professional liability, political risk, product warranty and liability, international exposure, etc. Changes in other governmental policies are also affecting large projects, mentioning healthcare, workplace safety, workers' compensation, environmental clean up, etc.(author)

  2. The Information System for Operational Activity Organization as a Tool for Configuration Management in NPP

    International Nuclear Information System (INIS)

    Manchev, B. L.; Yordanova, V. S.; Nenkova, B. G.

    2008-01-01

    The Configuration Management (CM) is an integrated management process by means of which conformity between design requirements, physical configuration and the plant documentation is ascertained. This conformity is maintained during the entire life cycle of the facility. CM ensures that during the entire operational life of the plant the following requirements are met: The basic design requirements of the plant are established, documented and maintained; The physical structures, systems and components (SSC) of the plant are in conformity with the design requirements; The physical and functional characteristics of the plant are correctly incorporated in the operational documentation and the documentation for repair, as well as in the documents for tests and training; The changes in the design documentation are incorporated in the physical configuration and the operative documentation; The changes in the design are minimized by management process for review according to approved criteria; The changes proposed in the equipment and documentation of the plant are estimated entirely with the purpose of determining their effect and are reviewed and approved by appropriate managing staff before their introduction. The information system for organization of the operational activity (IS OOA) consists of several modules used for storage and retrieval of data for different aspects of the operation of the equipment at the site of Kozloduy NPP, as defects and failures, design requirements and bases, design data and characteristics, tests, life time, maintenance and repair, as well as changes in the design or the design documentation. IS OOA consists of single relational database and provides built-in connections to the database of the SmartDoc system for control of the documentation, as well as to the database for human resources. Central place in IS OOA is taken by the 'Equipment' module while all other modules are connected with the identification data of the structures

  3. 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

  4. Role and responsibilities of management in NPP personnel training and competence. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    The main aim and result of this seminar was imparting knowledge to various levels of Paks NPP management on their special tasks and responsibilities to achieve personnel competence, which include: meeting relevant regulatory and other requirements; defining the qualifications for NPP personnel jobs; training using systematic approach to training to attain the required level of qualification and competence of all NPP personnel, which includes management, operations, maintenance and technical support personnel and others; recruiting and retaining qualified personnel, including career development; supporting the training of all personnel on their responsibilities for introducing, maintaining and improving safety. Refs, figs and tabs

  5. Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

    International Nuclear Information System (INIS)

    Serban, M.

    1997-01-01

    The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP

  6. Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

    Energy Technology Data Exchange (ETDEWEB)

    Serban, M [Technical Safety Directorate, Unit 1., Cernavoda Nuclear Power Plant (Romania)

    1997-12-01

    The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP.

  7. ''RESURS'' - The Russian scientific-technical programme for NPP equipment lifetime monitoring, estimation, prediction and management

    International Nuclear Information System (INIS)

    Emelyanov, V.

    1994-01-01

    RESURS programme is described implementation of which will allow to work out regulatory-methodological basis providing legal and technical solution of NPP equipment lifetime management, prediction, monitoring and estimation problems

  8. Evaluation of cost of radioactive waste management during the Chernobyl NPP decommissioning

    International Nuclear Information System (INIS)

    Gavrish, V.M.; Tkachev, D.A.

    2009-01-01

    The article presents the results of calculations on evaluation of radioactive waste volumes, the required financing, and the labor expenses for management of radioactive waste that may arise during the decommissioning of Chernobyl NPP Units 1, 2, 3

  9. Planning and management support for NPP personnel SAT-based training programmes

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

    Planning and management support for NPP personnel SAT-based training programmes is described for the following job positions: reactor operator; turbine operator; reactor maintenance worker; pump maintenance worker; chemistry foreman; health physics foreman; electric maintenance worker

  10. Configuration management and change control at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Gheorghiu, Virgil

    1998-01-01

    Effective configuration management requires that: 1. the design basis of station structures, systems, equipment and components be maintained at all times; 2. only accurate and approved technical, operational and maintenance information is available for performance of station activities; 3. correct operating manuals, flowsheets, operating sequences, operating task and training manuals are prepared and maintained currently. Design Engineering at Cernavoda NPP is primarily the responsibility of the Engineering Services Department supported if necessary by the Technical Unit. The key elements needed to achieve excellence in design engineering support for station operation, including design process and implementation of modification are investigated by answering the questions: 1. What is the station expectation for design change control?; 2. How is this provided?. Concerning design, the following aspects are stressed: Detailed Design Development; Design Verification; Design Change Implementation. The present design process is auditable and well documented. It consists of detailed design development, and design output documents such as applicable drawings, procurement specifications, installation and test requirement and the results of design and safety reviews. The design change implementation does not proceed until an Inspection Test Plan has been developed and approved as required. (author)

  11. Knowledge management at Kozloduy NPP - challenges and solutions

    International Nuclear Information System (INIS)

    Tzotchev, S.; Pironkov, L.

    2004-01-01

    Like any highly technical endeavor, the use of nuclear technology relies heavily on a vast accumulation of knowledge - volume upon volume of scientific research, engineering analysis, design documentation, operational data, maintenance records, regulatory reviews and countless other pieces of technical information, combined with complex reservoir of scientists, engineers, technicians and managers with relevant background and expertise. The effective management of nuclear knowledge includes systematic and organized application of accumulated specific knowledge as well as ensuring the sustainable availability of qualified personnel. This means that: 1) The know-how should be properly identified, captured and classified; 2) Adequate tools for support, access and transfer of data should be available; 3) Renewing of workforce without loss of institutional memory should be guaranteed. During the centuries this process has been applied spontaneously and there are a lot of examples that the world use to be workable earlier too. However nowadays this type of spontaneous knowledge management is ineffective. Information volume and the communication efficiency have increased so much that new tools have to be created to handle the knowledge being communicated trough numerous sources. Besides information space is strongly polluted. The information channels provide unnecessary redundant information. Target oriented searching and delivering of useful information is difficult and requires significant resources. What value this know-how represent, how can it be maintained for and passed to the next generation, what are the problems of aging and renewing of workforce, what measures have been taken by Kozloduy NPP and what are the challenges to be faced yet - these are the issues to be addressed in this paper. (authors)

  12. Kozloduy NPP units 3 and 4 rest life time program execution

    International Nuclear Information System (INIS)

    Genov, S.

    2005-01-01

    In this paper the following tasks are considered: Kozloduy NPP units 3 and 4 life time evaluation; programme for the units life time assuring; units 3 and 4 renewals. The main activities for the programme implementation are described and the obtained results are presented. In conclusion, the executed activities of program for assuring the life time of units 3 and 4 of Kozloduy NPP, cogently prove that the lifetime of structures, systems and components, is assured duly and those structures, systems and components will be in service safely, economically effectively and mostly reliable till the end of the 30 years design lifetime. For some of them it has been proved even for 35 and 40 years. Program activities continue during 2005, although the early shutdown of units 3 and 4 is possible

  13. 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.

  14. 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

  15. 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)

  16. The development of techniques for determining the residual life time prediction on NPP equipment

    International Nuclear Information System (INIS)

    Antonov, Alexander V.; Dagaev, Alexander V.; Volnikov, Ivan S.

    1999-01-01

    The problem of determining the residual life prediction of NPP equipment is presently highly pressing. NPP residual life resources are 30 years, but for particular equipment it is much less. Thus, residual life resource for equipment of control and protection system of NPP unit is 5-10 years. The NPP equipment is expensive and its replacing requires much expense. Hence an urgent problem is to study residual life resources of equipment on the basis of statistic information obtained during operation. Deterministic approach of determining residual life resources for particular equipment is widely known in the literature. Physical and statistical models are also being developed for determining the residual life, e.g. the model (loading-bearing capability). The present work offers the techniques of the residual life determination reasoning from statistic information of functioning objects in the process of operation. To put the techniques into effect it is necessary to have information about the time of operation of a group of objects of the same type, the number of failures; it is desirable to know failure operating time, order of the object replacement and the reason which caused the replacement (failure or planned preventive maintenance). Metrics is based on studying the parameters for the series of failures resulted from real statistic data. Then we can proceed to distribution density of the failure working time. For this purpose the Voltarra's equation of the second order is solved f(t) = ω(t) + ∫ 0 t f(t - τ)ω(τ)dτ. Since statistics of data sampling related to failure is small due to difficulties in solution of Voltaire's equation, the authors offer moderate method of solution for the above equation. After distribution density of the failure working time is determined the calculation of equipment residual life is made by the following formula: T τ (t) 1/P(τ)∫ 0 ∞ P(t)dt. The proposed techniques are realised as the software. In the course of working

  17. Remote technology in RBMK-1000 spent fuel management at NPP site

    International Nuclear Information System (INIS)

    Makarchuk, T.F.; Kozlov, Y.V.; Tikhonov, N.S.; Tokarenko, A.I.; Spichev, V.V.; Kaljazin, N.N.

    1999-01-01

    The report describes the remote technologies employed in the nuclear power plant with RBMK-1000 type. Spent fuel transfer and handling operations at reactor (AR) and away from reactor (AFR) on reactor site (RS) facilities are illustrated by the example of the Leningradskaya NPP and are typical for all NPPs with RBMK-1000. The current approach to spent fuel management at NPP sites is also presented. (author)

  18. Ageing management of french NPP civil work structures

    Science.gov (United States)

    Gallitre, E.; Dauffer, D.

    2011-04-01

    This paper presents EDF practice about concrete structure ageing management, from the mechanisms analysis to the formal procedure which allows the French company to increase 900 MWe NPP lifetime until 40 years; it will also introduce its action plan for 60 years lifetime extension. This practice is based on a methodology which identifies every ageing mechanism; both plants feedback and state of the art are screened and conclusions are drawn up into an "ageing analysis data sheet". That leads at first to a collection of 57 data sheets which give the mechanism identification, the components that are concerned and an analysis grid which is designed to assess the safety risk. This analysis screens the reference documents describing the mechanism, the design lifetime hypotheses, the associated regulation or codification, the feedback experiences, the accessibility, the maintenance actions, the repair possibility and so one. This analysis has to lead to a conclusion about the risk taking into account monitoring and maintenance. If the data sheet conclusion is not clear enough, then a more detailed report is launched. The technical document which is needed, is a formal detailed report which summarizes every theoretical knowledge and monitoring data: its objective is to propose a solution for ageing management: this solution can include more inspections or specific research development, or additional maintenance. After a first stage on the 900 MWe units, only two generic ageing management detailed reports have been needed for the civil engineering part: one about reactor building containment, and one about other structures which focuses on concrete inflating reactions. The second stage consists on deriving this generic analysis (ageing mechanism and detailed reports) to every plant where a complete ageing report is required (one report for all equipments and structures of the plant, but specific for each reactor). This ageing management is a continuous process because the

  19. Long-term monitoring as aging management component in the NPP Grohnde

    International Nuclear Information System (INIS)

    Reese, Sven H.; Seichter, Johannes

    2009-01-01

    In the frame of aging management of safety relevant mechanical systems, structures and components (SSC) a classification is performed with respect to the safety relevance. For SSC of group M1 integrity has to be assured, i.e. components must not fail. The other safety relevant components are classified as group M2, i.e. failure is admissible as isolated case. SSC of group M1 in the NPP Grohnde are included into the long-term monitoring system, the annual status report ''fatigue'' has to identify the actual usage value and predict the end-of-life usage. The authors describe the used methodology concerning loading evaluation based on temperature cycling data, the thermal hydraulic modeling using finite element methods for fatigue relevant components.

  20. 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 ...

  1. In-core fuel management for Cofrentes NPP

    International Nuclear Information System (INIS)

    Marco, M.

    1990-01-01

    Hidroelectrica Espanola has established an in-house nuclear analysis capability in Hidrola's Servicio de Ingenieria y Analisis Nucleares (SIAN). This article describes SIAN, its origins, resources, codes, and its work related to the company's 100%-owned Cofrentes NPP. 1 fig., 2 tabs

  2. Knowledge Management Applications at the Paks NPP Ltd

    International Nuclear Information System (INIS)

    Buza, K.

    2006-01-01

    The objective of the human resource policy at the Paks NPP Ltd. is to make available personnel in optimal quantity, either employed or contracted, that are properly selected, trained and equipped with all knowledge, skills and attitudes required for the long term safe, competitive and reliable operation of the plant. The plant's service time extension has been approved as a consequence of which significant efforts must be turned to ensure properly prepared labor force for the long term plant operation. This is only achievable if - using knowledge related to the corporate recruitment needs and the job-specific requirements/expectations - personnel are selected from internal or external resources that can be prepared through expedient, targeted development programs to fill in positions specified as necessary for plant operations. A decisive factor of the achievements of the plant is the staff properly prepared and performing jobs with professionalism. The accumulated collective knowledge and experience of the long years are assets which, - when the future of the plant is planned - can and must be used as a firm foundation. What value does this knowledge represent, how can it be preserved and transferred to the next generation and what steps have been taken already by the plant to achieve this goal? - these are the questions that the paper is to provide a concise response for. The concise program has set the ultimate goal of - while keeping the best of traditional tools such as the spontaneous knowledge management - evolving to address KM in a planned, conscious manner, making use of the achievements of dedicated projects already terminated or on-going (like the Safety Upgrading Program, the Training Reconstruction Project or the Final Safety Report) and introducing a complex, needs-driven career and succession planning system. Planned to run on three main tracks: the selection and development of leaders in frame of the Management Pool of Talents; the selection and

  3. 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

  4. Improvement of Radwaste Management System at Bilibinskaya NPP in the Far North Conditions - 13456

    Energy Technology Data Exchange (ETDEWEB)

    Fedorov, Denis; Adamovich, Dmitry; Savkin, Alexander [SUE SIA Radon, 2/14, 7th Rostovsky lane, Moscow, 119121 (Russian Federation)

    2013-07-01

    Since 2009 Bilibinskaya NPP is getting started to prepare to the decommissioning in the Far North conditions. Bilibinskaya NPP is located in the Far North of Russian Federation in Chukotka region. Since 1974 it operates 4 units EGP-6 with the capacity of 48 MW each. According to the contract, SIA Radon has performed the following works: - LLRW disposal safety analysis, - The technology of spent ion-exchanger and salt residue solidification is proposed, - Expected radwaste (till 2027) management economical analysis, - Technical proposals for LLRW and IRW management. (authors)

  5. Managing RTP Console Upgrading Project: Best Practice for Nuclear Malaysia as TSO in Supporting NPP Development

    International Nuclear Information System (INIS)

    Nurfarhana Ayuni Joha; Syahirah Abdul Rahman; Izhar Abu Hussin

    2011-01-01

    Human Resource Development (HRD) is required for Nuclear Power Programme (NPP). To be a Technical Support Organisation (TSO) for NPP, Nuclear Malaysia should be ready to take the responsibility in supporting Nuclear Regulatory Agency (NRA) and NPP Operators. In nurturing Nuclear Malaysia as TSO, the prime important and focus of HRD for the NPP is the reactor engineering technology. Nuclear Malaysia gives various phases of supports needed to build NPP such as during siting, design, planning, licensing, construction, commissioning, operation and maintenance in its own way and capability. The current Nuclear Malaysia unique approach is the TRIGA PUSPATI reactor (RTP) upgrading project. Research reactor plays an important role in Research and Developpement organization as a nuclear facility to assist the development of NPP. Therefore, upgrading the research reactor is needed to build the skills and gain knowledge of workers to work safely. After 29 years of operation, the RTP system is facing aging problems due to many components in the reactor are outdated. Therefore, immediate action should be carried out to mitigate the aging factor of the reactor to prevent the worsening of the aging problem, and to prevent untoward incident from happening. Action should also cover short and long term planning to prevent current situation from recurring. Currently, RTP is upgrading its console from analog to digital system. One of the achievements in this console upgrading project is the development and implementation of project management. This paper comprises the overview on the RTP console upgrading project, the project management and how this project can lead Nuclear Malaysia to be a good TSO for the development of NPP. (author)

  6. Remaining life prediction of I and C cables for reliability assessment of NPP systems

    International Nuclear Information System (INIS)

    Santhosh, T.V.; Ghosh, A.K.; Fernandes, B.G.

    2012-01-01

    Highlights: ► A framework for time dependent reliability prediction of I and C cables for use in PSA of NPP has been developed using stress–strength interference theory. ► The proposed methodology has been illustrated with the accelerated thermal aging data on a typical XLPE cable. ► The behavior of insulation resistance when the degradation process is linear or exponential has also been modeled. ► The reliability index or probability of failure obtained from this approach can be used in system reliability evaluation to account for cable aging for PSA of NPP. - Abstract: Instrumentation and control (I and C) cables are one of the most important components in nuclear power plants (NPPs) because they provide power to safety-related equipment and also to transmit signals to and from various controllers to perform safety operations. I and C cables in NPP are subjected to a variety of aging and degradation stressors that can produce immediate degradation or aging-related mechanisms causing the degradation of cable components over time. Although, there exits several life estimation techniques, currently there is no any standard methodology or an approach toward estimating the time dependent reliability of I and C cables that can be directly used in probabilistic safety assessment (PSA) applications. Hence, the objective of this study is to develop an approach to estimate and confirm the continued acceptable margin in cable insulation life over time subjected to aging. This paper presents a framework based on the structural reliability theory to quantify the life time of I and C cable subjecting to thermal aging. Since cross-linked polyethylene (XLPE) cables are extensively being used in Indian NPPs, the remaining life time evaluations have been carried out for a typical XLPE cable. However, the methodology can be extended to other cables such as polyvinyl chloride (PVC), ethylene propylene rubber (EPR), etc.

  7. Core Management of NPPs in China and Experience of Tianwan NPP

    International Nuclear Information System (INIS)

    Guohan, G.

    2006-01-01

    The Current Status of the NPPs in China; the Nuclear Power Development Plan till 2020; the Fuel Management and the Core Management Strategy of NPPs are briefly presented in this paper. The gained experience during construction of Taiwan NPP, new design features and major construction milestones of Taiwan NPP are also discussed. The full list of 21 non-conformance reports (NCR) submitted by Jiangsu Nuclear Power Company to NNSA during construction of Taiwan NPP is given. The main issues raised during FSAR review like: RP operation with incomplete number of primary loops; Sedimentation in the construction and piping of service water system; Location of postulated pipe break; Stratification analysis for surge line of pressurizer; Safety classification of equipment in primary circuit; Fire resistant capability of cable insulation; Fire Hazard Analysis; Optimization of protection against ionizing radiation ect. are also listed

  8. Organization and management of maintenance in the NPP's Asco and Vandellos II

    International Nuclear Information System (INIS)

    Folguera, M.; Corral, A.

    2014-01-01

    The article starts with a description of the international framework that, using technical instructions, guides and guidelines, regulates the maintenance of nuclear power plants. It also outlines the characteristics of the organization and management of maintenance in the NPP's operated by ANAV. Such management is supported in a variety of processes and programs among which are: work management, training and qualification, operational experience, supervision, foreign material exclusion, work management in RP areas and outage preparation. (Author)

  9. Radioactive waste management after NPP accident: Post-Chernobyl experience

    International Nuclear Information System (INIS)

    Mikhalevich, A.; Grebenkov, A.

    2000-01-01

    As a result of the Chernobyl NPP accident a very large amount of so-called 'Chernobyl waste' were generated in the territory of Belarus, which was contaminated much more than all other countries. These wastes relate mainly to two following categories: low-level waste (LLW) and new one 'Conventionally Radioactive Waste' (CRW). Neither regulations nor technology and equipment were sufficiently developed for such an amount and kind of waste before the accident. It required proper decisions in respect of regulations, treatment, transportation, disposal of waste, etc. (author)

  10. Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

    Directory of Open Access Journals (Sweden)

    Zsolnay Eva M.

    2016-01-01

    Full Text Available The service life of the Hungarian Paks Nuclear Power Plant (NPP will be extended from the originally planned 30 years to 50 years. To improve the reliability of the results obtained in frame of the old reactor pressure vessel (RPV surveillance programme, new methods have been developed, and based on them, the old exposition data have been re-evaluated for all the four reactor units. At the same time, a new RPV surveillance programme has been developed and introduced, and long term irradiations have been performed to determine the radiation damage of the surveillance specimens due to the high fast neutron exposition. Neutron transport calculations have been performed with a validated neutron transport code system to determine the fast neutron exposition of the RPVs during the extended service life. The cavity dosimetry is in the introductory phase. This paper presents the new developments in the field of the RPV surveillance dosimetry and summarises the results obtained. According to the results the service life of the NPP can safely be extended for the planned 50 years.

  11. NPP Information Model as an Innovative Approach to End-to-End Lifecycle Management of the NPP and Nuclear Knowledge Management Proven in Russia

    International Nuclear Information System (INIS)

    Tikhonovsky, V.; Kanischev, A.; Kononov, V.; Salnikov, N.; Shkarin, A.; Dorobin, D.

    2016-01-01

    Full text: Managing engineering data for an industrial facility, including integration and maintenance of all engineering and technical data, ensuring fast and convenient access to that information and its analysis, proves to be necessary in order to perform the following tasks: 1) to increase economic efficiency of the plant during its lifecycle, including the decommissioning stage; 2) to ensure strict adherence to industrial safety requirements, radiation safety requirements (in case of nuclear facilities) and environmental safety requirements during operation (including refurbishment and restoration projects) and decommissioning. While performing tasks 1) and 2), one faces a range of challenges: 1. A huge amount of information describing the plant configuration. 2. Complexity of engineering procedures, step-by-step commissioning and significant geographical distribution of industrial infrastructure. 3. High importance of plant refurbishment projects. 4. The need to ensure comprehensive knowledge transfer between different generations of operational personnel and, which is especially important for the nuclear energy industry, between the commissioning personnel generations. NPP information model is an innovative method of NPP knowledge management throughout the whole plant lifecycle. It is an integrated database with all NPP technical engineering information (design, construction, operation, diagnosing, maintenance, refurbishment). (author

  12. Planning and management support for NPP personnel SAT-based training programmes. IAEA regional workshop. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Within the European regional TC Project a workshop on Planning and Management Support for NPP Personnel SAT Based Training programmes was held at the Paks NPP Maintenance Training Centre in June 1998. It was organized jointly by IAEA and the Paks NPP. The objective of the workshop was to present the important experience gained by successful implementation of the IAEA Model Project on Strengthening Training for Safe Operation at Paks NPP as well as international experience in developing and carrying out the projects to upgrade NPP personnel training in particular maintenance training, and competence based Systematic Approach to Training (SAT). Twenty five participants from Armenia, Bulgaria, China, Czech republic, Hungary, Romania, Russia, Slovak Republic and Ukraine attended the workshop presenting and exchanging experiences in implementing NPP SAT-based training programmes

  13. The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

    International Nuclear Information System (INIS)

    Zeleznik, Nadja; Kralj, Metka; Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea; Mele, Irena

    2010-01-01

    The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

  14. Scientific management of the commissioning of the Temelin NPP

    International Nuclear Information System (INIS)

    Pazdera, F.; Vasa, I.; Svoboda, C.

    2002-01-01

    A Scientific Supervisory Group (SSG) for the commissioning of the Temelin nuclear power plant was set up by the statutory body of CEZ, a.s. (utility which holds responsibility for the start-up of the plant pursuant to Act No. 18/1997). The SSG provides support to the operator through expertise in nuclear safety assurance and nuclear power plant commissioning. Nuclear Research Institute Rez plc was appointed to this function. The article gives the definition and explains the statute of the SSG, highlights its main tasks and responsibilities, and presents the main results of activities of the SSG. The mission of the International Scientific Council for the Commissioning of the Temelin NPP is also briefly outlined. (author)

  15. Establishment of ''Internal Rules'' and EDMS - Electronic Document Management System at NPP NEK

    International Nuclear Information System (INIS)

    Mandic, D.

    2012-01-01

    The main purpose of this paper is to present NPP's plans regarding the on-going project that started in November 2011, and that is related to the establishment of ''Internal Rules'' and EDMS - Electronic Document Management System.The term ''Internal Rules'' has been directly translated from Slovenian language (''Notranja pravila'') and adopted from the translated version of appropriate Slovenian national codes (ZVDAGA [1] in Slovenian language or PDAAIA [2] in English version). ''Internal Rules on capture and storage of materials in digital form'' refer to the rules adopted by a person as his/her internal act with reference to storage of his/her material. The main purpose for the establishment of the Internal Rules is to be able to justify that Krsko NPP is organized in compliance with the national codes covering that subject and strictly performing according to those Internal Rules. Once a Slovenian company achieves recognized and registered status in accordance with the Internal Rules document that has been certified and approved by the ARS (Archives of the Republic Slovenia), such company can utilize e-documents in the same way as they would utilize physical documents. Furthermore, a Slovenian company with approved Internal Rules can use e-documents in any legal aspect associated with the document's life cycle and the document's content as they would use the physical document or an authorized and approved copy of the physical document. Related to the nuclear regulatory background, NEK operates in compliance with the Slovenian legislation and also the US codes, regulations and guidelines; therefore, regarding the NPP specific documents, the Internal Rules and EDMS must also be in compliance with them. Since early 1990's, NEK has implemented document/records management system oriented towards supporting storage and management of physical documents/records and controlling distribution of active document copies. Document/records management system was supported by

  16. Radioactive waste management at Cernavoda NPP after 5 years of experience

    International Nuclear Information System (INIS)

    Raducea, D.

    2002-01-01

    Many human activities generate waste but people are worried about those produced in nuclear power plants. Their concern is an unjustified fear toward the hazard from radioactive wastes because any country, which produces electrical power in this way, pays a lot of attention of all relevant parties involved in radioactive waste management. The same policy is applied for Cernavoda NPP. Our concept establishes the general approach required for the collection, handling, conditioning and storage of radioactive waste from Cernavoda NPP Unit 1 and will be ready for expansion when other units are brought into service. Among others, a major objective is to reduce the radioactive waste production and volume. In this regard we are trying to improve as much as possible our procedures and radioactive wastes management. Further, it will be presented the radioactive waste management, including the improvements in our program and the future plans.(author)

  17. Life management plants at nuclear power plants PWR

    International Nuclear Information System (INIS)

    Esteban, G.

    2014-01-01

    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)

  18. A lifecycle management program for NPP turbine balance of plant

    International Nuclear Information System (INIS)

    Manabe, Jun; Yamakami, Katsuhiko; Hiraoka, Satoshi; Kawai, Toshinari

    2009-01-01

    A lifecycle management program, for turbine balance of plant of light water reactor units which had been operated for more than 20 years but still having a long intended residual life time, was proposed and implemented from the view point of system and equipment supplier. Here would be introduced the program executed for several utilities. The program consists of unit surveillance analyzing both operation and inspection data, degradation assessment for the equipment and prospecting for the future by planning the proper measures for the issues based on both technology and economy. The program is introduced exampling the generating power affected by main steam pressure reduction derived from the scale adhesion and degradation of equipment. Multidisciplinary optimum design for the replacement of the feedwater heaters, one of the items of the planning, is introduced. Additionally would be introduced the new concept maintenance support program, mainly applied to the units already replaced their principal machines and auxiliaries, configured with both the condition based maintenance system monitoring the trend of parameters of a component and the diagnosis of malfunctions ascertaining the equipment by analyzing and synthesizing operation parameters. (author)

  19. Rest lifetime evaluation and ageing management in NPP 'Kozloduy' unit 1-4

    International Nuclear Information System (INIS)

    Erve, M.; Heck, R.; Schmidt, J.; Daum, G.; Bataklieva, L.; Stoev, M.

    1999-01-01

    In 1992 as a result of an IAEA SRM review the 'WANO 6-month program' has been issued to improve operation, maintenance nad safety culture for the four WWER 440/230 units at the NPP 'Kozloduy' Siemens has awarded 3 contracts related to RTL evaluation of the main equipment, integrity of reactor pressure vessel and to the leak-before-break behaviour of the main piping od unit 2. It is pursuit an overall strategy that allows to: implement on the basis of RTL evaluation a long term ageing management program (AMAP) for Kozloduy's units 1-4 to assure their operation until the end of their design life; identify those components and equipment for which from the safety point of view urgent and immediate actions have to be performed; increase step by step the safety and reliability according to the Western standards and to internationally accepted safety culture; keep open the possibility of life extension as far as this would be technically feasible and acceptable and economically reasonable. Under the technical leadership of Siemens studies have been performed related to the subject of integrity and RTL, such as: reirradiation of RPV samples from Unit 1 and 2; evaluation of PV embrittlement of Unit 1; transfer of the results of LBB assessment of Unit 2 to Units 1, 3 and 4; transfer of results of RTL evaluation of Unit 2 to Units 1, 3 and 4; PTS analysis of RPV of Unit 1, 2,3 and 4. The main remarkable results are: no life-limiting mechanisms detected, requiring immediate actions, except for RPVs; residual lifetime determined for RPVs on reliable basis of advanced modern PTS analysis and sample testing; necessary activities in monitoring of ageing and in-service inspection clearly identified successful proof of lBB for main primary piping after slight modification of supports; international experts agreement reached (e.g. Risk Audit, successful IAEA experts meetings and OSART missions)

  20. 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

  1. 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....

  2. 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...

  3. Development of regulatory guide for review of aging management of the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung [Cheongju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2001-03-15

    This is the final report of the second year study. Based on the first year study, proposal of revised guidelines, analysis of revised or newly issued IAEA safety guides and reference guidelines of developed countries, and proposal of detailed guidelines of aging management in PSR have been performed in the second year study. The summary of results in the study so far can be summarized as below, overall view on PSR and idea of effective domestic application were leaded through additional investigation and comparison of legal basis, experiences and current status of PSR implementation among the countries having operating NPPs including Korea. Strategies of adequate application of PSR are roughly reevaluated and totally reestablished in summary from the analysis in factor by factor basis of PSR implementation experience in foreign countries and background of IAEA guidelines. Models and draft framework of PSR report in the first year study were summarized and reevaluated, and structure and outline options of PSR guidelines for judging the PSR report are newly proposed with comparison of their strengths and weaknesses based on the first year study. Among the opt ions, guidelines framework equivalent to the PSR report was picked up as the best. For the judgement of aging management, the most appropriate one was chosen for the detailed judgement of aging management review in our PSR being based on the Standard Review Plan for License Renewal (SRP-LR) in United States considering potential future usage in the judgement for continued operation of old NPP at the time of expiration of its design life. A draft PSR guidelines is prepared and attached by revision of basic guidelines issued in 2000, considering the issues discussed for the draft revision of IAEA PSR guide, the draft IAEA document about 'experience of PSR implementation of member states', and the characteristics of Hungarian PSR Guidelines.

  4. 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

  5. Fuel management study on quarter core refueling for Ling Ao NPP

    International Nuclear Information System (INIS)

    Zhang Hong; Li Jinggang

    2012-01-01

    The fuel management study on quarter core refueling is introduced for Ling Ao NPP. Starting from the selection of the objective of fuel management for quarter core refueling, the code and method used and the analysis carried out are explained in details to reach the final loading pattern chosen. The start-up physics test results are listed to demonstrate the realized quarter core fuel management. In the end, the advantage and disadvantage after turning to quarter core refueling has been given for the power plant from the fuel management point of view. (authors)

  6. New version of NPP Krsko Decommissioning program and LILW and spent fuel management

    International Nuclear Information System (INIS)

    Zeleznik, N.; Mele, I.; Jenko, T.; Lokner, V.; Levanat, I.; Rapic, A.

    2004-01-01

    According to the requirements of the bilateral agreement between Republic of Slovenia and Republic of Croatia on the legal and other obligations for Nuclear power plant (NPP) Krsko the Decommissioning program was prepared. The main purpose of the program was to estimate the overall expenses of the future decommissioning, radioactive waste and spent fuel management of the NPP Krsko in order to establish separate fund in Croatia and to correct the rate per kWh collected in the existing decommissioning fund in Slovenia. The program looked at all possible scenarios of dismantling, radioactive waste and spent fuel management and proposed the most plausible two scenarios which are technically possible and financially feasible. (author)

  7. Application of the combined cycle LWR-gas turbine to PWR for NPP life extension, safety upgrade and improving economy

    International Nuclear Information System (INIS)

    Kuznetsov, Yu.N.; Gabaraev, B.A.

    2002-01-01

    Full text: The unconventional technology to extend the lifetime for the NPPs now in operation and make a construction of new NPPs cheaper - erection of steam-gas toppings to the nuclear power units - is considered in the paper. Application of the steam-gas toppings permits through reducing power of ageing reactors to extend lifetime of nuclear power unit, enhance its safety and at the same time to keep full load operation of NPP turbine and other balance-of-plant equipment. Proposed technology is examined for Russian VVER-440 reactor as an example and, also, as a pilot project, for Russian boiling VK-50 reactor now in operation Application of the steam-gas topping permits: extend the service life of ageing VVER-440 reactor by 10...15 years; use the turbine and other NPP balance-of-plant equipment at full power; increase the efficiency of combined cycle up to 48% and more; enhance the safety of NPP operation; utilize NPP balance-of-plant equipment after reactor decommissioning; perform the cost-effective operation in maneuvering modes; increase capacity factor of the plant. The construction of pilot project on the basis of the VK-50 reactor will allow not only to demonstrate new technology but also to attain appreciable economic effect including that obtained due to using the available reserves of the NPP turbine. (author)

  8. 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....

  9. Server application for automated management training system of NPP personnel

    International Nuclear Information System (INIS)

    Poplavskij, I.A.; Pribysh, P.I.; Karpej, A.L.

    2016-01-01

    This paper describer the server side of automated management training system. This system will increase the efficiency of planning and accounting training activities, simplifies the collecting the necessary documentation and analysis of the results. (authors)

  10. Qinshan NPP in-core fuel management improvement

    International Nuclear Information System (INIS)

    Kong Deping; Liao Zejun; Wu Xifeng; Wei Wenbin; Wang Yongming; Li Hua

    2006-01-01

    In the 10-year operation of Qinshan Nuclear Power Plant, the initial designed reloading strategy has been improved step by step based on the operation experiences and the advanced domestic and international fuel management methods. Higher burnup has been achieved and more economic operation gained through the loading pattern improvement and the fuel enrichment increased. The article introduces the in-core fuel management strategy improvement of Qinshan Nuclear Power Plant in its 10-year operation. (authors)

  11. 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)

  12. Strengthening ALARA approach in work management at Krsko NPP

    International Nuclear Information System (INIS)

    Breznik, B.; Kovac, Z.; Sirola, P.

    1999-01-01

    As Low As Reasonably Achievable (ALARA) occupational exposures at nuclear power plants should be included in work management as a concept. There are world-wide trends required by the utilities for improved design, operation and maintenance. Within the period of seventeen years of plant operation maintaining low radiation exposures requires additional efforts. The benefit of this effort should be reducing risks to nuclear workers, better work planning and performance. The Krsko Plant ALARA organisations has been revised recently and built on different levels of the hierarchy. The goal is to promote good industry practice and the management of work on primary systems. The established ALARA programme describes the objectives and defines the procedures and tools for its implementation. Brief presentation of the programme as well as organisational responsibilities of dedicated ALARA committee and working groups is the scope of this paper. The management tools and ALARA indicators are discussed to implement the programme and to evaluate the results.(author)

  13. Investigating a Link Between Knowledge Management and NPP Organizational Performance

    International Nuclear Information System (INIS)

    Grosbois, J. de

    2011-01-01

    Effective knowledge management (KM) enhances a firm's capability to assimilate, create and exploit knowledge. KM is widely recognized in both the management literature and in practice as an important enabler of long term organizational performance. Its role is particularly important in technology intensive industries such as the nuclear power industry. Various nuclear power plants (NPPs) around the globe have begun to recognize the strategic importance of KM initiatives in achieving sustained high levels of operational performance. Although these organizations have been involved in KM-related activities for some time, they typically have not viewed and managed these activities from a KM perspective. Several NPPs have been early adopters of KM practices in the nuclear industry, and have been proactive in implementing company-wide KM programmes. However, at most NPPs, the concepts and benefits of KM are only beginning to be understood and have yet to be applied. Atomic Energy Canada Ltd. (AECL) undertook a research project entitled Knowledge Management (KM) for Nuclear Power Plants (NPPs), which formed part of the IAEA's Coordinated Research Project (CRP) on Comparative Analysis of Methods and Tools for Nuclear Knowledge Preservation. The programme scope of work included the following activities: conducting a literature review, participation in IAEA KM meetings and Assist Visits to NPPs, development of an industry survey, peer review and trial of the survey, and preparation of a summary report. This paper summarizes findings of the research done at AECL under this CRP.

  14. Client application for automated management training system of NPP personnel

    International Nuclear Information System (INIS)

    Pribysh, P.I.; Poplavskij, I.A.; Karpej, A.L.

    2016-01-01

    This paper describes the client side of automated management training system. This system will optimize the speed of the organization and quality of the training plan; reduce the time of collecting the necessary documentation and facilitate the analysis of the results. (authors)

  15. Information technologies in radioactive waste management, applied in NPP-Kozloduy, Bulgaria

    International Nuclear Information System (INIS)

    Jeliazkov, J.; Jeliazkova, L.; Atanasov, Sv.

    1994-01-01

    Radioactive waste (RAW) management in NPP is a complex problem, that can be considered as a combination of sub problems, for example scientific, administrative, social, economical, etc. The separate examination of these sub problems does not lead to creation of overall system for optimal RAW management. There's no doubt that such an administrative system, supported by information technologies, should present in every one existing and planned nuclear power plant to optimize its operation as a whole, not only separate elements. The aim is to avoid the fallacy of the single and the complex. This paper presents a basic part of the whole information management system as defined above that concerns RAW management. The information management system is prepared for NPP-Kozloduy, Bulgaria by means of modern concepts and technological schemes and is aimed to help the administrative personnel in this very important activity - RAW management. On the base of objective data about the available waste and prognoses about arisings in the future, on the base of chosen technologies and equipment the system gives multi-variant plan for treatment, processing and disposal of waste, after the choice of a variant it monitors its application in the practice

  16. Research on Integration of NPP Operational Safety Management Performance Systems

    International Nuclear Information System (INIS)

    Chi, Miao; Shi, Liping

    2014-01-01

    The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

  17. Use of a Computerized Tool (ORAM) to Help Manage Outage Safety and Risk at NPP Krsko

    International Nuclear Information System (INIS)

    Spiler, J.; Basic, I.; Vrbanic, I.; Fifnja, I.; Kastelan, M.; Dagan, W. J.; Shanley, L. B.; Naum, T. J.

    1998-01-01

    Outage Risk Assessment and Management (ORAM) is a computerized methodology developed by the U.S. Electric Power Research Institute (EPRI) to help Nuclear Power Plant personnel manage the risk and safety associated with refueling and forced plant outages. Today, over 60 plants including NPP Krsko are using ORAM during the preparation and performance of plant outages. In fact, many plants are attributing much of the reductions in the duration of refueling outages to the use of ORAM. The success of the ORAM methodology is the capability to provide plant and management personnel with understandable results from both deterministic evaluations of plant safety and quantitative risk assessments. The Nuklearna Elektrarna Krsko (NEK) use of ORAM involves both of these approaches. The deterministic portion of ORAM is used to model the NPP Krsko Shutdown Technical Specifications and administrative considerations. The probabilistic portion of ORAM uses industry and NEK specific initiating events and other risk elements pertaining to shutdown to derive a quantitative risk assessment for various end states, including core damage and RCS boiling. This paper expands on the value of each approach and demonstrates the benefits of combining these elements in the decision-making process. Another key advantage of ORAM is the ability to apply the methodology to specific outages. Since no outage is identical, this provides tremendous benefits to plant personnel for managing the safety and risk of a particular outage. ORAM does this ba organizing all of the various plant configurations and equipment unavailability windows into numerous plant states. Furthermore, ORAM evaluations can be a utomated b y interfacing with outage scheduling software programs such as Primavera. For each plant state, the deterministic and the probabilistic logic evaluations are applied. This paper will demonstrate the ORAM evaluation for an actual NPP Krsko outage. (author)

  18. 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)

  19. PTS assessment - The basis of life time evaluation at NPP Paks

    International Nuclear Information System (INIS)

    Elter, J.; Oszwald, F.; Ratkay, S.; Fekete, T.; Gillemot, F.; Marothy, L.

    1997-01-01

    Plant specific PTS analysis at NPP Paks was performed in the frame of the AGNES (Advanced General New Evaluation of Safety) project. NPP Paks belongs to the second generation of the WWER-440/213 NPP-s. To verify the safety during transient events and predict the lifetime of the RPV-s several transient cases have been analyzed. The paper summarizes: The general scheme elaborated for the assessment; the safety philosophy used; the applied and available codes and methods; the ongoing and planned developments. (author). 8 refs, 3 figs, 1 tab

  20. PTS assessment - The basis of life time evaluation at NPP Paks

    Energy Technology Data Exchange (ETDEWEB)

    Elter, J; Oszwald, F; Ratkay, S [NPP Paks (Hungary); Fekete, T; Gillemot, F; Marothy, L [Atomic Energy Research Inst., Budapest (Hungary)

    1997-09-01

    Plant specific PTS analysis at NPP Paks was performed in the frame of the AGNES (Advanced General New Evaluation of Safety) project. NPP Paks belongs to the second generation of the WWER-440/213 NPP-s. To verify the safety during transient events and predict the lifetime of the RPV-s several transient cases have been analyzed. The paper summarizes: The general scheme elaborated for the assessment; the safety philosophy used; the applied and available codes and methods; the ongoing and planned developments. (author). 8 refs, 3 figs, 1 tab.

  1. Practice of fuel management and outage strategy at Paks NPP

    International Nuclear Information System (INIS)

    Farago, P.; Hamvas, I.; Szecsenyi, Zs.; Nemes, I.; Javor, E.

    2000-01-01

    The Paks Nuclear Power Plant generates almost 40% of Hungarian electricity production at lowest price. In spite of this fact the reduction of operational and maintenance costs is one of the most important goal of the plant management. The proper fuel management and outage strategy can give a considerable influence for this cost reduction. The aim of loading pattern planning is to get the required cycle length with available fuel cassettes and to keep all key parameters of safety analysis under safety limits. Another important point is production at profit, where both the fuel and spent fuel cost are determining. Earlier the conditions given by our only fuel supplier restricted our possibilities, so at the beginning the fuel arrangement changing was the only way to improve efficiency of fuel using. As first step we introduced the low leakage core design. The next step was the 4 years cycle using of some cassettes. By this way nearly half of 3 years cycle old cassettes remained in the core for fourth cycle. In the immediate future we want to use profiled cassettes developed by Russian supplier. Simultaneously we will load new type of WWER cassettes with burnable poison developed by BNFL Company. Hereby we can apply more BNFL cassettes for four years cycle even more. Both cost of fuel and number of spent fuel can be reduced besides keeping parameters under safety limits. The Hungarian in service inspection rules determine that every four year we have to make a complete inspection of reactor vessel. Therefore earlier we had two types of outages. Every 4 years we planned a long outage with 55-65 days duration and normal ones with about 30-35 days duration between the long ones. During the normal outages this way did not give us enough room to utilise the shortest possible critical path determined by works on reactor. Some years ago we changed our outage strategy. Now we plan every 4 years a long outage, and between them one normal and two short ones. As a result the

  2. 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)

  3. Information on current status of equipment and activities for extension of NPP Kozloduy life time

    International Nuclear Information System (INIS)

    Pekov, B.

    1995-01-01

    The NPP Kozloduy personnel activities are described directed to undertake measures to overcome the difficulties entailed by equipment failures and human errors in order to avoid recurrent emergency events and to reduce their total numbers. 12 figs, 2 tabs

  4. International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

    International Nuclear Information System (INIS)

    Barbashev, S.V.

    1997-01-01

    The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

  5. Decommissioning of Brennilis NPP

    International Nuclear Information System (INIS)

    Baize, Jean-Marc

    1998-01-01

    This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

  6. Development of tools to manage the operational monitoring and pre-design of the NPP-LV cycle

    International Nuclear Information System (INIS)

    Perusquia, R.; Arredondo S, C.; Hernandez M, J. L.; Montes T, J. L.; Castillo M, A.; Ortiz S, J. J.

    2015-09-01

    This paper presents the development of tools to facilitate the management so much, the operational monitoring of boiling water reactors (BWR) of the nuclear power plant of Laguna Verde (NPP-LV) through independent codes, and how to carry out the static calculations corresponding to process of optimized pre-design of the reference cycle next to current cycle. The progress and preliminary results obtained with the program SACal, developed at Instituto Nacional de Investigaciones Nucleares (ININ), central tool to achieve provide a management platform of the operational monitoring and pre-design of NPP-LV cycle are also described. The reached preliminary advances directed to get an Analysis center and automated design of fuel assembly cells are also presented, which together with centers or similar modules related with the fuel reloads form the key part to meet the targets set for the realization of a Management Platform of Nuclear Fuel of the NPP-LV. (Author)

  7. 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

  8. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014)

    International Nuclear Information System (INIS)

    Gonzalez Fernandez-conde, A.; Brochet, I.; Ferreira, A.

    2015-01-01

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  9. Plant Engineering and Construction System with Knowledge Management: A Case Study in NPP Construction in Hitachi-GE NE

    International Nuclear Information System (INIS)

    Mochida, T.; Hamamoto, M.; Nakamitsu, N.

    2016-01-01

    Full text: Hitachi-GE Nuclear Energy, Ltd. (HGNE) has more than 40 years BWR plants construction experience. The company continues to develop plant engineering system and plant construction systems based on the experience and the lessons learned. Currently, these systems are integrated in a variety of knowledge bases using the latest information technology (IT). Their performance is continuously validated in the recent NPP constructions. Typical examples are shown as case studies for knowledge management. These plant engineering and construction management systems are essential to achieve the on-time and on-budget-goals in NPP construction projects. (author

  10. Life Cycle Collection Management

    Directory of Open Access Journals (Sweden)

    Helen Shenton

    2003-09-01

    Full Text Available Life cycle collection management is a way of taking a long-term approach to the responsible stewardship of the British Library's collections and is one of the Library's strategic strands. It defines the different stages in a collection item's existence over time. These stages range from selection and acquisitions processing, cataloguing and press marking, through to preventive conservation, storage and retrieval. Life cycle collection management seeks to identify the costs of each stage in order to show the economic interdependencies between the phases over time. It thereby aims to demonstrate the long-term consequences of what the library takes into its collections, by making explicit the financial and other implications of decisions made at the beginning of the life cycle for the next 100 plus years. This paper describes the work over the past year at the British Library on this complex and complicated subject. It presents the emerging findings and suggests how it can be used for practical reasons (by individual curators and selectors and for economic, governance and political purposes. The paper describes the next steps in the project, for example, on a predictive data model. The British Library is seeking to benchmark itself against comparable organisations in this area. It intends to work with others on specific comparison for example, of life cycle costing of electronic and paper journals, as a prelude to eliding digital and 'traditional' formats.

  11. Materials ageing degradation programme in japan and proactive ageing management in NPP

    International Nuclear Information System (INIS)

    Shoji, T.

    2013-01-01

    Predictive and preventive maintenance technologies are increasingly of importance for the long term operation (LTO) of Light Water Reactor (LWR) plants. In order for the realization LTO to be successful, it is essential that aging degradation phenomena should be properly managed by using adequate maintenance programs based on foreseeing the aging phenomena and evaluating their rates of development, where Nuclear Power Plants can be continued to operate beyond the original design life depending upon the regulatory authority rules. In combination with Periodic Safety Review (PSR) and adequate maintenance program, a plant life can be extended to 60 years or more. Plant Life Management (PLiM) is based upon various maintenance program as well as systematic safety review updated based upon the state of the art of science and technology. One of the potential life time limiting issue would be materials ageing degradation and therefore an extensive efforts have been paid world-widely. In 2007, NISA launched a national program on Enhanced Ageing Management Program and 4 nationwide clusters were formed to carry out the national program where materials ageing degradation was one of the major topics. In addition to these degradation modes, one important activities in this program is proactive materials degradation management directed by the author which is a kind of the extension program of NRC PMDA program based upon more fundamental approach by a systematic elicitation by the experts nominated from all over the world. NISA program can be divided into two phases, one is from fiscal years (FY) 2006 - 2010 and the other FY 2011. Later phase is focusing more on System Safety due to Fukushima NPP accident. The main objectives of the Phase I is to evaluate potential and complex degradation phenomena and their mechanisms in order to identify future risks of component aging in nuclear power plants. The following items are of particular concern in this phase: (a) investigation of

  12. Implementation of an indicator-based safety management system for the EnKK NPP's

    International Nuclear Information System (INIS)

    Bassing, G.; Nasellu, M.; Ritter, J.

    2004-01-01

    This presentation at the Eurosafe Berlin 2004 will give an overview of the activities on safety management of EnBW Kernkraft GmbH taken up with a notifiable event in August 2001 at KKP 2 nuclear site. After this event EnBW announced the development and introduction of an indicator-based safety management system (SMS) at all sites of its nuclear power plants. A SMS team with members from all NPP sites was built which had to analyse all processes based on the DIN EN ISO 9000 philosophy and to control them by indicators. The regulatory authorities and their experts would accompany this process in a suitable fashion and monitor and review it after its introduction. This presentation shows the process during the development of the system, the status of its introduction and the general involvement of the regulator. (orig.)

  13. Structure design of human factor data management system for Daya Bay NPP

    International Nuclear Information System (INIS)

    Zhang Li; Zhang Ning; Guo Jianbing; Huang Weigang; Zhu Minhong; Wang Jin

    2000-01-01

    Collection, analysis and quantification of human factor data are important compositions of human reliability analysis (HRA) and probabilistic risk assessment (PRA). Various human factor databases have been set up, but there are comparatively little human factor data management systems which can be uses for collection, classification, analysis, calculation and predication of the human factor data. Therefore, the human factor data management system for Daya Bay NPP is developed, with the following three modules and four databases: original data module, computing module, introduced data module, and basic database, other data source of the plant, external database and introduced database. The foundational problems about human factor data and the systemic structure and function are described. The data structure in the database is also discussed, because it is of the most importance in the system

  14. Trends and results in In-Core management for the Kozloduy NPP WWER-440 reactors

    International Nuclear Information System (INIS)

    Haralampieva, Tz.; Antov, A.; Georgieva, N.; Spasova, V.

    2001-01-01

    The paper presents the experience gained during the design and operation of the last fuel cycles of the four WWER-440/V-230 units at Kozloduy NPP. High efficiency and economy of the fuel utilization requires very precise procedures for fuel in-core management, including calculations and analyses for reloading scheme design, compared with results from operational measurements and fuel cycle efficiency. The paper describes the main stages of implementation of advanced fuel assemblies in the Kozloduy NPP WWER-440 reactors. New advanced fuel has been implemented after the completion of comprehensive neutron-physical, thermal-hydraulic and thermal-mechanical analyses by using advanced computer codes. As a general task of the fuel cycle improvements it is pointed the increasing of the final fuel burnup and decreasing of the number of spent fuel assemblies. Series of calculations and analyses, related to the introducing of the advanced fuel assemblies and improvement of the fuel cycle characteristics have been carried out to guarantee the safe operation and fuel reliability

  15. Steam generator life management

    International Nuclear Information System (INIS)

    Tapping, R.L.; Nickerson, J.; Spekkens, P.; Maruska, C.

    1998-01-01

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermal hydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. This report shows how recent advances in cleaning technology are integrated into a life management strategy, discusses downcomer flow measurement as a means of monitoring steam generator condition, and describes recent advances in hideout return as a life management tool. The research and development program, as well as operating experience, has identified

  16. Ageing management of EDF NPP concrete structures: from the theory to the reality

    International Nuclear Information System (INIS)

    Gallitre, E.; Brunet, C.

    2009-01-01

    This paper presents EDF practice about concrete structure ageing management, from the materials analysis to the formal procedure which allows EDF to increase 900 MWe NPP lifetime until 40 years. This practice is based on a methodology which identifies every ageing mechanism, then both plants feedback and state of the art are screened and conclusions are drawn up and taken into account into an 'ageing analysis data sheet'. That leads to a collection of 57 data sheets: if the data sheet conclusion is not clear enough, then a more detailed report is launched. This ageing management detailed report gathers every theoretical knowledge and monitoring data; its objective is to propose a solution for ageing management: this solution can include more inspections or specific research development. After a first practise on the 34 French 900 MWe PWR units, only 2 generic ageing management detailed reports have been needed for the civil engineering part: one about reactor building containment which focuses on two mechanisms: steel liner corrosion and pre-stress losses, and one about other structures which focuses on Alkali-Aggregate Reaction (AAR). (authors)

  17. 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

  18. Development of the regulatory guide on the management of aging for the operating NPP

    International Nuclear Information System (INIS)

    Shin, Tae Myung; Lee, Jae Kyung; Byeon, Chang Soo; Kim, Hyo Soo; Kim, Young Ryul; Eun, Hui Kwang

    2000-03-01

    this is the first final report, and it includes the analysis of PSR regulation status for the operating NPP of foreign countries and thus established scope and method of Korean PSR. The detailed requirements of aging management, as one of the most important factors, is planned to be dealt in the second final report, The result of study so far can be summarized as below, The necessity and feasibility of domestic PSR application is confirmed through the investigation, comparison and review of PSR implementation and regulation status in foreign countries, And, detailed analysis of vaseline guidelines of IAEA performed to establish a skeleton of desirable safety review guideline for Korean NPP. Our own objectives, scope and strategy of review for PWR are roughly set up form factor by factor analysis of PSR implementation experience in foreign countries and background of IAEA guidelines. The essential elements of review for each PSR safety factors are classified and proposed. For efficient review of proposed safety factors and elements, three different option of framework for PSR guidelines are proposed and compared. Through analysis of strength safety factors and elements, three different options of framework for PSR guidelines are proposed and compared. Through analysis of strength and weakness of the three optional frameworks proposed for Korean PSR guideline, the third one is recommended as the best for both owner and regulator. By maintaining the current framework of SAR at maximum and, at the same time, referring the basic concept of IAEA PSR guide, the detailed contents and its review elements are chosen. The standards on the aging was proposed preliminarily for the application of aging evaluation in PSR

  19. Development of the regulatory guide on the management of aging for the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung; Byeon, Chang Soo; Kim, Hyo Soo [Chungju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul; Eun, Hui Kwang [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    this is the first final report, and it includes the analysis of PSR regulation status for the operating NPP of foreign countries and thus established scope and method of Korean PSR. The detailed requirements of aging management, as one of the most important factors, is planned to be dealt in the second final report, The result of study so far can be summarized as below, The necessity and feasibility of domestic PSR application is confirmed through the investigation, comparison and review of PSR implementation and regulation status in foreign countries, And, detailed analysis of vaseline guidelines of IAEA performed to establish a skeleton of desirable safety review guideline for Korean NPP. Our own objectives, scope and strategy of review for PWR are roughly set up form factor by factor analysis of PSR implementation experience in foreign countries and background of IAEA guidelines. The essential elements of review for each PSR safety factors are classified and proposed. For efficient review of proposed safety factors and elements, three different option of framework for PSR guidelines are proposed and compared. Through analysis of strength safety factors and elements, three different options of framework for PSR guidelines are proposed and compared. Through analysis of strength and weakness of the three optional frameworks proposed for Korean PSR guideline, the third one is recommended as the best for both owner and regulator. By maintaining the current framework of SAR at maximum and, at the same time, referring the basic concept of IAEA PSR guide, the detailed contents and its review elements are chosen. The standards on the aging was proposed preliminarily for the application of aging evaluation in PSR.

  20. Motor life management at Gentilly 2 nuclear power plant

    International Nuclear Information System (INIS)

    Lazic, L.; Renaud, P.; Marcotte, P.

    2002-01-01

    Hydro Quebec's Gentilly 2 CANDU Nuclear Power Plant (NPP) located on the St. Lawrence River about 150 kms NE of Montreal Quebec Canada, is completing its second full decade of commercial operation. Since the original design life of 30 years is fast approaching, Hydro Quebec (HQ) is positioning itself proactively, to ensure plant operation for the original design life as well implementing a plant life management program to achieve a plant life extension to 50 years. All components in a nuclear plant are affected by ageing during the plant service life. This affects the availability, reliability, and safety of the plant operation and could affect the plant service life. However, if a life management program (LMP) is implemented; the ageing mechanisms can be understood and monitored, and their effects can be controlled and even mitigated. Among other vital equipment in the plant, the station motors are being examined to determine what has to be done to ensure that the motors do not contribute negatively to the plant operating plan. Gentilly 2 NPP has almost 900 motors of various configurations. Their size ranges from 0.1 HP to 9000 HP. A distribution of quantity at different horsepower levels is given. This paper will describe the plant's motor history, method of operation, and proposed future changes required to ensure effective life management of the motors. Up to the present time, Gentilly 2 NPP staff has had very good experience with plant motor operation and reliability. Nevertheless, indications from other industry motor experiences indicate that this favourable trend is unlikely to continue. A plant motor life management strategy as outlined in this paper, based on condition based maintenance in combination with traditional types of maintenance, can help to ensure protection against unexpected plant motor problems and help to ensure achievement of motor design life and beyond. Although nothing will ever replace a thorough visual inspection for discovering

  1. Overview of the solid radioactive waste management programme for Cernavoda NPP

    International Nuclear Information System (INIS)

    Raducea, D.

    2001-01-01

    The wastes generated from nuclear power plants have a very large diversity, and can be grouped into non-radioactive and radioactive wastes. These two types are manipulated completely different ways from each other. Among radioactive wastes, solid radioactive wastes are important, because of their diversity, their method of treatment and of their volume compared to the others types. The strategy for their treatment and characterisation has a dynamic character and allows modification after the identification of new solutions at the international level, or after the production of new waste types. The Radioactive Waste Management concept for Cernavoda NPP established the general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment. The radioactive waste management programme has the following major characteristics: plant operation at all times ensures that radioactive wastes are minimised; procedures are established to ensure that radiation doses to operating staff and members of the public are in accordance with ALARA and contamination from collection, transportation and storage of wastes are eliminated; all staff is trained and qualified to carry out their responsibilities. This presentation does not address the management of spent fuel, contaminated heavy water and the disposal of the solid radioactive wastes.(author)

  2. Modeling of the fatigue damage accumulation processes in the material of NPP design units under thermomechanical unstationary effects. Estimation of spent life and forecast of residual life

    International Nuclear Information System (INIS)

    Kiriushin, A.I.; Korotkikh, Yu.G.; Gorodov, G.F.

    2002-01-01

    Full text: The estimation problems of spent life and forecast of residual life of NPP equipment design units, operated at unstationary thermal force loads are considered. These loads are, as a rule, unregular and cause rotation of main stress tensor platforms of the most loaded zones of structural elements and viscoelastic plastic deformation of material in the places of stresses concentrations. The existing engineering approaches to the damages accumulation processes calculation in the material of structural units, their advantages and disadvantages are analyzed. For the processes of fatigue damages accumulation a model is proposed, which allows to take into account the unregular pattern of deformation multiaxiality of stressed state, rotation of main platforms, non-linear summation of damages at the loading mode change. The model in based on the equations of damaged medium mechanics, including the equations of viscoplastic deformation of the material and evolutionary equations of damages accumulation. The algorithms of spent life estimation and residual life forecast of the controlled equipment and systems zones are made on the bases of the given model by the known real history of loading, which is determined by real model of NPP operation. The results of numerical experiments on the basis of given model for various processes of thermal force loads and their comparison with experimental results are presented. (author)

  3. Regulatory approach to NPP ageing in Bulgaria

    International Nuclear Information System (INIS)

    Vassilev, D.

    2000-01-01

    In this contribution summary information of Kozloduy NPP units is presented. The nuclear legislation, regulatory approach for managing safety aspects on NPP ageing, short term programme, complex programme PRG'97 ant other aspects of ageing management are discussed

  4. Two managerial grids in NPP

    International Nuclear Information System (INIS)

    Zhao Hui

    2012-01-01

    Today, the nuclear power corporation (NPC) enjoys the profit of LCEP (the low carbon economic policy). at the same time, they also enduring more and more pressure. For example, the partner competition or the NPP potential occupational risk . The efficient counterplot of risk is the self-ability cultivation. It is essential to research the NPP managerial flow. The nuclear power plant (NPP) unit is a carrier of the NPC enterprise management system, and has taken on a new look 'pull one portion then the whole moving'. The NPP has three systematical characters, the security responsibility center, the man-machine system and the input-output system. The manufacturing system and the enterprise management system are the great constituents of the NPP managerial flows. Means of systems analysis, we can find out the truth of the NPP running interface. In CHINA, there are many operating experiences near 20 years. It indicates that the NPP manufacturing system and the enterprise system are the roots of the nuclear power corporation, the core of the all NPP systems must be based on it. So the ability cultivation is the work core to NPP. It is reliably to ensure the NPP to be up against problems, for instance, the security duty, the costing control and the man-machine system running harmoniously. This paper introduces the NPP managerial flow and the present state of QNPC, also come up with a proposal to refer for the NPC development actions of collective measure, specialization, standardization, fine. (author)

  5. The management of safety within the completion of units 3. and 4. in NPP Mochovce

    International Nuclear Information System (INIS)

    Ocenas, M.

    2009-01-01

    The contribution defines the way of management of safety and protection of health and protection against the fire during completion of units 3. and 4. in NPP Mochovce. The creation of the management of safety raised from the legal and other requirements applied in the civil activities and mainly from the requirements for coordination of safety on the site. The whole system is methodically managed through the 5 basic documents so-called 'Building rules': 1) Safety-technical conditions of performance in SE, Inc. Bratislava (project MO34); 2) MO34/1/MNA-003.00-02 the elaboration of the integrated safety plan; 3) MO34/1/NA-003.00-03 risks analyse; 4) PNM3460100 Integrated safety plan for completion of Units 3.and 4 in NPP Mochovce; 5) Project of construction organization. The system itself of the management of the safety prevention must by provided by the supplier in compliance with the standard OHSAS 18 001 and ISO 14001, and in compliance with the requirement of the builder applied in the technical specification for the contract. Most of necessary related documentation of Safety plan for the site is usually part of the documentation for quality management of contractor. Therefore it is necessary to put the reference in each chapter of the Safety plan for site and the standpoint how to apply it for the particular specific situation. The coordinator is mandatory to manage the prevention for the part of safety of specified site and to coordinate the activity of suppliers during the works tie in this way, that the each contractor shall meet the safety requirements given by safety plan and also to identify and to eliminate the risks menaced in the particular work places or the suppliers each other. The builder established its own control system and for this purpose he settled the data base so-called 'The system of corrective and precautionary activities'. The system registers in its data base all discrepancies determined during the regular controls of the head workers

  6. Main directions of works on radioactive waste management at 30-km zone near the Chernobyl' NPP

    International Nuclear Information System (INIS)

    Grushinskij, B.Ya.; Komarov, V.I.; Proskuryakov, A.N.; Kham'yanov, L.N.; Khubizov, S.B.; Ignatenko, E.I.; Ryzhkova, V.N.; Luppov, V.A.; Matskevich, G.V.; Frolov, V.N.

    1989-01-01

    Main points and stages of creating an specialized enterprise for centralized reprocessing and radioactive waste disposal are considered. The enterprise is intended for collection conditioning and burial of all types of radioactive wastes, formed during liquidation of accident effect at the Chernobyl' NPP as well as forming in operation of NPP. The enterprise is also used to decontaminate equipment and constructions, for reprocessing of secondary radioactive wastes forming during decontamination process of equipment constructions, transport and work clothes

  7. MORE. Management of Requirements in NPP modernisation projects - Project report 2005

    International Nuclear Information System (INIS)

    Thunem, A.P.J.; Fredriksen, R.; Thunem, H.P.J.; Ventae, O.; Valkonen, J.; Holmberg, J.E.

    2006-04-01

    The overall objective of the project MORE is to improve the means for managing the large amounts of evolving requirements in Nordic NPP modernisation projects. In accordance to this objective, the activity will facilitate the industrial utilisation of the research results from the project TACO. On the basis of experiences in the Nordic countries, the overall aim of the TACO project has been to identify the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements. The project resulted in the development of a traceability model for handling requirements from their origins and through their final shapes. Particular emphasis for the MORE project in 2005 was put on utilising a prototype of a tool (TRACE) intended to support an adopted approach to dependable requirements engineering, suitable for modelling and handling large amounts of requirements related to all stages of the systems development process and not only those traditionally including requirements at high-level stages. (au)

  8. MORE. Management of Requirements in NPP modernisation projects - Project report 2005

    Energy Technology Data Exchange (ETDEWEB)

    Thunem, A.P.J.; Fredriksen, R.; Thunem, H.P.J. [IFE (Norway); Ventae, O.; Valkonen, J.; Holmberg, J.E. [VTT Technical Research Centre of Finland (Finland)

    2006-04-15

    The overall objective of the project MORE is to improve the means for managing the large amounts of evolving requirements in Nordic NPP modernisation projects. In accordance to this objective, the activity will facilitate the industrial utilisation of the research results from the project TACO. On the basis of experiences in the Nordic countries, the overall aim of the TACO project has been to identify the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements. The project resulted in the development of a traceability model for handling requirements from their origins and through their final shapes. Particular emphasis for the MORE project in 2005 was put on utilising a prototype of a tool (TRACE) intended to support an adopted approach to dependable requirements engineering, suitable for modelling and handling large amounts of requirements related to all stages of the systems development process and not only those traditionally including requirements at high-level stages. (au)

  9. Issues on safe radioactive waste management at ChNPP site in International Shelter Implementation Plan

    International Nuclear Information System (INIS)

    Bykov, V.; Kilochytska, T.; Gromyko, S.; Kadkin, Y.; Kondratiev, S.; Pavlenko, A.; Bogorinski, P.

    2003-01-01

    The International Shelter Implementation Plan (SIP) [1], is aimed to convert the ChNPP unit 4, destroyed by a beyond-design accident in 1986, into an environmentally safe facility by means of large-scale projects such as stabilization of the existing Sarcophagus (Shelter), construction of a New Safe Confinement (NSC), and installation of engineering and monitoring systems. This report presents some important safety issues concerning radioactive waste (RAW) management at the Shelter. One of the main problems of RAW management is to dispose of large volumes of RAW generated during ground preparation work. It is necessary that RAW be sorted carefully to separate low-active radioactive waste (LLW), which will be the majority, from high-level waste. Considering the fact that the Shelter is in the exclusion zone, the interim storage of LLW in this zone is possible, but a set of safety measures is required, e.g. prevention of dust generation or spreading of radioactivity with water. Another problem is high level RAW management. Highly radioactive fragments of the core, including fuel were ejected during the accident and are now buried under the man-made layer around the Shelter. Unanticipated disclosure of such fragments may happen during any ground preparation work as well as during clearing of premises inside the damaged buildings. Therefore, permanent radiation monitoring is required to prevent any intolerable exposure of workers. Unanticipated disclosure of high-active radioactive waste (HLW) could lead to considerable delay of any work. Since it is particularly difficult to remove HLW from those locations, which can not be easily accessed with removal equipment, such waste needs to be confined and properly shielded at in situ. Due to absence of a permanent HLW storage, an interim storage needs to be provided for in the territory of the Sarcophagus. (author)

  10. Plant life management at Loviisa

    International Nuclear Information System (INIS)

    Hytoenen, Y.; Savikoski, A.

    1998-01-01

    IVO, Power Engineering Ltd. has developed a company-wide approach to plant life management. The first stage of plant life management comprises operational and maintenance histories, design and plant inspection data using advanced computer systems. The life of the plant can be controlled by maintenance, refurbishment and inspection programs, and by varying the method of plant operation. On-line monitoring is needed, and cost control and training must be taken into account if the life of the plant is to be managed efficiently. Identifying the life-limiting factors is essential at Loviisa. It has been concentrated on the aging in the form of materials degradation due to fatigue, erosion, corrosion, radiation and thermal effects. Certain other life-limiting factors are also mentioned

  11. An assessment of the fire protection requirements throughout a NPP life related to current IAEA regulations and American, Canadian and UE regulations

    International Nuclear Information System (INIS)

    Branzeu, N.; Necula, D.; Badea, M.; Teodorescu, D.; Peteu, M.

    2006-01-01

    Statistics on fires has surprisingly shown that the frequency of fires in a nuclear power plant are as high as in the conventional industrial units. The analyses on fires occurred in a NPP need to consider both their well-known severe damages and the nuclear consequences. In 1975 a severe fire occurred in BROWNS FERRY NPP due to the ignition of the polyurethane foam used in the electric cable penetration sealings. The fire propagated to the cable channels and damaged over 1600 cables. The fire event revealed important shortcomings in the fire protection design and procedures. The fire represented a crucial event that changed fundamentally the fire protection regulation in the United States nuclear industry. The fire protection programs, standards and guides currently applied, have been developed on basis of this fire analysis and gained conclusions/experience. The purpose of the article is to be a short presentation of the fire protection requirements for all NPP life stages (i.e. design, construction, commissioning, operation and decommissioning), including the most recent issues of the standards, codes, guides and regulations in US, Canada, IAEA and some European countries. Such documentation represented the main technical support in establishing the national fire protection standard design regarding all the stages of a CANDU-6 NPP life, all the types of operational NPPs, particularly for Cernavoda NPP Unit 1 and Unit 2 (now in an advanced stage of construction). In order to satisfy the requirements provided by this documentation, as practically as possible, a list of analyses and fire protection improvement measures for Cernavoda NPP is presented. (authors)

  12. Recent development in life management of the pressurised components. National report

    International Nuclear Information System (INIS)

    Gillemot, F.

    1998-01-01

    Hungarian activities concerning NPP life management include government actions, regulatory actions, utility actions, and related research and development. Nuclear Regulatory Body and the National Committee of Atomic Energy were reorganised. New national Code of Safety was issued and the Nuclear Regulatory Committee is sponsoring a series of studies on ageing evaluation and management. NPP Paks started life management program, started several safety enhance actions, revised operation instructions according to enhanced safety requirements, extended surveillance program, built up a new training center. Research actions are concerned with study of thermal ageing, development of PTS methodology, study of welding properties of WWER-440 reactors, participation in IAEA CRP on use of Master curve, use of new IAEA PTS guide, method for crack measurements, elaboration of national database on RPV materials and management of the IAEA RPV database

  13. Design on human supervisory control of safety management for advance NPP

    International Nuclear Information System (INIS)

    Nugroho, D.H.; Soentono, S.; Taryo, T.; Wahyon, P.I.

    2006-01-01

    Full text: Full text: Characteristics of an advance NPP related with economic and safety enhancement was represented on capabilities in intelligent control and diagnostic to provide nearly autonomous operation with anticipatory maintenance. An autonomous control system should enable automatic operation while adapting to component faults and system variable upsets. It needs therefore to have many intelligent capabilities, such as modeling, analysis, self-validation, diagnosis and decision. This paper describes a human supervisory control design for nuclear reactor fault management which collaborates between human and autonomous control. The beneficial of collaboration is provided based on belief of information value evaluated from Dempster's rule of evidence. The belief of the collaboration is better compared with single usage. The collaboration was conducted in which agent will autonomously and periodically be conducting surveillance by checking the component abnormalities in the plant if anomalies occur. The anomalies were determined using fault detection module. Thereby the system will be able to conduct preventive maintenance. In the situation of accident happened, hence the system will diagnose to determine the location of component failure autonomously. A human supervisor will then determine the action of decison making based on the prediction result. The decision making will be conducted based on the 4th Sheridan's autonomous level in which the autonomous control will execute the duty autonomously when the plant is in normal condition, or in the predictable accident range. But if the unpredictable accident occurs in the plant, the supervisor will then take over the role to control the plant, and the machine will do what commanded by the supervisor. Sistematically, the system explained before was represented by Traveling Salesman Problem-based surveillance, modified ART-2 artificial neural networks-based fault detection and Bayesian Networks-based fault

  14. Application of the IS-22. Implantation of aging management programs in Cofrentes NPP; Aplicacion de la IS-22. Implantacion de los programas de gestion del envejecimiento en CN Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Zapat, J. D.; Sainero, J.

    2014-10-01

    The Safety Instruction IS-22 is mainly based on the License Renewal rule (10CFR54), unlike the 10 CFR54, the IS-22 is a continued process to be met in the current operation as well as in the long term operation period. Key elements of the aging management according to the IS-22 are the Aging Management Program (AMPs). The AMPs implementation as part of the current Plant Life Management in Cofrentes NPP provides a new approach to the plant maintenance and a solid support for the long term operation. (Author)

  15. Management of fire and industrial safety - challenges during commissioning of a NPP

    International Nuclear Information System (INIS)

    Maiti, Subhaschandra; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    Construction and commissioning period of NPP are reduced world over drastically by stringent schedule for financial and economic reasons. For meeting the schedule, commissioning of components and systems are started immediate after installation, while construction activities are continued in parallel at the same place. Parallel activities' and 'Time Constraint' have brought new challenges to 'Management of Fire and Industrial Safely' during commissioning. An innovative approach was used during such phase of commissioning of TAPP-3 and 4. This paper outlines challenges encountered during this phase and special approach and measures used to meet those challenges. This paper also outlines problems encountered during implementation of these measures and subsequent change in approach to ensure smooth and safe execution of activities. Primarily, challenges were conflicting requirements by various agencies to carryout commissioning in parallel with construction activities concurrently. Main challenges were related to fall hazard, chemical hazard, fire hazard, electrical safety, work in confined space, housekeeping problem. Moreover it was within exclusion zone of another operating plant, which added one more dimension to those challenges. Conventional Safely management approach was little short to resolve these challenges. Such challenges were envisaged; analyzed and innovative measures were arrived at. Along with conventional safely analysis like Job Safely or Hazard Analysis (JSA or JHA), Accident Analysis, Accident Trend Analysis, Fire Hazard Analysis (FHA), innovative method like 'Area-Job- Hazard Charting' and 'Ratio Analysis' were used to understand activity dependent time varying hazard scenarios. Based on this analysis, decision were taken to change various existing elements of safely management like safety organizations; standard operating procedures (SOP); emergency operating procedures (EOP); resource allocation, planning and scheduling; safely training; safely

  16. Nuclear power plant life management

    International Nuclear Information System (INIS)

    Rorive, P.; Berthe, J.; Lafaille, J.P.; Eussen, G.

    1998-01-01

    Several definitions can be given to the design life of a nuclear power plant just as they can be attributed to the design life of an industrial installation: the book-keeping life which is the duration of the provision for depreciation of the plant, the licensed life which corresponds to the duration for which the plant license has been granted and beyond which a new license should be granted by the safety authorities, the design life which corresponds to the duration specified for ageing and fatigue calculations in the design of some selected components during the plant design phase, the technical life which is the duration of effective technical operation and finally the economic life corresponding to the duration of profitable operation of the plant compared with other means of electricity production. Plant life management refers to the measures taken to cope with the combination of licensed, design, technical and economical life. They can include repairs and replacements of components which have arrived to the end of their life due to known degradation processes such as fatigue, embrittlement, corrosion, wear, erosion, thermal ageing. In all cases however, it is of great importance to plan the intervention so as to minimise the economic impact. Predictive maintenance is used together with in-service inspection programs to fulfil this goal. The paper will go over the methodologies adopted in Belgium in all aspects of electrical, mechanical and civil equipment for managing plant life. (author)

  17. Annx IV. Delayed nuclear power plant project management experience Cernavoda 2 NPP, Romania

    International Nuclear Information System (INIS)

    2008-01-01

    greater contingency due to the uncertainty of the legacy equipment inventory, the possible effect of code changes during the legacy period, and the possibility of schedule extensions. One of the critical success factors for the construction restart of Cernavoda NPP Unit 2 was the condition and assessment of existing material and equipment stored in the warehouses or installed in the field. A preservation program was implemented separately for site-installed materials and managed through the construction division. Subsequently, a refurbishment program was also implemented on identified equipment, which including checking and testing of equipment and changing materials defined as obsolete or undesirable for further use in operation of equipment. For the most part, the extent of testing of equipment is the same as for a new build project. However, some major components require additional testing which should be performed early enough in the program to take corrective action if required. A good example of this is the Main Output Transformers T01, and T02, which were manufactured 20 years ago by Electroputere in Romania. These transformers have been preserved on site and recently refurbished. The Cernavoda 2 Project provided many opportunities to better define the correct approach to a successful completion of a delayed project. Most significant is the need to have a full assessment and definition of the remaining scope of work before the beginning of the Completion Contract. In conclusion, MT Project Management team adapted their work processes and procedures to suit the specificity and challenges of the Cernavoda 2 project. Interfaces with internal groups and external organizations were optimized through efficient communication processes. This allowed timely identification of issues through to the Engineering, Procurement, Construction, Planning, and Commissioning organizations. It was clearly demonstrated that teamwork, creativity and dedication to quality and productivity

  18. Current evolutionary stage of L/ILW management at operating NPP in the USA

    International Nuclear Information System (INIS)

    Miller, C.C.

    2001-01-01

    The volume of Low and Intermediate Level Waste (L/ILW) from commercial nuclear power plants (NPP) buried annually in the USA has decreased dramatically over the last two decades. The reduction in disposal volume has occurred for both dry active wastes (DAW) and wet wastes (e.g., resins, filters and sludges). Decreased disposal volume has occurred at both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). The reduction in disposal volume occurred in stages. The major driver to reduce disposal volume in the commercial sector of the USA has been increasing burial costs. The current drive to further reduce overall NPP operating costs to meet a deregulated electric market in the USA has unexpectedly resulted in further waste reductions. This paper will review the stages of waste reduction and describe the current stage for NPP in the USA. (author)

  19. Accounting for land use in life cycle assessment: The value of NPP as a proxy indicator to assess land use impacts on ecosystems.

    Science.gov (United States)

    Taelman, Sue Ellen; Schaubroeck, Thomas; De Meester, Steven; Boone, Lieselot; Dewulf, Jo

    2016-04-15

    Terrestrial land and its resources are finite, though, for economic and socio-cultural needs of humans, these natural resources are further exploited. It highlights the need to quantify the impact humans possibly have on the environment due to occupation and transformation of land. As a starting point of this paper (1(st) objective), the land use activities, which may be mainly socio-culturally or economically oriented, are identified in addition to the natural land-based processes and stocks and funds that can be altered due to land use. To quantify the possible impact anthropogenic land use can have on the natural environment, linked to a certain product or service, life cycle assessment (LCA) is a tool commonly used. During the last decades, many indicators are developed within the LCA framework in an attempt to evaluate certain environmental impacts of land use. A second objective of this study is to briefly review these indicators and to categorize them according to whether they assess a change in the asset of natural resources for production and consumption or a disturbance of certain ecosystem processes, i.e. ecosystem health. Based on these findings, two enhanced proxy indicators are proposed (3(rd) objective). Both indicators use net primary production (NPP) loss (potential NPP in the absence of humans minus remaining NPP after land use) as a relevant proxy to primarily assess the impact of land use on ecosystem health. As there are two approaches to account for the natural and productive value of the NPP remaining after land use, namely the Human Appropriation of NPP (HANPP) and hemeroby (or naturalness) concepts, two indicators are introduced and the advantages and limitations compared to state-of-the-art NPP-based land use indicators are discussed. Exergy-based spatially differentiated characterization factors (CFs) are calculated for several types of land use (e.g., pasture land, urban land). Copyright © 2016 Elsevier B.V. All rights reserved.

  20. 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)

  1. Severe accident management at the Loviisa NPP - Application of integrated ROAAM and PSA level 2

    International Nuclear Information System (INIS)

    Siltanen, S.; Routamo, T.; Tuomisto, H.; Lundstrom, P.

    2007-01-01

    The Risk Oriented Accident Analysis Methodology (ROAAM) was developed for assessment and management of rare, high consequence hazards. The purpose of most ROAAM applications has been to solve major, isolated severe accident issues related to early containment failure such as Mark-I Liner Attack and Direct Containment Heating. In addition to ROAAM in the issue resolution context, the so called Integrated ROAAM approach can be used to provide an overall frame of safety evaluation that allows determination of whether an adequate level of safety has been achieved for a plant. Integrated ROAAM approach brings together quantifications of probabilistic elements based on statistical inference and treatment of deterministic elements based on identification of dominant physics, for severe accident phenomenology, in a well defined and clearly structured way. Fortum, as an owner of the Loviisa NPP, used the Integrated ROAAM approach when developing and implementing a comprehensive severe accident management (SAM) strategy for the Loviisa NPP. The SAM strategy is based on unique features of this VVER-440 plant with ice condenser containment and it includes hardware modifications at the plant, substantial new I and C qualified for severe accident conditions, new SAM guidelines, a SAM Handbook, revision of emergency preparedness organization, and versatile training approaches. It could be argued that the resolution of individual severe accident issues is not sufficient for assessing the overall safety of a nuclear power plant, and thus the ROAAM (in an issue resolution context) is not performing the same function as a PSA study (level 2 included). Actually the Integrated ROAAM approach takes on even a more ambitious task than the PSA, since it determines how a balance can be achieved between accident prevention and mitigation of containment-threatening physical phenomena. Thus it provides a tool for implementing a sound diverse defence-in-depth strategy at a plant. Integrated

  2. The changing of land use and land management in Ignalina NPP region

    International Nuclear Information System (INIS)

    Milius, J.; Ribokas, G.

    1998-01-01

    The investigated locality (Ignalina NPP) represents territory of NPP and Visaginas town as well as agrarian territories of three former environs Dukshtas and Rimshe (Ignalina district) and Turmantas (Zarasai district). The changes of land, started with the beginning of construction works of NPP (1974) and are still taking place, are analyzed. The data on the land fund and current data of land reform agrarian services were used. The changes of the plots of farming lands in agrarian territories were preconditioned by the same factors which operated in other territories of hilly agrarian landscape. In the drained terrains the plots of farming lands increased, whereas, in other territories re naturalization processes set in resulting in the increase of the areas covered with forests and bushes which were not used for agricultural purposes. Thus, we may assert that the impact of the NPP itself on the change of the structure of farming lands in agrarian territories was minimal. It manifested not as a permanent process but as a spontaneous fact - a mechanical allotment of a plots of land for building the NPP and town itself. The comparison of the structure of farming lands at the moment of allotment with the data of 1995 revealed that during the mentioned period the farming land were completely destroyed (1003 ha of ploughed lands, 168 ha - grasslands, 180 ha - pastures). The forest area was reduced by 625 ha. The destroyed farming lands were occupied by territories under buildings (719 ha), artificial ground cover (159 ha), and high tension current lines (over 800 ha) which are absolutely unfit neither for agriculture nor forestry. Though the NPP and Visaginas town exerted no appreciable influence on the structure of farming lands in the surrounding territories they substantially changed the territory of NPP and Visaginas. The former wooded - agrarian landscape was replaced by an untypical for these places technical - urbanized landscape. This should be taken into

  3. The challenge of the global management of plant design modifications. example of the new EJ system at Vandellos NPP

    International Nuclear Information System (INIS)

    Ortega, Fernando; Valdivia, Carlos; Fernandez Illobre, Luis; Trueba, Pedro

    2010-01-01

    One of the most challenging areas in the operation of nuclear power plants (NPP) is related to the management of plant design modifications. Plant modifications can be made to improve reliability, facilitate operation, improve safety or get better results. In any of these situations, plant modifications imply many different activities that have to be done in a coordinated manner. NUREG-0711 (Human Factors Engineering Program Review Model) shows a global approach to manage most of these activities. Although this approach is mainly focused on the design and construction of new plants, it can also be applied to plant modification management. Successful global management will require performing every activity in a specific order, taking advantage of the output coming from some tasks as input for others and finalizing every task when necessary. This will provide the best results in terms of quality, time required for implementation, safe and reliable operation and maintenance, and cost. Tecnatom is involved in most of the activities related to the operational areas and has applied a global approach to get advantages in terms of quality and cost, which is outlined in this paper. As an example of this approach, the Vandellos NPP experience is shown in this presentation. Vandellos NPP carried out an important design modification that consists of replacing an old essential service water system with a new one. This was a three-year project that implied the construction of new reservoirs, new buildings, the implementation of new equipment, and new panels in the main control room. This paper shows the way in which all of these activities were performed. (authors)

  4. 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

  5. NPP Decommissioning: the concept; state of activities

    International Nuclear Information System (INIS)

    Nemytov, S.; Zimin, V.

    2001-01-01

    The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

  6. Managing rail service life

    Directory of Open Access Journals (Sweden)

    Z. Popović

    2014-10-01

    Full Text Available The service life of rails depends especially on the operational loads and speeds on the railway lines, as well as on the rail maintenance policy. There are multiple aspects of rail maintenance optimization. The following article considers optimisation of rail maintenance activities relating to rail head surface condition in order to reduce corrective work on track geometry, as well as to minimize the overall costs for track maintenance. The objects of this research are issues and challenges related to rail and track maintenance in curves on modern conventional railway lines for mixed traffic.

  7. Managing BWR plant life extension

    International Nuclear Information System (INIS)

    Ianni, P.W.; Kiss, E.

    1985-01-01

    Recent studies have confirmed that extending the useful life of a large nuclear plant can be justified with very high cost benefit ratio. In turn, experience with large power plant systems and equipment has shown that a well-integrated and -managed plan is essential in order to achieve potential economic benefits. Consequently, General Electric's efforts have been directed at establishing a life extension plan that considers alternative options and cost-effective steps that can be taken in early life, those appropriate during middle life, and those required in late life. This paper briefly describes an approach designed to provide the plant owner a maximum of flexibility in developing a life extension plan

  8. 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

  9. Operation safety at Ignalina NPP

    International Nuclear Information System (INIS)

    Zheltobriukh, G.

    1999-01-01

    An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

  10. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Medeliene, D.

    2004-01-01

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  11. EMAS at Doel NPP

    International Nuclear Information System (INIS)

    Nolan, Peter; Thoelen, Els

    1998-01-01

    In October 1995, Doel NPP of Electrabel, Belgium opted to seek registration under the EC Eco-management and Audit Scheme (EMAS). A comprehensive environmental management system (EMS) has been introduced and implemented, encompassing all four PWRs and the supporting departments. A critical step was to seek certification from an accredited environmental auditing body against the International Standard ISO 14001. This provided the foundation for the publicly available environmental statement required by EMAS. The complications of achieving EMAS at a time when national and international standards were being re-formulated were successfully overcome and Doel NPP passed its EMAS audit in June 1997. (author)

  12. Chernobyl NPP: Completion of LRW Treatment Plant and LRW Management on Site - 12568

    Energy Technology Data Exchange (ETDEWEB)

    Fedorov, Denis; Adamovich, Dmitry [SIA ' RADON' , Moscow (Russian Federation); Klimenko, I.; Taranenko, L. [IVL Engineering, Kiev (Ukraine)

    2012-07-01

    Since a beginning of ChNPP operation, and after a tragedy in 1986, a few thousands m3 of LRW have been collected in a storage tanks. In 2004 ChNPP started the new project on creation of LRW treatment plant (LRWTP) financed from EBRD fund. But it was stopped in 2008 because of financial and contract problems. In 2010 SIA RADON jointly with Ukrainian partners has won a tender on completion of LRWTP, in particular I and C system. The purpose of LRTP is to process liquid rad-wastes from SSE 'Chernobyl NPP' site and those liquids stored in the LRWS and SLRWS tanks as well as the would-be wastes after ChNPP Power Units 1, 2 and 3 decommissioning. The LRTP design lifetime - 20 years. Currently, the LRTP is getting ready to perform the following activities: 1. retrieval of waste from tanks stored at ChNPP LWS using waste retrieval system with existing equipment involved; 2. transfer of retrieved waste into LRTP reception tanks with partial use of existing transfer pipelines; 3. laboratory chemical and radiochemical analysis of reception tanks contest to define the full spectrum of characteristics before processing, to acknowledge the necessity of preliminary processing and to select end product recipe; 4. preliminary processing of the waste to meet the requirements for further stages of the process; 5. shrinkage (concentrating) of preliminary processed waste; 6. solidification of preliminary processed waste with concrete to make a solid-state (end product) and load of concrete compound into 200-l drums; 7. curing of end product drums in LRTP curing hall; 8. radiologic monitoring of end product drums and their loading into special overpacks; 9. overpack radiological monitoring; 10. send for disposal (ICSRM Lot 3); The current technical decisions allow to control and return to ChNPP of process media and supporting systems outputs until they satisfy the following quality norms: salt content: < 100 g/l; pH: 1 - 11; anionic surface-active agent: < 25 mg/l; oil

  13. Aspects of Knowledge Management Programme Implementation into Management System of NPP Operator

    International Nuclear Information System (INIS)

    Sudakov, V.

    2016-01-01

    Full text: The paper deals with the implementation of KM tools and approaches in NPPs of Slovenské elektrárne. The case study emphasizes the importance of KM programme introduction into the existing management system of the company taking into account sustainability and successful of the programme and demonstrates some practical examples. (author

  14. 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

  15. 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.

  16. Application of the Combined Cycle LWR-Gas Turbine to PWR for NPP Life Extension Safety Upgrade and Improving Economy

    International Nuclear Information System (INIS)

    Kuznetsov, Yu. N.

    2006-01-01

    Currently, some of the most important problem for the nuclear industry are life extension, advance competitiveness and safety of aging LWR NPPs. Based on results of studies performed in the USA (Battelle Memorial Institute) and in Russia (NIKIET), a new power technology, using a combined cycle gas-turbine facility CCGT - LWR, so called TD-Cycle, can significantly help in resolution of some problems of nuclear power industry. The nuclear steam and gas topping cycle is used for re-powering a light water pressurized reactor of PWR or VVER type. An existing NPP is topped with a gas turbine facility with a heat recovery steam generator (HRSG) generating steam from waste heat. The superheated steam of high pressure (P=90-165 bar, T=500-550 C) generated in the HRSG, is expanded in a high pressure (HP) turbine for producing electricity. The HP turbine can work on one shaft with the the gas turbine or at one shaft with intermediate (IP) or low (LP) pressure parts of the main nuclear steam turbine, or with a separate electric generator. The exhausted steam from the HP turbine is injected into the steam mixer where it is mixed with the saturated steam from the NPP steam generator (SG). The mixer is intended to superheat the main nuclear steam and should be characterized by minimum losses during mixing superheated and saturated steam. Steam from the mixer superheated by 20-60 C directs to the existing IP turbine, and then, through a separator-reheater flows into the LP turbine. Feed water re-heaters of LP and HP are actually unchanged in this case. Feed water extraction to the HRSG is supplied after one of LP water heaters. This proposal is intended to re-power existing LWR NPPs. To minimize cost, the IP and LP turbines and electric generator would remain the same. The reactor thermal power and fast neutron flux to the reactor vessel would decrease by 30-50 percent of nominal values. The external peripheral row of fuel elements can be replaced with metal absorber rods to

  17. NPP safety and personnel training. XII International conference. Abstracts

    International Nuclear Information System (INIS)

    2011-01-01

    The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented [ru

  18. The influence of the Ignalina NPP on the people's life and on the development of business

    International Nuclear Information System (INIS)

    Klichius, A.

    1998-01-01

    The article summarize the results of the sociological survey, discuss the influence of the Ignalina nuclear power plant on the people's life and on the development of business in the North East of Lithuania (Ignalina, Shvenchionys, Utena, Zarasai districts and Visaginas town), reveal the discrepant part of the nuclear power plant, the problems of business development. (author)

  19. 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

  20. Analysis of NPP pipes and equipment damage in life time prolongation

    International Nuclear Information System (INIS)

    Tkachev, V.V.; Zheltukhin, K.K.

    2008-01-01

    Paper describes a procedure to calculate the probability of pipes and equipment failure taking account of both the service records of the structures under various conditions and their aging. The parameters characterizing applied loads, failures, as well as metal strength, mechanical and thermal properties serve as the arbitrary values used in the described procedure. Paper presents an example of the probability calculation of failure of the RBMK emergency feed pump recirculation pipes when their service life is prolonged [ru

  1. Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

    International Nuclear Information System (INIS)

    Cho, Hyo Sung; Woo, Tae Ho; The Cyber Univ. of Korea, Seoul

    2017-01-01

    The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

  2. Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hyo Sung [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; Woo, Tae Ho [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; The Cyber Univ. of Korea, Seoul (Korea, Republic of). Dept. of Mechanical and Control Engineering

    2017-03-15

    The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

  3. 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)

  4. 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

  5. Procedure for validating the life extension for the WWER-440 internals at NV NPP unit 3

    International Nuclear Information System (INIS)

    Filatov, V.M.; Evropin, S.V.

    2001-01-01

    The design lifetime (30 years) of the 1st generation WWER-440 reactor facilities is nearing completion in Russia. One of the major problems is to validate the life extension (LE) of the reactor internals ensuring the core arrangement and free passage of the control and protection system components during different operating modes, emergency modes included. The internals at the 1st generation units are designed so that to enable their replacement. But it requires a lot of funds and time. The work has been done to demonstrate that the internals may be further safely operated without their components being replaced provided their strength, longevity and serviceability are sufficiently validated. (author)

  6. Application of the ALARA principle to minimize the collective dose in NPP accident management within the containment

    International Nuclear Information System (INIS)

    Bogorad, V.; Slepchenko, O.; Kyrylenko, Y.

    2016-01-01

    The paper focuses on application of the ALARA principle to minimize the collective doses (both for NPP personnel and the public) related to admission of personnel to the containment for accident management activities and depending on operation of ventilation systems. Results from assessment of radiation consequences are applied to a small - break LOCA with failure of LPIS at VVER - 1000 reactors. The public doses are evaluated using up - to - date RODOS, MACCS and HotSpot software for assessment of radiation consequences. The personnel doses are evaluated with MicroShield and InterRAS codes. The time function and optimal value of the collective dose are defined. The developed approach can be applied for minimization of the collective dose for optimization of accident management strategies at NPPs

  7. MORE: Management of requirements in NPP modernisation projects. Project report 2007

    International Nuclear Information System (INIS)

    Fredriksen, R.; Katta, V.; Raspotnig, C.; Valkonen, J.

    2008-03-01

    This report documents the work and related activities of the MORE project in the period January 1 - December 31 in 2007. The focus of this report is on improvements of the former project results, to identify and apply a couple of case studies from NPP projects, and activities in order to initiate and implement the industrial take-up and utilisation of the research results in real modernisation projects. The report also provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  8. MORE: Management of requirements in NPP modernisation projects. Project report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. [Institutt for energiteknikk (IFE) (Norway); Valkonen, J. [Technical Research Centre of Finland (VTT) (Finland)

    2008-03-15

    This report documents the work and related activities of the MORE project in the period January 1 - December 31 in 2007. The focus of this report is on improvements of the former project results, to identify and apply a couple of case studies from NPP projects, and activities in order to initiate and implement the industrial take-up and utilisation of the research results in real modernisation projects. The report also provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  9. 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)

  10. Main features of the pressurized component life management related R and D activity in Hungary

    International Nuclear Information System (INIS)

    Gillemot, F.; Oszwald, F.

    1995-01-01

    During the last one and half years the following main developments related to the life-time management of the NPP units took place in Hungary: 1. National project named AGNES (Advanced General New Evaluation of Safety) finished. 2. The first results of the extended surveillance program of NPP Paks has been measured. 3. The upgraded ultrasonic testing equipment used for RPV outside testing, and nozzle testing is regularly used in refuelling periods. 4. Radiation embrittlement and thermal ageing research started on RPV materials, mainly on cladding. 5. Participation in the development of the IAEA RPV ageing database. 6. Participation in IAEA pilot studies on ageing. 7. Operation of the Budapest Research Reactor, and building a new high capacity helium cooled irradiation rig. 8. Nondestructive evaluation of material ageing of a steam generator vessels. 9. A life-time calculation of Paks RPV-s. This report is a short survey of these developments. 19 refs, 4 figs

  11. Management of operators' competence and change of generation at NPP; Osaamisen hallinta ydinvoimalaitoksessa operaattoreiden sukupolvenvaihdostilanteessa

    Energy Technology Data Exchange (ETDEWEB)

    Nuutinen, M.; Reiman, T.; Oedewald, P. [VTT Industrial Systems, Espoo (Finland)

    2003-05-01

    The change of personnel generation is an important challenge faced in the nuclear power production. This study focused on the competence management and the change of the operators' generation in a Finnish nuclear power plant (NPP). The competence management was examined in two different ways. First, it was studied from a knowledge management point of view, and secondly, from a learning in work point of view. The first aim of the study was clarify mechanisms and factors, which were assumed to affect the development of the operators' expertise. The considered mechanisms were emotional and cultural control of behavior. The second aim of the study was to develop a general model for analyzing operators' possibilities to learning in work. In addition, this study discussed the applicability of two current learning theories for the development of practical training. A result of the study was the model of learning process, which defines factors and mechanisms interacting in the development of operator trainees into skilful operators in high reliability organizations. The central mechanisms were earning the trust of social group and constructing self-confidence. Based on the results of the study there is a challenge to develop common tools and practices for the trainees' goal-oriented, question-directed and gradually deepening learning and the legitimate participation in the social group in NPP. The study also produced new information of the operators' core task. A demand of the core task is developing and maintaining the competence in a daily work. (orig.)

  12. Failed (leaking) spent fuel management and storage in the Paks NPP

    International Nuclear Information System (INIS)

    Burjan, T.

    2011-01-01

    At the cycle 22, unit 4, Paks NPP the fissile contents raised irregularly in the water of the primary circuit. At the end of the cycle sipping tests were performed for the entire core to find out the leaking fuel assembly primarily responsible for this phenomenon. The identified leaking assembly temporarily was placed in the Spent Fuel Relaxing Pool. For measuring environmental impact of leaking assemblies an investigation program was developed and implemented. The assessment covered the following: effects of the leaking fuel on the water of relaxing pool and on the gaseous emissions in case open storage; in case when the leaking cassette is in a special hermetical storage case, how much gas is collected in the locked case and what is its composition; how to change the measured sipping test signal depending on relaxing time of leaking fuel cassettes. Based on the evaluation of the investigation program results the NPP modified the operational instructions for the treatment and storage of failed fuel assemblies. (author)

  13. Knowledge Management Learned from Decommissioning and Environmental Remediation after an Unexpected Radiological Contamination Occurred at Fukushima Dai-ichi NPP Accident

    International Nuclear Information System (INIS)

    Inoue, T.

    2016-01-01

    Full text: The Fukushima Dai-ichi Nuclear Power Plant (NPP) Accident resulted in severe damage of cores in units 1 to 3, and subsequently entailed not only contamination of facility but also widely-spread radiological contamination in environment due to the release of radioactive nuclides. Decommissioning activities will require at least 30–40 years with various stages of operation, such as contaminated water treatment, decontamination of reactor buildings, retrieval of spent fuel (SF) from SF pools, inspection of primary containment vessel (PCV) and reactor pressure vessel (RPV), and retrieval and further management of damaged fuel and melted debris. Especially, a water injection for core cooling is a pressing issue to stabilize the melted debris, which leads to produce a large amount of contaminated water. Environmental remediation is a crucial issue to return a normal life for local residents. On-site cleaning and off-site remediation produce various kinds and enormous amount of contaminated material with low to high radioactivity. Knowledge management of on-site and off-site issues over generation are critical to achieve the cleaning and remediation requiring a couple of decades. In addition, knowledge obtained through a long term-operation should be shared globally. (author

  14. 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

  15. Management of the used ion-exchangers contaminated with C-14 generated by NPP Cernavoda

    International Nuclear Information System (INIS)

    Boteanu, O.; Valeca, M.; Arsene, C.

    2016-01-01

    For the conditioning of ion-exchangers generated from operation of Cernavoda NPP Unit 1, techniques of direct immobilization in cement, bitumen and organic polymers have been experimented. The selected process for conditioning of spent resins is the bituminization. The bituminization process consists of the incorporation in bitumen of the spent resin, at temperatures between 110 and 1200C, and the solidification of the mixture by cooling. The percentage of incorporated spent resin in bitumen is ranged from 40 to 50% dry resin. The advantages of bituminization are: the bitumen is insoluble in water, the bituminization installation is simple, the matrix is not cost expensive, the temperature process is low, bitumen is compatible with wastes having various compositions, and the volume of the final product is smaller. The main disadvantage is that bitumen is combustible, although not easily flammable, and, at high temperature, interaction between bitumen matrix and chemical components, might occur. (authors)

  16. Fuel utilization experience in Bohunice NPP and regulatory requirements for implementation of progressive fuel management strategies

    Energy Technology Data Exchange (ETDEWEB)

    Patenyi, V [Nuclear Regulatory Authority, Bratislava (Slovakia); Darilek, P; Majercik, J [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    1994-12-31

    The experience gained in fuel utilization and the basic requirements for fuel licensing in the Slovak NPPs is described. The original project of WWER-440 reactors supposes 3-year fuel cycle with cycle length of about 320 full power days (FPD). Since 1984 it was reduced to 290 FPD. Based on the experience of other countries, a 4-year fuel cycle utilization started in 1987. It is illustrated with data from the Bohunice NPP units. Among 504 fuel assemblies left for the fourth burnup cycle no leakage was observed. The mean burnup achieved in the different units varied from 33.1 to 38.5 Mwd/kg U. The new fuel assemblies used are different from the recent ones in construction, thermohydraulics, water-uranium ratio, enrichment and material design. To meet the safety criteria, regulatory requirements for exploitation of new fuel in WWER-440 were formulated by the Nuclear Regulatory Authority of Slovak Republic. 1 tab., 5 refs.

  17. Plant Betterment as Anticipated Measure For Plant Life Management

    International Nuclear Information System (INIS)

    Louvat, J. P.

    1991-01-01

    A lot of modifications have been made since critically on each of the 28 standardized 900 MW class PWR units in France. Most of this technical upgrading was accomplished to facilitate operation, improve availability, or bring the unit design in line with evolving regulatory requirements, but a substantial part of the modifications was dedicated to Plant Life Management. As part of the program launched by EDF for plant life management, this paper introduces the Frustum's contribution for plant betterment and enhancement of reactor operation concurrently to ensure or extend plant service life. The solutions contemplated in this field are provided to reduce the frequency of unexpected reactor trip occurrences, to mitigate their negative effects or to smooth off the reactor operation and thus the magnitude of associated transients. The lifetime evaluation of NPP is basically an economical exercise, which tries to determine how long the operation of the plant will remain competitive, taking into account the long term perspective maintenance costs. There cannot be any conflict between lifetime and safety considerations, based upon the pituitary requisite that the safety requirement must be met at any time of the operation. Plant life management needs a consistent approach that can not be improvised on a case by case basis. Instead, it must be kept in mind from the very beginning of unit operation. This is the sense of the backfitting and technical upgrading carried out in France for the PWRs of the 900 MW class. It is thanks to this necessary anticipation that plant life will be actually managed, giving benefit both from the standpoint of availability and from that of the service lives of sensitive components. Substantial savings will thus be obtained

  18. Plant life management (PLIM) in Swiss nuclear power plants

    International Nuclear Information System (INIS)

    Stejskal, Jan; Steudler, Daniel; Thoma, Kurt; Fuchs, Reinhard

    2002-01-01

    Full text: The Swiss Utility Working group for ageing Management (AM) presented their programme for the first time at the PLIM/PLEX 93. In the meantime the key guideline documents have been prepared and the most so called S teckbrief - files for Safety Class 1 (SC1) are issued. The 'Steckbrief' file is a summary of the component history and includes the results of the Reviews performed and measures taken or planned to counteract ageing mechanisms. The scope of these activities does not only serve the important aspect of reliable plant service but also facilitates component and plant life extension feasibility. The older plants have been operated now for up to 30 years, so PLEX will become a more important topic for Swiss NPP. It is very encouraging, that there is an official memorandum of the Swiss authority with the clear statement, that they could not identify any technical reason, why the older plants should not extend their design life of 40 years for at least 10 and the younger for 20 years. The result of this is that a well established Ageing Management Programme (AMP) provide a good basis for Plant Life Extension (PLEX), e.g. the Swiss AMP has to be seen as a PLIM. (author)

  19. Belene NPP

    International Nuclear Information System (INIS)

    Tsvetanov, P.

    1990-01-01

    The book presents the main results of the studies of the Bulgarian Academy of Sciences (BAS) on the construction of a new nuclear power plant at Belene on the Danube river. The programme of the studies comprises five areas: the socio-economic and energy development and the necessity of the commissioning; a technical project and design level of the equipment (safety, radioactivity control, waste disposal and economic efficiency of the power plant); the seismic properties of the construction site; the corresponding risk and design features of the plant; the ecological impacts of the NPP and public opinion. The studies in the different areas have been carried out by independent teams, fully responsible for the formulated topical conclusions. The general opinion of the BAS voiced in the book is that the construction of Belene NPP is not sufficiently substantiated and is considered unacceptable. 94 refs., 53 fig., 56 tabs. (R.Ts.)

  20. Improved Nuclear Power Plant maintenance. Application to Cofrentes NPP

    International Nuclear Information System (INIS)

    Serradell, V.

    2002-01-01

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

  1. Computerization of effluent management and external dose calculation using the 'ODCM' methodology applied to Almaraz-NPP

    International Nuclear Information System (INIS)

    Garcia Gutierrez, M.E.; Sustacha Duo, D.

    1993-01-01

    The ODCM (Offsite Dose Calculation Manual), the official operational document for all nuclear power plants develops the details for the technical specifications for discharges and governs their practical application. The use of ODCM methodology for managing and controlling data associated with radioactive discharges, as well as the subsequent processing of this data to assess the radiological impact, requires and generates a large volume of data, which demands the frequent application of laborious and complex calculation processes, making computerization necessary. The computer application created for Almaraz NPP has the capacity to store and manage data on all discharges, evaluate their effects, presents reports and copies the information to be sent periodically to the CSN (Spanish Nuclear Regulatory Commission) on a magnetic tape. The radiological impact of an actual or possible discharge can be evaluated at anytime and, furthermore, general or particular reports and graphs on the discharges and doses over time can be readily obtained. The application is run on a personal computer under a relational database management system. This interactive application is based on menus and windows. (author)

  2. 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)

  3. A model for severe accidents management of WWER 440 at Kozloduy NPP

    International Nuclear Information System (INIS)

    Genovski, I.; Bonev, B.; Velev, V.; Grigorov, A.; Filipov, L.

    2006-01-01

    In order to reduce the residual risk associated with hypothetical severe nuclear accidents, systems and components for filtered containment venting and H2 reduction were implemented in the Kozloduy NPP units 3 and 4. The system technologies developed have to fulfill the following main tasks: 1) Creating a new pressure barrier system to confine the activity inventory by maintaining a slight containment sub-atmospheric pressure thereby preventing any relevant unfiltered activity releases. 2) Retaining a great extend of the airborne activity in the liquid phase of the venturi scrubber unit and return these activity back into the containment. 3) Controlling the containment atmosphere H2 gas mixture to prevent fast deflagration that may jeopardize the containment integrity. To meet above mentioned requirement a system was developed, consisting of a venturi scrubber unit which comprises a high speed long venturi section, a metal fibre filter section and molecular sieve. The system is operated by a turbo blower unit supplied with electrical power from the unaffected unit. The system keeps a slight sub-atmospheric pressure (approx. 5 - 10 mbar) in the containment with the purpose to minimize the uncontrolled radioactive release from the containment to the environment. The final analysis showed that the containment performance in combination with above mentioned countermeasures could be increased significantly and the impact to the environment is minimized

  4. 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

  5. The main objectives of lifetime management of reactor unit components

    International Nuclear Information System (INIS)

    Dragunov, Y.; Kurakov, Y.

    1998-01-01

    The main objectives of the work concerned with life management of reactor components in Russian Federation are as follows: development of regulations in the field of NPP components ageing and lifetime management; investigations of ageing processes; residual life evaluation taking into account the actual state of NPP systems, real loading conditions and number of load cycles, results of in-service inspections; development and implementation of measures for maintaining/enhancing the NPP safety

  6. 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)

  7. Safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    1995-01-01

    Preparation of safety practices on assessment and management of aging of major NPP components important to safety, CRP on management of aging of concrete containment buildings, CRP on management of aging of in-containment instrumentation and control cables are outlined

  8. Modernization programme at Dukovany NPP

    International Nuclear Information System (INIS)

    Trnka, M.

    2000-01-01

    The main goal of each NPP is to produce electricity safely, economically and without influence to environment. For Dukovany NPP it means to upgrade all documentation and perform the Equipment Upgrading Programme. All these activities are time and money consuming and therefore the determination of priority of all items was necessary. In the presentation there are mentioned some important changes in documentation, results of PSA studies and reason for Equipment Upgrading Programme performance. It was selected the most important item from the list of Equipment Upgrading Programme the I and C upgrading. Management has decided that Dukovany NPP will become among the best NPPs with WWER type of reactor. It seems this decision is the best way how to extend lifetime of the NPP. (author)

  9. 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

  10. 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....

  11. Management of tritium exposures for professionally exposed workers at Cernavoda 1 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Chitu, Catalina; Simionov, Vasile [CNE-PROD Cernavoda NPP, No. 1, Medgidiei Str. Cernavoda 905200 (Romania)

    2004-07-01

    Operating experience to date of CANDU reactors has indicated that the major contributor to the internal dose of professionally exposed workers is the tritiated heavy water (DTO). CANDU reactors are both moderated and cooled by heavy water (D{sub 2}O). Tritium is produced in CANDU reactors by neutron reactions with deuterium, boron, and lithium and by ternary fission. Even small leaks from these systems can produce important contaminations with tritiated water vapours of the air in the reactor building and thus increased individual and collective internal doses. Professionally exposed workers are subject to a combination of acute and chronic tritium exposure and HTO dosimetry program at Cernavoda NPP is based on multiple sample results. The routine urine bioassay program performs the monitoring and dosimetry functions for DTO. A specialized laboratory using Liquid Scintillation Spectrometry methods currently determines tritium activities in urine samples. The frequency of biological samples submission depends on the tritium concentration in the last sample. Dose assignments resulting from routinely measured weekly and monthly urinary levels of tritium oxide are based on the method of linear interpolation unless it is known that there has been no exposure between samples (vacation). All information about these doses is stored into a dedicated electronic database and used to make periodical reports and to ensure that the legal and administrative individual and annual limits are not exceeded. A chronic unprotected exposure to small tritium dose rate (< 50{mu}Sv/h) may lead to internal doses that exceed the intervention level. In case of acute exposure an increased daily water intake combined with a proper medical intervention could reduce the effective half time of tritium 2-3 times. (authors)

  12. Life cycle management in product development

    DEFF Research Database (Denmark)

    Skelton, Kristen; Pattis, Anna

    2013-01-01

    The integration of Life Cycle Thinking (LCT) and Life Cycle Management (LCM) into business operations poses great challenges, as it requires a wider range of environmental responsibility often extending beyond a company's immediate control. Simultaneously, it offers many opportunities...

  13. Contamination control by laundry monitor at NPP

    International Nuclear Information System (INIS)

    Singh, Vishwanath P.; Rana, P.K.; Lokeshwar Rao, S.; Managanvi, S.S.

    2010-01-01

    The operation of nuclear power reactor produces electricity as well as small quantity of radioactive waste as gaseous, liquid and solid. The waste contains radionuclides produced by fission and activation in reactor systems with wide spectrum of energy and half life. The long-lived nuclides Sr, Cs, Ba, Iodine and Co etc compared to short-lived are important in view of radiation protection. The radioactive contamination on the materials, human body or other places where it is undesirable is enormously harmful to workers at Nuclear Power Plant (NPP). The spread of radioactive from controlled areas is very complex problem for power reactor plant management

  14. 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.

  15. 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

  16. 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

  17. Operation Aspect of the Main Control Room of NPP

    International Nuclear Information System (INIS)

    Sahala M Lumbanraja

    2009-01-01

    The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

  18. Ageing Management Review of the reactor pressure vessels in Laguna Verde NPP

    International Nuclear Information System (INIS)

    Gris Cruz, Magdalena; Arganis, Carlos R.J.; Medina Almazan, A. Liliana

    2012-01-01

    In the present paper, for both units of Laguna Verde Nuclear Power Plant (LVNPP), the Ageing Management Review of the reactor pressure Vessel was carried out, including the identification of the intended functions, the materials and the environments. The evaluation of the ageing effect/mechanism and the Aging management programs currently implemented were prepared. The most important aging effects/ mechanisms are: loss of fracture toughness due to neutron irradiation embrittlement, fatigue, stress corrosion cracking (SCC), general corrosion and erosion-corrosion. The neutron irradiation embrittlement is managed by the reactor vessel materials surveillance program. The fatigue is a Time Limited Aging Analysis (TLAA), for which is necessary to calculate some fatigue usage factors. SCC is managed by, the In service inspections (ISI) program, but also by the Water Chemistry program, including, currently, On Line Noble Chem. The water chemistry program also manages General Corrosion and erosion-corrosion. The results were compared with the GALL report. (author)

  19. An integrated approach to plant life management

    International Nuclear Information System (INIS)

    Fredlund, L.

    1998-01-01

    Plant life is no longer determined by components, almost everything can be replaced. A plant life management program should aim at actions and replacements being performed at the right time. In order to manage this there is need for experience feedback systems, a plant specific risk study and safety upgrades. (author)

  20. Safety culture in Ignalina NPP, regulatory view

    Energy Technology Data Exchange (ETDEWEB)

    Maksimovas, G [VATESI (Lithuania)

    1997-09-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP.

  1. Safety culture in Ignalina NPP, regulatory view

    International Nuclear Information System (INIS)

    Maksimovas, G.

    1997-01-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP

  2. Accident beyond the design basis management with the coolant loss at the NPP with WWER

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Klyuchnikov, A.A.; Kolykhanov, V.N.

    2010-01-01

    The analysis of status and experience of development on modelling and accident beyond the design basis management, including the severe accidents, at the nuclear power plants is carried out. The methodical providing of manuals on the accident beyond the design basis management with the coolant loss on the basis of simulated critical system configurations providing the necessary safety function performance on reactor unit is proposed. The project of symptom-oriented manuals on accident beyond the design basis management with the coolant loss on the serial power unit with WWER-1000 on the basis of developed methodical providing and well known results of deepened safety analysis is presented.

  3. The significance of plant life management

    International Nuclear Information System (INIS)

    Myrddin Davies, L.

    2000-01-01

    The paper carries a definition and describes Plant life and plant life management. It also describes the procedures and defines the categorisation of components giving examples and referring to key components. Examples of 'good practice and guidance' are given for the establishment and implementation of plant life management programmes. A description is given of recent and current IAEA activities under the aegis of the International Working Group on Nuclear Power Plant Life Management (IWG-LMNPP). Some of the future activities in this field are described. (author)

  4. Irradiation Embrittlement Monitoring Programs of RPV's in the Slovak Republic NPP's

    International Nuclear Information System (INIS)

    Kupca, Ludovik

    2006-01-01

    Four types of surveillance programs were (are) realized in Slovak NPP's: 'Standard Surveillance Specimen Program' (SSSP) was finished in Jaslovske Bohunice V-2 Nuclear Power Plant (NPP) Units 3 and 4, 'Extended Surveillance Specimen Program' (ESSP), was prepared for Jaslovske Bohunice NPP V-2 with aim to validate the SSSP results, For the Mochovce NPP Unit 1 and 2 was prepared completely new surveillance program 'Modern Surveillance Specimen Program' (MSSP), based on the philosophy that the results of MSSP must be available during all NPP service life, For the Bohunice V-1 NPP was finished 'New Surveillance Specimen Program' (NSSP) coordinated by IAEA, which gave arguments for prolongation of service life these units for minimum 20 years, New Advanced Surveillance Specimen Program (ASSP) for Bohunice V-2 NPP (units 3 and 4) and Mochovce NPP (units 1, 2) is approved now. ASSP is dealing with the irradiation embrittlement of heat affected zone (HAZ) and RPV's austenitic cladding, which were not evaluated till this time in surveillance programs. SSSP started in 1979 and was finished in 1990. ESSP program started in 1995 and will be finished in 2007, was prepared with aim of: increasing of neutron fluence measurement accuracy, substantial improvement the irradiation temperature measurement, fixed orientation of samples to the centre of the reactor core, minimum differences of neutron dose for all the Charpy-V notch and COD specimens, the dose rate effect evaluation. In the year 1996 was started the new surveillance specimen program for the Mochovce RPV's unit-1 and 2, based on the fundamental postulate - to provide the irradiation embrittlement monitoring till the end of units operation. The 'New Surveillance Specimen Program' (NSSP) prepared in the year 1999 for the Bohunice V-1 NPP was finished in the year 2004. Main goal of this program was to evaluate the weld material properties degradation due to the irradiation and recovery efficiency by annealing too. The

  5. Design and implementation of component reliability database management system for NPP

    International Nuclear Information System (INIS)

    Kim, S. H.; Jung, J. K.; Choi, S. Y.; Lee, Y. H.; Han, S. H.

    1999-01-01

    KAERI is constructing the component reliability database for Korean nuclear power plant. This paper describes the development of data management tool, which runs for component reliability database. This is running under intranet environment and is used to analyze the failure mode and failure severity to compute the component failure rate. Now we are developing the additional modules to manage operation history, test history and algorithms for calculation of component failure history and reliability

  6. Development of Managing Program for Small Bore Piping Socket Weld on the Secondary System of NPP

    International Nuclear Information System (INIS)

    Lee, Dong Min; Ryu, Jong Myeong; Cho, Hong Seok; Cho, Ki Hyun; Choi, Sang Hoon; Kim, Man Hee

    2011-01-01

    Kori unit 3 had stopped operation due to leakage at steam generator drain line socket weld on June 6th, 2008. The cause of socket weld damage was known as welding defect and fatigue by vibration under normal operation. With above reason, the government has been required developing management program for small bore piping socket weld. Therefore, we have developed the socket weld management program to secure reliability and soundness of socket welds which are located at all domestic NPPs

  7. Application of the combined cycle LWR-gas turbine to PWR for NPP life extension, safety upgrade and improving economy

    International Nuclear Information System (INIS)

    Kuznetsov, Yu. N.; Lisitsa, F. D.; Smirnov, V. G.

    2000-01-01

    The unconventional technology to extend the lifetime for the NPPs now in operation and make a construction of new NPPs cheaper three-quarter erection of steam-gas toppings to the nuclear power units three-quarter is considered in the paper. Application of the steam-gas toppings permits through reducing power of aging reactors to extend lifetime of nuclear power unit, enhance its safety and at the same time to keep full load operation of NPP turbine and other balance-of-plant equipment. Proposed technology is examined for Russian VVER-440 reactor as an example and, also, as a pilot project. for Russian boiling VK-50 reactor now in operation. Heat flow sheets of the power plants, their parameters and economic problems are discussed. (author)

  8. Regulatory review of NPP Krsko Periodic Safety Review

    International Nuclear Information System (INIS)

    Lovincic, D.; Muehleisen, A.; Persic, A.

    2004-01-01

    At the request of the Slovenian Nuclear Safety Administration (SNSA), Krsko NPP prepared a Periodic Safety Review (PSR) program in January 2001. This is the first PSR of NPP Krsko, the only nuclear power plant in Slovenia. The program was reviewed by the IAEA mission in May 2001 and approved by SNSA in July 2001. The program is made in accordance with the IAEA Safety Guide 'Periodic Safety Review of Operational Nuclear Power Plants' No. 50-SG-012 and with European practice. It contains a systematic review of operation of the NPP Krsko, including the review of the changes as a result of the modernization of the facility. The main tasks of PSR are review of plant status for each safety factor, development of aging and life cycle management program, review of seismic design and PSHA analysis and update of regulatory compliance program. The prioritization process of findings and action plan are also important tasks of PSR. The basic safety factors of the PSR review are: Operational Experience, Safety Assessment and Analyses, Equipment Qualification and Ageing Management, Safety Culture, Emergency Planing, Environmental Impact and Radioactive Waste, Compliance with license requirements and Prioritization. It had been agreed that SNSA will have reviewed all PSR reports generated during the PSR process. At the end of 2003 the PSR Summary Report with selected recommendations for action plan was completed and delivered to SNSA for review. The paper presents regulatory review of NPP Krsko PSR with emphasis on the evaluation of the PSR issues ranking process. (author)

  9. Study on time management of FCD concrete pouring AP1000 NPP and its application

    International Nuclear Information System (INIS)

    Wu Jie; Yang Ming; Cong Jiuyuan

    2010-01-01

    Haiyang nuclear power plant adopts the advanced third-generation nuclear power technology, AP1000, the design concept of passive system and the methods of modularization and 'open-top' construction greatly shortens the construction period. At the same time, higher requirements are put forward to the management of construction, quality and progress control. This paper will apply the statistical process control theory and method to the time management of FCD (First Concrete Day) to Unit 1 of Haiyang AP1000 nuclear power plant, and it brings up the mathematical model of time management based on verification through modeling, data analysis, model optimization and the actual construction work. The theory and method studied in this paper can not be only applied to the FCD concrete pouring for Unit 1 of Haiyang AP1000 nuclear power plant, but also have great referential and guiding significance to the continuous concreting of the mass concrete of the follow-up similar construction. (authors)

  10. The assessment of training efficiency. A management tool in Sta. Ma de Garona NPP

    International Nuclear Information System (INIS)

    Carretero, Felipe; Sanchez Alvarez, Francisco J.; Soriano, Santiago Lucas

    2003-01-01

    Nowadays, one of the critical factors which determines the success of the companies is their adaptability to changes and the development of key competencies in a more global and competitive market. The acquisition, maintenance and updating of those competencies is a fundamental concern of the training managers. Training management implies also to answer, as accurate as possible, questions as following: Which is the quality of the training activities? Are the taught knowledge, skills and attitudes fully assimilated? Are they transferred to job position? Is it possible to correlate training effort and company results? Which is the comprehensive cost of the training programme? and finally, Is the cost reasonable according to the results?, in other words, has been the training programme efficient enough?The present paper introduces the experience in implementing an assessment system of training efficiency, in Sta. M a de Garona, as a training management tool for decision making. (author)

  11. Safety culture at Mochovce NPP

    International Nuclear Information System (INIS)

    Markus, Jozef; Feik, Karol

    2002-01-01

    This article presents the approach of Mochovce NPP to the Safety culture. It presents activities, which have been taken by Mochovce NPP up to date in the area of Safety culture enhancement with the aim of getting the term into the subconscious of each employee, and thus minimising the human factor impact on occurrence of operational events in all safety areas. The article furthermore presents the most essential information on how the elements characterising a continuous progress in reaching the planned Safety culture goals of the company management have been implemented at Mochovce NPP, as well as the management's efforts to get among the best nuclear power plant operators in this area and to be an example for the others. (author)

  12. Methodology on ageing management review for main components of a PWR NPP

    International Nuclear Information System (INIS)

    Dou Yikang; He Yinbiao; Xu Xuelian; Zhang Ming; Liang Xingyun

    2005-01-01

    According to the requirements of NNSA, for Chinese operational NPPs periodical safety review (PSR) should be carried out every 10 years. Ageing management is one of the important safety factors to be reviewed. Entrusted by Qinshan Nuclear Power Plant (QNPP), Shanghai Nuclear Engineering Research and Design Institute (SNERDI) carried out the ageing management review (AMR), as a part of the first PSR of QNPP, from 2001 to 2003. This paper summarizes the methodology of the AMR process, including screening of critical components and structures, identification of main ageing mechanisms and their indicators and the tabulated review process, etc. 15 components and structures, hereafter referred as equipment, were selected as review objects based on their significance of safety, replaceability and cost-benefit considerations. To these objects, the main ageing mechanisms and relevant ageing indicators were identified according to specific working and environmental condition, design and manufacture information, operation and maintenance history, etc. The review can be divided into two parallel parts, the review for specific equipment and the review for overall management procedures and their implementation. To typical components, such as RPV and SG, fatigue analysis based on operational transient accounting was carried out to observe the actual safety margins. Through the review, the weaknesses in ageing management and potential threats to structural integrity were identified and thus continued improvement can be made in the next period of 10 years. (authors)

  13. The Impact of Knowledge Management Practices on NPP Organizational Performance - Results of a Global Survey

    International Nuclear Information System (INIS)

    2013-06-01

    The IAEA has been asked by Member States in the 2012 General Conference Resolutions to ''further increase the level of awareness of efforts in managing nuclear knowledge'' and to continue ''to further develop and disseminate guidance and methodologies for planning, designing, and implementing nuclear knowledge management programs''. The present report summarizes the results of empirical research on the relationship between KM practices in nuclear power plants, their impact on the quality of organizational knowledge processes and the resulting effects on the organizational effectiveness of nuclear power plants. It presents the basic findings of the ''IAEA Global Nuclear Power Plant Survey: Investigating the Link Between Knowledge Management Practices and Organizational Performance'', which was conducted in 2010. This benchmark survey of KM practices in nuclear power plants was developed using a standard research methodology. The survey was made available on a global basis to all nuclear power plant sites. Senior operations managers were asked to complete the survey with input, as required, from their plant management team. Data from individual survey responses were treated as confidential, and only aggregate findings were reported. A total of 124 station ''site organizations'' participated in the survey, representing a response rate of approximately 60%. The findings provide empirical evidence of the importance of KM practices in improving the organizational effectiveness of nuclear power plants. They provide information about the current state of the industry with respect to KM practices, illustrating the direct and tangible benefits of implementing such practices and justifying continued or further efforts to ensure that KM programmes and systems are strategically planned and implemented in operating nuclear power plants. The research provides insights into the mechanisms by which KM practices have an impact on organizational effectiveness and provides a basis for

  14. Waste assaying and radiation monitoring equipment at the waste management centre of NPP Leningrad

    Directory of Open Access Journals (Sweden)

    Šokčić-Kostić Marina

    2006-01-01

    Full Text Available The waste accumulated in the past at the Nuclear Power Plant Leningrad has to be sorted and packed in an optimal way. In the area of waste treatment and management, the completeness and quality of direct monitoring are of the outmost importance for the validity of, and confidence in, both practicable waste management options and calculations of radiological impacts. Special monitoring systems are needed for this purpose. Consistent with the scale of work during the waste treatment procedures and the complexity of the plant data have to be collected from characteristic parts in various treatment stages. To combine all the information, a tracking procedure is needed during the waste treatment process to characterize the waste for interim and/or final disposal. RWE NUKEM GmbH has developed special customer-tailored systems which fulfill the specifications required by plant operation and by the authorities.

  15. Migration of the Almaraz NPP integrated operation management system to a new computer platform

    International Nuclear Information System (INIS)

    Gonzalez Crego, E.; Martin Lopez-Suevos, C.

    1996-01-01

    In all power plants, it becomes necessary, with the passage of time, to migrate the initial operation management systems to adapt them to current technologies. That is a good time to improve the inclusion of data in the corporative database and standardize the system interfaces and operation, whilst maintaining data system operability. This article contains Almaraz experience in migrating its Integrated Operation Management System to an advanced computer platform based on open systems (UNIX), communications network (ETHERNET) and database (ORACLE). To this effect, clear objectives and strict standards were established to facilitate the work. The most noteworthy results obtained are: Better quality of information and structure in the corporative database Standardised user interface in all applications. Joint migration of applications for Maintenance, Components and Spare parts, Warehouses and Purchases. Integration of new applications into the system. Introduction of the navigator, which allows movement around the database using all available applications. (Author)

  16. Risk informed approach and its application in Daya Bay NPP operation safety management

    International Nuclear Information System (INIS)

    He Yu; Zhang Jinlong; Bao Yukun

    2004-01-01

    The paper presents a systematic risk assessment approach based on probabilistic theory, and discusses its significance and application process in safety management. Risk informed approach that uses deterministic engineering principles and probabilistic methods is the appropriate approach to decision making at nuclear power plants. The paper also studies an actual case taken place at Daya Bay Nuclear Power Station using PSA approach to equipment maintenance. (authors)

  17. Decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

  18. Waste management strategy for cost effective and environmentally friendly NPP decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Per Lidar; Arne Larsson [Studsvik Nuclear AB (ndcon partner), Nykoping (Sweden); Niklas Bergh; Gunnar Hedin [Westinghouse Electric Sweden AB (ndcon partner), Vasteraas (Sweden)

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  19. Waste management strategy for cost effective and environmentally friendly NPP decommissioning

    International Nuclear Information System (INIS)

    Per Lidar; Arne Larsson; Niklas Bergh; Gunnar Hedin

    2013-01-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  20. Decommissioning Planning during the Operation of the Loviisa NPP. Planning, Management and Organizational Aspects

    Energy Technology Data Exchange (ETDEWEB)

    Tuunanen, J. P.; Eurajoki, T. E.E., [Fortum Power and Heat Ltd, Nuclear Waste Espoo (Finland)

    2013-08-15

    The first decommissioning plan for Loviisa nuclear power plant was written already in 1980's, when the plant had just started operation. The plan has been updated in 5-6 years intervals and this work still continues towards the final decommissioning plan. The decommissioning plan is based on immediate dismantling option and final disposal of decommissioning waste to the extension of the on site final disposal facility for low and intermediate level waste. The decommissioning planning has been organized as an independent project, which is realised in close cooperation with Fortum's research programme on radioactive waste management. The plant personnel are involved in the planning work through providing operating experience on contamination and activation of systems, structures and components. Later in the decommissioning phase the plant personnel will form the main part of the decommissioning organization. (author)

  1. Emergency preparedness at Ignalina NPP

    International Nuclear Information System (INIS)

    Kairys, A.

    1998-01-01

    Brief review of Ignalina NPP safety upgrading and personnel preparedness to act in cases of accidents is presented. Though great activities are performed in enhancing the plant operation safety, the Ignalina NPP management pays a lot of attention to preparedness for emergency elimination and take measures to stop emergency spreading. A new Ignalina NPP emergency preparedness plan was drawn up and became operational. It is the main document to carry out organizational, technical, medical, evacuation and other activities to protect plant personnel, population, the plant and the environment from accident consequences. Great assistance was rendered by Swedish experts in drawing this new emergency preparedness plan. The plan consists of 3 parts: general part, operative part and appendixes. The plan is applied to the Ignalina NPP personnel, Special and Fire Brigade and also to other contractor organizations personnel carrying out works at Ignalina NPP. There are set the following emergency classes: incident, emergency situation, alert, local emergency, general emergency. Separate intervention level corresponds to each emergency class. Overview of personnel training to act in case of an emergency is also presented

  2. NPP construction cost in Canada

    International Nuclear Information System (INIS)

    Gorshkov, A.L.

    1988-01-01

    The structure of capital costs during NPP construction in Canada is considered. Capital costs comprise direct costs (cost of the ground and ground rights, infrastructure, reactor equipment, turbogenerators, electrotechnical equipment, auxiliary equipment), indirect costs (construction equipment and services, engineering works and management services, insurance payments, freight, training, operating expenditures), capital per cents for the period of construction and cost of heavy water storages. It proceeds from the analysis of the construction cost structure for a NPP with the CANDU reactor of unit power of 515, 740 and 880 MW, that direct costs make up on the average 62%

  3. Qualification of NPP operations personnel

    International Nuclear Information System (INIS)

    Wang Jiao.

    1987-01-01

    Competence of personnel is one of the important problems for safety operation of nuclear power plant. This paper gives a description of some aspects, such as the administration of NPP, posts, competence of personnel, training, assessing the competence and personnel management

  4. BALTICA III. Plant condition and life management

    International Nuclear Information System (INIS)

    Hietanen, S.; Auerkari, P.

    1995-01-01

    The BALTICA III, International Conference on Plant Condition and Life Management was held on June 6 - 8, 1995 on board Silja Serenade on its cruise between Helsinki - Stockholm and at the Forest Lake Hotel Korpilampi in Espoo. BALTICA III provides forum for the transfer of technology from applied research to practise. This is the second volume of the publications, which contain the presentations given at the BALTICA III, Plant Condition and Life Management. A total of 45 articles report recent experience in plant condition and life management. The conference focuses on recent applications that have been demonstrated for the benefit of safe and economical operation of power plants. Practical approach is emphasised, including the presentations that aim to provide insight into new techniques, improvements in assessment methodologies as well as maintenance strategies. Compared to earlier occasions in the BALTICA series, a new aspect is in the applications of knowledge-based systems in the service of power plant life management. (orig.)

  5. 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)

  6. Mochovce NPP simulator

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

    Mochovce NPP simulator basic features and detailed description of its characteristics are presented with its performance, certification and application for training of NPP operators as well as the training scenario

  7. The V-1 NPP and V-2 NPP upgrading

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

  8. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    International Nuclear Information System (INIS)

    Lee, Jaiho; Song, Eunhye

    2014-01-01

    life cycle. In 2003, KHNP launched development project to make standard NPP data model on the basis of international standard. The information management framework on the basis of international standard for maintenance and repair was developed by automating P and ID, 2D-P and ID translator, data management server, and browsers. KHNP also developed a methodology for data sharing between ERP system and standard NPP data model. However, the standard data model was not applied to the entire life cycle of NPP. In 2006, KHNP started another project to construct an integrated plant ontology based on GPM data model and a plant-knowledge management system to intellectualize the plant information

  9. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho; Song, Eunhye [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    life cycle. In 2003, KHNP launched development project to make standard NPP data model on the basis of international standard. The information management framework on the basis of international standard for maintenance and repair was developed by automating P and ID, 2D-P and ID translator, data management server, and browsers. KHNP also developed a methodology for data sharing between ERP system and standard NPP data model. However, the standard data model was not applied to the entire life cycle of NPP. In 2006, KHNP started another project to construct an integrated plant ontology based on GPM data model and a plant-knowledge management system to intellectualize the plant information.

  10. Product Life Cycle - Quality Management Issues

    DEFF Research Database (Denmark)

    Alting, Leo; Majstorovic, Vidosav D.

    2004-01-01

    The strategic goal of our country is European and world integration. Within this context the management of sustainable development considered from the aspect of product’s life cycle and its quality management represents a real challenge for researchers, economy and educational system. The aim...

  11. Managing the Student for Life

    Science.gov (United States)

    Grayson, Katherine

    2010-01-01

    Ever since the first customer relationship management (CRM) tools found their way onto North American campuses around 2002, higher education administrators have cringed at the mention of the word "customer," preferring to substitute "constituent" for the more sales-driven term. Yet, with competition for qualified candidates…

  12. Modelling in life insurance a management perspective

    CERN Document Server

    Norberg, Ragnar; Planchet, Frédéric

    2016-01-01

    Focussing on life insurance and pensions, this book addresses various aspects of modelling in modern insurance: insurance liabilities; asset-liability management; securitization, hedging, and investment strategies. With contributions from internationally renowned academics in actuarial science, finance, and management science and key people in major life insurance and reinsurance companies, there is expert coverage of a wide range of topics, for example: models in life insurance and their roles in decision making; an account of the contemporary history of insurance and life insurance mathematics; choice, calibration, and evaluation of models; documentation and quality checks of data; new insurance regulations and accounting rules; cash flow projection models; economic scenario generators; model uncertainty and model risk; model-based decision-making at line management level; models and behaviour of stakeholders. With author profiles ranging from highly specialized model builders to decision makers at chief ex...

  13. Life Cycle Assessment of Slurry Management Technologies

    DEFF Research Database (Denmark)

    Wesnæs, Marianne; Wenzel, Henrik; Petersen, Bjørn Molt

    This report contains the results of Life Cycle Assessments of two slurry management technologies - acidification and decentred incineration. The LCA foundation can be used by the contributing companies for evaluating the environmental sustainability of a specific technology from a holistic Life...... Cycle perspective. Through this the companies can evaluate the environmental benefits and disadvantages of introducing a specific technology for slurry management. From a societal perspective the results can contribute to a clarification of which slurry management technologies (or combination...... of technologies) having the largest potential for reducing the overall environmental impacts....

  14. Revision 2 of the Program of NPP Krsko Decommissioning and SF and LILW Disposal

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Rapic, A.

    2010-01-01

    First joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF and LILW Disposal (DP) was completed in 2004 and formally adopted in 2005. As bilateral agreement on the NPP requires periodic revisions at least each 5 years, revision 2 of DP was started in September 2008, with the purpose to incorporate relevant developments since the 1st revision, to improve the level of details and reliability of DP, and to propose updated and more accurate cost estimates and appropriate financing models. In the first phase of the revision, new supporting studies for DP modules were prepared. Among these studies, the most demanding was the NPP Krsko specific Preliminary Decommissioning Plan (PDP), complying with the IAEA-recommended format, which included development of the NPP decommissioning inventory database. For upgrade of SF management, new and more detailed descriptions with improved cost estimates were prepared. Update of LILW disposal concept was based on new developments and projects prepared for the Slovenian repository. In the second phase of the revision, integrated DP scenarios were formulated and analyzed. They integrate NPP decommissioning together with RW and SF management/disposal into rationally inter-related sequences. Boundary conditions for this revision required: (a) that the reference scenario from the previous revision should be re-examined, with appropriate variations or new alternatives; (b) that the option of the NPP Krsko life extension should also be included; and (c) that the possibility of diverging interests of the contracting parties should also be analyzed (i.e. waste division and separate management). Finally, scenario evaluation is intended to compare the analyzed scenarios taking into account both their feasibility and estimated costs. It should provide the basis for determining future financing of DP, namely the annuities to be paid by the NPP Krsko owners into the national decommissioning funds.(author).

  15. Development of tools to manage the operational monitoring and pre-design of the NPP-LV cycle; Desarrollo de herramientas para administrar el seguimiento operativo y el pre-diseno del ciclo de la CLV

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Arredondo S, C.; Hernandez M, J. L.; Montes T, J. L.; Castillo M, A.; Ortiz S, J. J., E-mail: raul.perusquia@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    This paper presents the development of tools to facilitate the management so much, the operational monitoring of boiling water reactors (BWR) of the nuclear power plant of Laguna Verde (NPP-LV) through independent codes, and how to carry out the static calculations corresponding to process of optimized pre-design of the reference cycle next to current cycle. The progress and preliminary results obtained with the program SACal, developed at Instituto Nacional de Investigaciones Nucleares (ININ), central tool to achieve provide a management platform of the operational monitoring and pre-design of NPP-LV cycle are also described. The reached preliminary advances directed to get an Analysis center and automated design of fuel assembly cells are also presented, which together with centers or similar modules related with the fuel reloads form the key part to meet the targets set for the realization of a Management Platform of Nuclear Fuel of the NPP-LV. (Author)

  16. Development and advance of methodological basis of the determination of remaining life of reinforced concrete construction of NPP

    International Nuclear Information System (INIS)

    Matchenko, T.Yi.; Shamyis, L.B.; Pervushova, L.F.; Matchenko, O.T.

    2011-01-01

    The analysis is made of the existing methodological basis on determination of the technical state and residual service life of building constructions with categories of responsibility 1 and 2. The absent norms parameters for estimation of the state and service life of constructions are determined. Components for the decision of this problem are analyzed also.

  17. 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.

  18. Workflow in Almaraz NPP

    International Nuclear Information System (INIS)

    Gonzalez Crego, E.; Martin Lopez-Suevos, C.

    2000-01-01

    Almaraz NPP decided to incorporate Workflow into its information system in response to the need to provide exhaustive follow-up and monitoring of each phase of the different procedures it manages. Oracle's Workflow was chosen for this purpose and it was integrated with previously developed applications. The objectives to be met in the incorporation of Workflow were as follows: Strict monitoring of procedures and processes. Detection of bottlenecks in the flow of information. Notification of those affected by pending tasks. Flexible allocation of tasks to user groups. Improved monitoring of management procedures. Improved communication. Similarly, special care was taken to: Integrate workflow processes with existing control panels. Synchronize workflow with installation procedures. Ensure that the system reflects use of paper forms. At present the Corrective Maintenance Request module is being operated using Workflow and the Work Orders and Notice of Order modules are about to follow suit. (Author)

  19. Aging management and life extension

    International Nuclear Information System (INIS)

    Carey, John; Deng, Daniel; Tai, Tom M.

    2004-01-01

    Approximately 20% of the present electric generating capacity in the United States is supplied by nuclear power plants and may be retired due to initial license expiration between the years 2002 and 2030. One of the recommended actions for implementing the National Energy Strategy (Bill H.R. 776) is license renewal of currently operating nuclear power plants which DOE has estimated would save between $800 million and $1 billion in avoided new construction costs - and represent a nationwide benefit of as much as $350 billion - assuming the licenses are renewed for 20 years. The U.S. Atomic Energy Act of 1954 limits the duration of operating licenses of nuclear power plants to a maximum of 40 years but permits their renewal. And, although Title 10, Part 50.51 of Code of Federal Regulations (10CFR50.51) permitted license renewal, it provided no standards or procedures for renewal applications. License renewal requirements were established on January 13, 1992 when NRC's Final Rule (10 CFR Part 54) went into effect. The Final rule established the requirements that an applicant for license renewal must meet, the information that must be submitted to the NRC for review. This involves the performance of an Integrated Plant Assessment (IPA) which is designed to ensure that the effects of aging on important equipment will be adequately managed during the renewal term. The issuance of 10 CFR Part 54 established the regulatory and legal requirements for license renewal. The technical basis for, or viability of, license renewal has been explored by the Electric Power Research Institute (EPRI) since the late 1970s/early 1980s. The NRC as well as industry organizations such as EPRI have studied aging effects for close to two decades. The NRC's research program on plant aging degradation, which began formally in the early 1980s, is a comprehensive effort for the understanding and management of age-related degradation in safety-related systems, structures, and components (SSCs) and

  20. Implementation of Aging Management Programs in the NPP Almaraz and Trillo; Implantacion de programas de gestion de envejecimiento en C.N. Almaraz y C.N. Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, R.; Baladia, M.

    2011-07-01

    This paper is to present the methodology and management necessary to implement the aging management programs, under the Management Plan CNAT Life and media figures involved and their respective responsibilities. Furthermore, it will provide an overview of how these activities will be coordinated with the rest of the Life Management project.

  1. CANDU steam generator life management

    International Nuclear Information System (INIS)

    Tapping, R.L.; Nickerson, J.; Spekkens, P.; Maruska, C.

    1998-01-01

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermalhydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. The research and development program, as well as operating experience, has identified where improvements in operating practices and/or designs can be made in order to ensure steam generator design life at an acceptable capacity factory. (author)

  2. Strategy for decommissioning of NPP's in Germany

    International Nuclear Information System (INIS)

    Rittscher, D.; Sterner, H.

    2003-01-01

    According to German Atomic Law, two different strategies are possible, i.e. direct dismantling and safe enclosure before dismantling. Both approaches have their advantages and disadvantages. Taking into account the site and plant specific conditions the optimal strategy can be evaluated. Both approaches have been applied in Germany in the past. The German Atomic Law and the Radiation Protection Ordinance (June 2002) were adapted recently (July 2002). Additionally, the life operation time of the German NPP's was fixed in a new law (April 2002): Orderly Termination of the Commercial Production of Nuclear Electricity. These issues have made it necessary for the power utilities to review the strategies applied. As long as the final disposal in Germany is still an open issue, the construction of local Interim Stores is necessary to be able to dismantle a NPP. The basic strategies are not excluding each other and it seems clear today, that the optimal approach is a combination of these strategies, e.g. dismantling of all auxiliary systems and leaving activated parts for a longer SE period. Within this approach the advantages of both basic strategies have been integrated in one. The EWN GmbH has developed such integrated but still different approaches for the decommissioning projects of the Kernkraftwerke Greifswald (KGR) and the Arbeitsgemeinschaft Versuchsreaktor (AVR) Juelich. It can be stated that the decommissioning of a NPP does not present technical issues of concern, but is more a project management issue, although surrounded by sometime intricate political and juridical boundary conditions. A major strategy change is to be expected only when final disposal capacities are available in the future. (authors)

  3. 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

  4. A Study on the Functional Elements of Configuration Management throughout the Life Cycle of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yeom, C. S.; Cho, Y. S.

    2013-01-01

    Configuration Management (CM) is a technical and management process for maintaining consistency and traceability of any performance, functional and physical attributes of SSCs (Structures, Systems, or Components) with its requirements, design, and operational information. SSCs are the elements which make up a 'facility.' A structure is an element that provides support or enclosure. A system is a collection of components assembled to perform a specific facility function(s). A component is an active or passive item of equipment such as a pump, valve, relay, or an element of a large array such as pipe segments, elbows or reducers. For applying CM to nuclear industry, it is necessary to investigate and define the functional elements comprising CM. The elements can be used in planning and executing CM. Appropriate application of CM elements enables a user to plan and implement a CM program for SSCs of NPP. Although each element is separated, its implementation should not be performed in isolation because the CM elements should be balanced, consistent, and tracked. The degree of CM elements' application varies over the life cycle of NPP. The degree of rigor and techniques used in implementing CM is commensurate with type of NPP and its application environment as defined by the CM program requirements. For the consideration, it is necessary to make a CM STANDARD, and HANDBOOK or GUIDELINE for enabling more effective planning and implementing CM in nuclear industry

  5. Managing work life with systemic sclerosis.

    Science.gov (United States)

    Sandqvist, Gunnel; Hesselstrand, Roger; Scheja, Agneta; Håkansson, Carita

    2012-02-01

    To explore how individuals with SSc manage their work life. We conducted four focus group interviews, which included 17 patients currently working at least 20 h per week. The interviews were recorded and transcribed verbatim. The transcribed texts were analysed according to thematic content analysis. Relevant statements that generated preliminary categories were identified, after which themes and underlying subthemes were generated. The participants perceived their work role as being important, giving them a structure in everyday life and a sense of being useful members of society. Work and private life were interacting, and different adjustments had been developed to create a satisfactory balance of activities in daily life. Three themes emerged: adjustment of work situation, adapting to own resources and disclosing limitations. Reduced working hours, flexibility in the workplace concerning time schedule, room and tasks were all valuable adjustments, and were dependent on the employer, fellow workers as well as the individual's attitude towards informing employer and colleagues about his/her limitations. The participants had simplified and rationalized a lot of household chores and pointed to the importance of prioritizing meaningful activities, as well as the necessity of having time for rest and recovery. Reduced working hours, work flexibility and prioritizing meaningful activities and recovery were important factors in order to manage work life. Intervention, including problem-solving techniques and re-designing of activities in daily life, could be useful to coach individuals towards finding a balance in their work life.

  6. A study on the environmental impact analysis with life cycle assessment of O and M in NPP

    International Nuclear Information System (INIS)

    Jeong, H. S.; Kim, S. S.; Yoon, S. W.; Yang, M. H.; Kim, H. Z.

    2002-01-01

    In the modern times, characterized by mass-consumption, technologies have to evaluated not only in terms of usefulness but also in the aspects of resources exhaustion and environmental destruction. This study quantified environmental burdens from the stage of operation and maintenance in selected nuclear power plants. Four factors are evaluated, such as green house gas, hydrosphere, atmosphere and resources exhaustion for the selected PWR and PHWR with life cycle assessment(LCA)

  7. Maintenance: Changing Role in Life Cycle Management

    NARCIS (Netherlands)

    Takata, S.; Kimura, F.; van Houten, Frederikus J.A.M.; Westkamper, E.; Shpitalni, M.; Ceglarek, D.; Lee, J.

    2004-01-01

    As attention to environmental problems grows, product life cycle management is becoming a crucial issue in realizing a sustainable society. Our objective is to provide the functions necessary for such a society while minimizing material and energy consumption. From this viewpoint, we should redefine

  8. 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

  9. 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)

  10. Nuclear Fuel in Cofrentes NPP

    International Nuclear Information System (INIS)

    2002-01-01

    Fuel is an essential in the nuclear power generating business because of its direct implications on safety, generating costs and the operating conditions and limitations of the facility. Fuel management in Cofrentes NPP has been targeted at optimized operation, enhanced reliability and the search for an in-depth knowledge of the design and licensing processes that will provide Iberdrola,as the responsible operator, with access to independent control of safety aspects related to fuel and free access to manufacturing markets. (Author)

  11. Leningrad NPP and energetics of north-western Russia

    International Nuclear Information System (INIS)

    Belov, I.

    2000-01-01

    Problems of Leningrad NPP operating units modernization, their design service life finishing by year of 2010, are discussed. To assure safe operation of unit 1 investments in the amount of 30 mln. dol are necessary. Estimations suggest economic efficiency of the measures, permitting saving of 300 mln. dol worth of gas. Unfortunately, without a rise in tariff for electric power produced by NPP it seems impossible. It is recommended that substantiated tariffs are set for electric power produced by NPP starting from January, 2000. The measure is indispensable for raising investment funds intended for operating NPP modernization [ru

  12. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant, including decommissioning. (authors)

  13. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    Full text: This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant. (authors)

  14. A study on the methodology of integrated safety assessment on low and intermediate level waste (LILW) managed in temporary storage facility at NPP

    International Nuclear Information System (INIS)

    Ahn, Min Ho

    2010-02-01

    Since 1978, the KHNP has been operating 20 NPPs (16 PWRs and 4 CANDUs) and generating about 67,000 drums (200 L) of LILW (as of December 31, 2005), which have been stored in the temporary storage facility (TSF) at each NPP due to the absence of a repository for the disposal of LILW. Therefore, the period of temporary storage of LILW is so long compared to other countries. Furthermore, the details with respect to the safety analyse on the TSF have not been considered in PSAR and FSAR. Especially, the risk assessment on the TSF has scarcely been conducted as opposed to many researches on the disposal of LILW. Since 2003, however, the IAEA has been recognized on the importance of predispoal management of LILW. And then, the regulatory frame of U.S. NRC was being shifted to risk-based regulation from the deterministic approach. Therefore, most of radioactive wastes including the LILW will be managed in terms of the risk-based graded approach to future regulation system called RIR (risk informed regulation). If the radioactive wastes do not quantitatively deal with the risk-based regulation, the radiological risk on some of radioactive wastes might be overestimated or underestimated regardless of the degree of the risk. According to a consequence of these situations, the numbers of the researches on the predisposal management of LILW have been required for the preparation on new regulatory frame. In this study, the main objective of this study is to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, and to develop the integrated safety assessment code for routine operating condition and for for accident analysis on LILW managed in the TSF. In order to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, three main parameters were considered: risk-based accident scenarios, radionuclide inventory, and atmospheric dispersion factor (χ/Q). Arbitrary accidents related to LILW management in the

  15. Life Support Systems: Wastewater Processing and Water Management

    Data.gov (United States)

    National Aeronautics and Space Administration — Advanced Exploration Systems (AES) Life Support Systems project Wastewater Processing and Water Management task: Within an integrated life support system, water...

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. ASSET experience at Paks NPP

    International Nuclear Information System (INIS)

    Szabo, I.

    1997-01-01

    At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones

  1. ASSET experience at Paks NPP

    Energy Technology Data Exchange (ETDEWEB)

    Szabo, I [Operational Safety Dept., Paks NPP, Paks (Hungary)

    1997-10-01

    At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones.

  2. 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

  3. Transfer of technology construction management activities to preparation of NPP development in Indonesia (an experience of multi propose reactor 30 development at Serpong)

    International Nuclear Information System (INIS)

    Utomo

    2011-01-01

    Management and development of a nuclear installation could not be separated from the role of Construction Management in the planning stages of the project start until the commissioning. On the construction of nuclear installations MPR 30 Serpong, the role of human resource of Indonesia particularly Batan has received a lot of knowledge and experiences in the development process, the ongoing process of transfer of technology from the foreign consultants (Bechtel-USA) to Batan has been conducted at the time, and at least we are able to absorb knowledge and prove it through to completion development including commissioning activities. In the course of the time human resource challenges are required to have individual skills and expertise sufficient to handle a mega project such as nuclear power plants. Construction Management is managing a major project stages from planning, construction, procurement, installation commissioning until hand over to the owner. Based on the experience of the construction of the RSG-LP, it is expected that human resources that meet to the standards required competencies for the preparation of NPP in Indonesia are fulfilled. (author)

  4. Replacement of the computerized control system at NPP under operation

    International Nuclear Information System (INIS)

    Ermolaev, A.D.; Rakitin, I.D.

    1985-01-01

    Reasons and preconditions for replacement of the computerized control systems (CCS) at NPP under operation are consi-- dered. Problems dealing with management of CCS replacement, maintenance of a new CCS as well as NPP personnel training for the new system maintenance are discussed. A necessity of NPP personnel participation in these works in order to adapt CCS to requirements of NPP operation personnel and to initiate the training process is underlined. Replacement of CCS at NPP under operation is associated, as a rule, with obsolescence of old systems not ensuring growing requirements to NPP workability and safety. Principles observed at CCS replacement are reduced, mainly, to the following; maximum utilizatian of existing equipment, metal strUctures, cables, instruments, power supplies, ventilation system minimum of construction works and new communications; the least change of acting panels and boxes; changes in control desks should be introduced on the basis of the analysis of operator actions '

  5. Support to NPP operation and maintenance technology risk management. A concept for establishing criteria and procedure for the selection of components with respect to their importance. Stage 3.1. NPP equipment reliability management

    International Nuclear Information System (INIS)

    Stvan, F.

    2003-12-01

    A proposal was developed for a procedure using the deterministic approach to the assessment of components from the operational point of view and other aspects that cannot be directly and readily quantified and of the probabilistic approach for the assessment of component importance with respect to nuclear safety. A specific PSA study performed for the Dukovany NPP was employed. The structure of the report is as follows: (1) Aspects of component selection; (2) Introductory procedure; (3) Criteria for the selection of components with respect to their importance (4) Assessing the priority of use of the assets - effect on production, safety, and profit; (5) Assessment of the risk aspect of the assets - effect on major processes; (6) Assessment of the level of use of the assets; (7) Assessment of the structure of the assets - optimal structure for maintenance in relation to the major processes; (8) Assessment of the criteria for estimating the importance of the components; (9) Probabilistic assessment of importance from the safety aspect by means of PSA; and (10) Deterministic assessment of importance from the safety aspect. (P.A.)

  6. 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

  7. 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)

  8. Dissemination of Knowledge about NPP Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    2016-01-01

    Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

  9. Balancing preventive and corrective maintenance in Cernavoda Unit 1 NPP

    International Nuclear Information System (INIS)

    Riedel, M.; Marinescu, S.

    2000-01-01

    The paper presents a short reminder of Romania's Cernavoda NPP entering commercial operation and a brief description of the CANDU-6 project on which Unit 1 is based. The short term objectives of the maintenance management, the status of the existing maintenance programmes as well as future predictable maintenance programmes are outlined together with the Government plan to complete the balance of NPP. (author)

  10. 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)

  11. Key features of MIR.1200 (AES-2006) design and current stage of Leningrad NPP-2 construction

    International Nuclear Information System (INIS)

    Ivkov, Igor

    2010-01-01

    MIR.1200/AES-2006 is an abbreviated name of the evolving NPP design developed on the basis of the VVER-1000 Russian design with gross operation life of 480 reactor-years. This design is being implemented in four Units of Leningrad NPP-2 (LNPP-2. The AES-91/99 was used as reference during development of the AES-2006 design for LNPP-2; this design was implemented in two Units of Tianwan NPP (China). The main technical features of the MIR.1200/AES-2006 design include a double containment, four trains of active safety systems (4x100%, 4x50%), and special engineering measures for BDBA management (core catcher, H2 PARs, PHRS) based mainly on passive principles. The containment is described in detail, the main features in comparison with the reference NPP are outlined, the design layout principles are highlighted, the safety system structure and parameters are described. Attention is paid to the BDBA management system, hydrogen removal system, core catcher, and PHRS-SG and C-PHRS. (P.A.)

  12. Job life cycle management libraries for CMS workflow management projects

    International Nuclear Information System (INIS)

    Lingen, Frank van; Wilkinson, Rick; Evans, Dave; Foulkes, Stephen; Afaq, Anzar; Vaandering, Eric; Ryu, Seangchan

    2010-01-01

    Scientific analysis and simulation requires the processing and generation of millions of data samples. These tasks are often comprised of multiple smaller tasks divided over multiple (computing) sites. This paper discusses the Compact Muon Solenoid (CMS) workflow infrastructure, and specifically the Python based workflow library which is used for so called task lifecycle management. The CMS workflow infrastructure consists of three layers: high level specification of the various tasks based on input/output data sets, life cycle management of task instances derived from the high level specification and execution management. The workflow library is the result of a convergence of three CMS sub projects that respectively deal with scientific analysis, simulation and real time data aggregation from the experiment. This will reduce duplication and hence development and maintenance costs.

  13. Current status of Chernobyl NPP decommissioning

    International Nuclear Information System (INIS)

    2009-01-01

    Strategy of Chernobyl NPP decommissioning with the decommissioning license 2002-2064 is presented. The main activities at the stage of ChNPP units shutdown (2002 - 2012) are: units maintenance in safe state; decommissioning infrastructure construction; unloading of SNF – main activity determining the stage duration; systems and elements final shutdown; decommissioning life-support systems reconstruction; Comprehensive engineering and radiation survey (CERS); dismantling of the reactor facilities external equipment; removal of RAW from units; decommissioning documentation development. The decommissioning activities main results are presented

  14. Activities in the Czech Republic for reactor pressure components lifetime management

    International Nuclear Information System (INIS)

    Brumovsky, M.

    1995-01-01

    Preparation of a system of regulatory guides for life assessment of main pressure components, for inspection qualification and demonstration programmes are outlined. Lifetime management programme for NPP with WWER-440/V-213 reactors is described. Figs and tabs

  15. Reactor plant for Belene NPP completion

    International Nuclear Information System (INIS)

    Dragunov, Yu. G.; Ryzhov, S. B.; Ermakov, D. N.; Repin, A. I.

    2004-01-01

    Construction of 'Belene' NPP was started at the end of 80-ties using project U-87 with V-320 reactor plant, general designer of this plant is OKB 'Gidropress'. At the beginning of 90-ties, on completing the considerable number of deliveries and performance of civil engineering work at the site the NPP construction was suspended. Nowadays, considering the state of affairs at the site and the work performed by Bulgarian Party on preservation of the equipment delivered, the most perspective is supposed to be implementation of the following versions in completing 'Belene' NPP: for completion of Unit 1 - reactor plant VVER-1000 on the basis of V-320 reactor with the maximum use of the delivered equipment (V-320M) having the extended service life and safety improvement; for Unit 2 - advanced reactor plant VVER-1000. For the upgraded reactor plant V-230M the basic solutions and characteristics are presented, as well as the calculated justification of strength and safety analyses, design of the reactor core and fuel cycle, instrumentation and control systems, application of the 'leak-before break' in the project and implementation of safety measures. For the modernised reactor plant V-392M the main characteristics and basic changes are presented, concerning reactor pressure vessel, steam generator, reactor coolant pump set. Design of NPP with the modernized reactor plant V-320M meets the up-to-date requirements and can be licensed for completion and operation. In the design of NPP with the advanced reactor plant the basic solutions and the equipment are used that are similar to those used in standard reactor plant V-320 and new one with VVER-1000 under construction and completion in Russia, and abroad. Compliance of reactor design with the up-to-date international requirements, considering the extended service life of the main equipment, shows its rather high potential for implementation during completion of 'Belene' NPP

  16. 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

  17. 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

  18. Radioactive waste problems in the Kozloduy NPP

    International Nuclear Information System (INIS)

    Videnov, N.; Stanchev, V.

    1995-01-01

    An average volume of 1400 m 3 a year of solid radioactive waste (RAW) is generated in the Kozloduy NPP. The adopted waste processing sequence is collection, sorting and compaction with a 1000 tons force providing decrease in volume by factor of 15. A temporary storage facility at the Kozloduy NPP is licensed by ISUAE and CPPUAE. The treatment of liquid wastes is performed by Westinghouse formula and a technology using an automated solidification system. Contaminated oils are burned using an oil incinerator. A special 2-year programme for RAW management is being developed

  19. Radioactive waste problems in the Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Videnov, N; Stanchev, V [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    An average volume of 1400 m{sup 3} a year of solid radioactive waste (RAW) is generated in the Kozloduy NPP. The adopted waste processing sequence is collection, sorting and compaction with a 1000 tons force providing decrease in volume by factor of 15. A temporary storage facility at the Kozloduy NPP is licensed by ISUAE and CPPUAE. The treatment of liquid wastes is performed by Westinghouse formula and a technology using an automated solidification system. Contaminated oils are burned using an oil incinerator. A special 2-year programme for RAW management is being developed.

  20. Safety culture development at Daya Bay NPP

    International Nuclear Information System (INIS)

    Zhang Shanming

    2001-01-01

    From view on Organization Behavior theory, the concept, development and affecting factors of safety culture are introduced. The focuses are on the establishment, development and management practice for safety culture at Daya Bay NPP. A strong safety culture, also demonstrated, has contributed greatly to improving performance at Daya Bay

  1. 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)

  2. 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)

  3. Management system and organizational life cycle: A qualitative study

    OpenAIRE

    Selma Zone Fekih Ahmed

    2013-01-01

    This research deals with the importance of the components of the management system according to the phases of organizational life cycle. The goal of our research is to provide the theoretical reflection on the life cycle of the organization and to shed light on the components of the management system for each phase. The conceptual analysis shows that the management system is made up of its three components: ethics, mode of functioning and procedure of regulation. The organizational life cycle...

  4. Design, construction and commissioning of the new solid waste management and storage facilities of Ignalina NPP, Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Goehring, R.; Wenninger, K. [RWE NUKEM GmbH, Alzenau (Germany)

    2006-04-15

    The contract for the design, construction and commissioning (turn-key) of the New Solid Waste Management and Storage Facilities (SWMSF) has been awarded to RWE NUKEM GmbH. The contract was signed on the 30.11.2005. The New Solid Waste Management and Storage Facilities (SWMSF) are financed by the Ignalina Decommissioning Support Fund which is managed by European Bank for Reconstruction and Development (EBRD). The new facilities are required on the Ignalina Nuclear Power Plant (INPP) in order to support ongoing decomissioning work, including removal of waste from existing waste storage buildings. (orig.)

  5. NPP lifetime philosophy: the transatlantic difference

    International Nuclear Information System (INIS)

    Mowry, Christofer

    1998-01-01

    Fundamental institutional and cultural differences in the transatlantic nuclear power industries, and in particular those between the Nordic countries and the United States, have driven divergent plant life management strategies -strategies resulting in distinctly different plant performance. Recognition of the linkage between three key components of overall Nuclear Power Plant (NPP) performance - yearly O and M costs, safety, and effective plant lifetime -is based on different institutional perspectives. In the Nordic countries, explicit recognition of this linkage has been historically translated into an integrated approach to plant performance. American NPPs, however, have been forced to focus primarily on near term O and M performance and regulatory mandated investment. While Nordic NPPs view capital investment in plant lifetime management and modernization as necessary to avoid declining plant performance and the cost of replacement power, American NPPs exhibit reluctance for such investments due to the difficulty of justifying the associated short-term costs. The diverging histories of two NPPs of the same vintage and design, one in Sweden and one in the United States, exemplify the potential ramifications of these approaches. The Swedish plant continues to operate with excellent performance indicators, while undertaking a comprehensive and long-term modernization program. The American facility is likely to be decommissioned due to unsustainable economic performance. (author)

  6. Equipment Obsolescence Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Redmond, J.

    2014-07-01

    Nuclear Power Plant (NPP) Operators are challenged with securing reliable supply channels for safety related equipment due to equipment obsolescence. Many Original Equipment Manufacturers (OEMs) have terminated production of spare parts and product life-cycle support. The average component life cycles are much shorter than the NPP design life, which means that replacement components and parts for the original NPP systems are not available for the complete design life of the NPPs. The lack or scarcity of replacement parts adversely affects plant reliability and ultimately the profitability of the affected NPPs. This problem is further compounded when NPPs pursue license renewal and approval for plant-life extension. A reliable and predictable supply of replacement co components is necessary for NPPs to remain economically competitive and meet regulatory requirements and guidelines. Electrical and I and C components, in particular, have short product life cycles and obsolescence issues must be managed pro actively and not reactively in order to mitigate the risk to the NPP to ensure reliable and economic NPP operation. (Author)

  7. Care for the case manager: balancing your wheel of life.

    Science.gov (United States)

    Crowell, D M

    1998-01-01

    The case manager's role in our complex health care system is demanding and draining without some self-reflective attention. The Wheel of Life is a key tool for individuals to assess how well they are leading a fully balanced life. The eight aspects of a balanced life--values, self-care, work, relationships, leisure, relaxation, exercise, and centering--are explained and discussed. A self-reflective activity is presented that encourages readers to assess their current life balance. This focused clarification of personal and professional life will facilitate a more fully balanced life with rewards for case managers as individuals, and for their family, clients, and the health care organization.

  8. 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

  9. Plant level of automated control system at a NPP with RBMK reactor

    International Nuclear Information System (INIS)

    Vorob'ev, V.P.; Gorbunov, V.P.; Dmitriev, V.M.; Litvin, A.S.

    1987-01-01

    The functional structure of plant level automated control system (ACS) at NPP with RBMK-1000 reactors, its binding with the on-line control system of higher and lower levels, as well as engineering requirements to software and recommendations on composition of hardware components, are considered. NPP ACS is an organizational-engineering system consisting of computer facilities and binding aimed at solving management, economical, organizational and physical-engineering problems to control NPP more effectively. The system carries out data acquisition, preliminary processing, analysis, transmission and representation for users to accept solutions for NPP operation by operative and management personnel. The main aim of integrated NPP ACS is the control development and increase of NPP economical efficiency, the increase of electric and heat energy production, the optimization of the production distribution between units, the development of production and economic NPP control

  10. Life management/aging 1995 annual report. Revision 1

    International Nuclear Information System (INIS)

    Lindsay, D.C.

    1995-01-01

    This report provides the 1995 status of the Life Management/Aging Management Program and the activities over the current fiscal year. It relates to the Tank Waste Remediation System and to the double shell tanks

  11. Practice and experience of radiation protection and optimization (ALARA) management system in Daya Bay NPP during the past 10 years

    International Nuclear Information System (INIS)

    Chen Degan; He Yu; Yang Maochun; Gu Jingzhi

    2004-01-01

    With the practice of 10 years safe operation, Daya Bay Nuclear Power Station has established and continuously improved the management system for radiation protection and optimization (ALARA) which contains 3 basic requirements: all workers are trained, all employees are engaged in totally, and work management is implemented for the whole process. At the same time, strong efforts have been made to build the 'infrastructure' as a platform for its effective operation. This article introduces the contents and characteristics of the system and basic experiences of its effective implementation. In order to implement the management system effectively, it is necessary for NPPs to strengthen the responsibility system for radiation protection and the leading role of the radiation protection personnel, especially the role of technical support and supervision during the work with high radiation risk, emphasize the organic combination and actively mutual action with the safe operation management system of the plant, and pay great attention to the formation of safety culture and the experience feedback to ensure the continuous improvement of the management system

  12. Nuclear power plant life management and longer-term operation

    International Nuclear Information System (INIS)

    2006-01-01

    This book, prepared by NEA member country experts, contains data and analyses relevant to nuclear power plant life management and the plants' extended, longer-term operation (LTO). It addresses technical, economic and environmental aspects and provides insights into the benefits and challenges of plant life management and LTO. It will be of interest to policy makers and senior managers in the nuclear power sector and governmental bodies involved in nuclear power programme design and management. The data and information on current trends in nuclear power plant life management will be useful to researchers and analysts working in the field of nuclear energy system assessment. (authors)

  13. A reliability evaluation method for NPP safety DCS application software

    International Nuclear Information System (INIS)

    Li Yunjian; Zhang Lei; Liu Yuan

    2014-01-01

    In the field of nuclear power plant (NPP) digital i and c application, reliability evaluation for safety DCS application software is a key obstacle to be removed. In order to quantitatively evaluate reliability of NPP safety DCS application software, this paper propose a reliability evaluating method based on software development life cycle every stage's v and v defects density characteristics, by which the operating reliability level of the software can be predicted before its delivery, and helps to improve the reliability of NPP safety important software. (authors)

  14. Actual problems of management of territory and natural objects in the zone of population relocation at the Chernobyl' NPP

    International Nuclear Information System (INIS)

    Arkhipov, N.P.; Meshalkin, G.S.; Arkhipov, A.N.; Burov, N.I.; Mishenkov, N.N.; Fedotov, I.S.; Tursukova, T.A.; Kulikov, V.V.; Loginova, L.S.

    1989-01-01

    Basing on experimental data and using the research results and estimates of other authors an attempt is made to argue and formulate the principles of management for natural and agricultural lands, which can form the basis for development of the conception for use of the population relocation zone. The list of the first-priority works dealing with the problem of rational management of the zone natural objects is given. The necessity of development of the basis for organization of radioecologic nature, reserve, is shown. The scheme of organization of territory use in the population relocation zone is given. 2 figs.; 1 tab

  15. Temelin NPP commissioning experiences

    International Nuclear Information System (INIS)

    Hanus, V.

    2002-01-01

    The Building Permit for the Temelin NPP with four VVER units was issued in 1986, which is a long time ago. Since then, however, was taken a route that is very different from what anybody imagined. Described are the legislative and design changes and given is a current condition of the power plant

  16. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

  17. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

  18. Cost estimation and management over the life cycle of metallurgical ...

    African Journals Online (AJOL)

    This study investigates whether all expected costs over the life cycle of metallurgical research projects are included in initial, normal and fi nal cost estimates, and whether these costs are managed throughout a project's life cycle since there is not enough emphasis on the accurate estimation of costs and their management ...

  19. 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.''

  20. Operating Experience at NPP Krsko

    International Nuclear Information System (INIS)

    Kavsek, D.; Bach, B.

    1998-01-01

    Systematic analysis of operational experience by assessment of internal and industry events and the feedback of lessons learned is one of the essential activities in the improvement of the operational safety and reliability of the nuclear power plant. At NPP Krsko we have developed a document called ''Operating Experience Assessment Program''. Its purpose is to establish administrative guidance for the processing of operating events including on-site and industry events. Assessment of internal events is based on the following methods: Event and Causal Factor Charting, Change Analysis, Barrier Analysis, MORT (Management Oversight and Risk Tree Analysis) and Human Performance Evaluation. The operating experience group has developed a sophisticated program entitled ''Operating experience tracking system'' (OETS) in response to the need for a more efficient way of processing internal and industry operating experience information. The Operating Experience Tracking System is used to initiate and track operational events including recommended actions follow up. Six screens of the system contain diverse essential information which allows tracking of operational events and enables different kinds of browsing. OETS is a part of the NPP Krsko nuclear network system and can be easily accessed by all plant personnel. (author)

  1. Modernization of the oldest Swedish NPP

    International Nuclear Information System (INIS)

    Hagberth, Ronald

    1998-01-01

    OKG operates three BWR units of ABB design: Oskarshamn 1 with a net capacity of 440' MW, Oskarshamn 2 of 600 MW and Oskarshamn 3 of 1160 MW. Oskarshamn 1 NPP was commissioned in 1972 as the first commercial nuclear unit in Sweden. After more than twenty years of successful operation, the unit is now also the first reactor in Sweden to undergo a large safety modernization program. In the year 2000 the Oskarshamn 1 NPP will be modernized to a high level of safety standard and ready for operation for another period of at least 20 years. Experience gained can be used when modernizing other NPPs. The investment program for life extension is reasonable and shows that NPPs can be operated with an expected life span of more than 40 years at an ever-increasing safety level and still be very competitive in a deregulated market. (author)

  2. SAT for NPP personnel training in USA

    International Nuclear Information System (INIS)

    Spinney, R.

    1995-01-01

    This discussion addressed the experience with the application of SAT at USA NPPs. In particular, the transition of NPP training processes, staff composition, and reporting structure from the TMI accident to present. As well, oversight and guidance activities of the INPO and more intensive inspection by the NRC began during this period. The average NPP training staff grew to 30-40 per unit, along with a change in reporting line from plant to corporate management. With the reduction of resources occurring in the late 1980s, overall training staff size decreased, the composition changed, and reporting line reverted to plant management. The overall lessons-learned for application of the SAT consisted of the need for simplification, management involvement, and exploitation of the technology

  3. Equipment Reliability Program in NPP Krsko

    International Nuclear Information System (INIS)

    Skaler, F.; Djetelic, N.

    2006-01-01

    Operation that is safe, reliable, effective and acceptable to public is the common message in a mission statement of commercial nuclear power plants (NPPs). To fulfill these goals, nuclear industry, among other areas, has to focus on: 1 Human Performance (HU) and 2 Equipment Reliability (EQ). The performance objective of HU is as follows: The behaviors of all personnel result in safe and reliable station operation. While unwanted human behaviors in operations mostly result directly in the event, the behavior flaws either in the area of maintenance or engineering usually cause decreased equipment reliability. Unsatisfied Human performance leads even the best designed power plants into significant operating events, which can be found as well-known examples in nuclear industry. Equipment reliability is today recognized as the key to success. While the human performance at most NPPs has been improving since the start of WANO / INPO / IAEA evaluations, the open energy market has forced the nuclear plants to reduce production costs and operate more reliably and effectively. The balance between these two (opposite) goals has made equipment reliability even more important for safe, reliable and efficient production. Insisting on on-line operation by ignoring some principles of safety could nowadays in a well-developed safety culture and human performance environment exceed the cost of electricity losses. In last decade the leading USA nuclear companies put a lot of effort to improve equipment reliability primarily based on INPO Equipment Reliability Program AP-913 at their NPP stations. The Equipment Reliability Program is the key program not only for safe and reliable operation, but also for the Life Cycle Management and Aging Management on the way to the nuclear power plant life extension. The purpose of Equipment Reliability process is to identify, organize, integrate and coordinate equipment reliability activities (preventive and predictive maintenance, maintenance

  4. Integrated radioactive waste management from NPP, research reactor and back end of nuclear fuel cycle - an Indian experience

    International Nuclear Information System (INIS)

    Kumar, S.; Ali, S.S.; Chander, M.; Bansal, N.K.; Balu, K.

    2001-01-01

    India is one of the developing countries operating waste management facilities for entire nuclear fuel cycle for the last three decades. Over the years, the low and intermediate level (LIL) liquid waste streams arising from reactors and fuel reprocessing facilities have been well characterised and different processes for treatment, conditioning and disposal are being practised. LIL waste generated in nuclear facilities is treated by chemical treatment processes where majority of the activity is retained in the form of sludge. Decontamination factors ranging from 10 to 1000 are achieved depending upon the process employed and characteristics of the waste. At an inland PHWR site at Rajasthan, the LIL waste is concentrated by solar evaporation. To augment the treatment capability, a plant is being set up at Trombay to treat LIL waste based on reverse osmosis process. Alkaline waste of intermediate level activity is being treated by using indigenously developed resorcinol formaldehyde resin. Solid radioactive waste is volume reduced by compacting, baling and incineration depending on the nature of the waste. Cement matrix is employed for immobilisation of process concentrate such as chemical sludge, ash from incinerators etc. The solid waste, depending on the activity contents, is disposed in underground engineered trenches in near surface disposal facility. Bore well samples around the trench are drawn periodically to ascertain the effectiveness of the disposal system. The gaseous waste is treated at the source itself. High efficiency particulate air (HEPA) filter and impregnated activated carbon is employed to restrict the release of airborne activity to the environment. Radioactive waste discharges are kept well below the authorised limits prescribed by the regulatory authorities. This paper covers the waste management practices being adopted in India for treatment, conditioning, interim storage and disposal of low and intermediate level waste arising from the

  5. 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

  6. Family Life Education for Remarriage: Focus on Financial Management.

    Science.gov (United States)

    Lown, Jean M.; And Others

    1989-01-01

    Reviews literature on family financial management of remarried couples and describes educational workshop on financial management in remarriage. Proposes five premises based on family developmental conceptual framework. Encourages family life educators to include financial management in remarriage education programs and presents outline for…

  7. Title IV Cash Management Life Cycle Training. Participant's Guide.

    Science.gov (United States)

    Department of Education, Washington, DC.

    This participant's guide includes: "Introduction: Welcome to Cash Management Life Cycle Training"; "Module 1: Review of Cash Management Principles" (cash management overview and activity); "Module 2: Common Origination and Disbursement (COD) System Overview" (e.g., full participants and phase-in participants, COD…

  8. Modernization and safety improvement project of the NPP V-2 Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Michal, V.; Losonsky, B.; Magdolen, J.

    2000-01-01

    This contribution deals with the form, present state, and results of the Nuclear Power Plants Research Institute (the Slovak acronym is VUJE - Vyskumny Ustav Jadrovych Elektrarni) participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project. A short description of VUJE history, activity, and results is also presented as well as NPPs Jaslovske Bohunice characterization. VUJE was established in 1977 and deals with scientific and research needs of nuclear power plants, such as design, construction, commissioning and operation. The next fields of VUJE activity are, NPP reconstruction, NPP personnel training, radioactive waste management technology, and NPP decommissioning. The nuclear power plant, Jaslovske Bohunice, is situated approximately 15 km from the district town of Trnava in the southwestern region of the Slovak Republic. The construction of the first Czechoslovak NPP A-1 began on this site in 1957 .The construction of the double-unit NPP V-1 with WWER-440 (type V-230) reactor began in 1972. The first unit of NPP V-1 began operation in 1978 and the second in 1980. NPPs construction on the Bohunice site continued with NPP V-2, which has two units with WWER-440 (type V-213) reactors. Unit 1 and Unit 2 of NPP V-2 were commissioned in 1984 and 1985, respectively. Slovak electric utility Slovenske elektrarne (SE) is the owner/commissioner of NPP V-2. This NPP is responsible for more than 20% of the total electrical energy production of SE, making it an essential supporter of the Slovak economy. (authors)

  9. Framatome Contribution to Chinese NPP Development and Standardization

    International Nuclear Information System (INIS)

    Charbonneau, S.

    1996-01-01

    First discussions in 1978 between Framatome and Chinese authorities about the supply of an NPP were successfully concluded in 1986 by the signature of the supply contracts (nuclear islands, conventional islands, nuclear fuel assemblies, and project management assistance) for the Daya Bay NPP. Since then teams of engineers and technicians from Framatome and other French companies, and from relevant Chinese institutes and agencies have gotten to know each other better and have deepened their relationships

  10. 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.)

  11. 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

    1999-12-31

    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.)

  12. 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.)

  13. 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

  14. 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.

  15. 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.)

  16. Technical and economical problems of decommissioning nuclear power plants (NPP) in Russia

    International Nuclear Information System (INIS)

    Vaneev, M.

    2001-01-01

    The introduction per new century has brought to atomic Engineering many new problems. One of them, which has got a serious urgency, we now shall consider. It is a problem of decommissioning NPP in Russia. By 2014 all maintained nowadays NPP in Russian Federation will develop the regular service life. And all of them on idea should be removed from operation. But, as we understand, in today's difficult economic conditions, to it NPP the procedure of prolongation of service life will be applied, and where it is impossible by virtue of the various reasons, the procedure of translation NPP in nuclear - safe condition and in a mode of a long storage under supervision, before acceptance of the decision about a method and way of financing of a decommissioning will be applied. Possible the following variants will be: use platforms of the old NPP for construction new NPP, or using as burial place NPP. The variant of a decommissioning up to a condition 'green grass' is represented unprofitable because of its dearness. The similar decommissioning was carried out in Japan. Was removed from operation research reactor of a type WWR. The expenses for this method of a decommissioning considerably surpass expenses for a method of a burial place NPP basically because of high cost of dismantle and transportation in long-term storehouses of the 1 contour equipment. The most urgent problem of decommissioning NPP, which developed their regular service life - is financing this final stage of a exploitation cycle of the block. I shall remind, that the financing is carried out from uniform fund of decommissioning. The formation of this fund occurs by deduction 1.3 % of cost of the put electric power to the consumers by all maintained NPP of Russia. The expenditure of this fund is carried on time on some tens years. They are spent for 3 basic stages: preparation to decommissioning NPP, long endurance under supervision, dismantle and burial the NPP equipment. Nowadays on faculty NPP MPEI

  17. Recovery After Stroke: Managing Life at Home

    Science.gov (United States)

    ... be made before you go home. Staying Safe Connected and  Write out emergency phone numbers in large ... learn how to manage many sharp or hot objects that pose serious dangers in the kitchen. To ...

  18. Life Cycle Thinking, Measurement and Management for Food System Sustainability.

    Science.gov (United States)

    Pelletier, Nathan

    2015-07-07

    Food systems critically contribute to our collective sustainability outcomes. Improving food system sustainability requires life cycle thinking, measurement and management strategies. This article reviews the status quo and future prospects for bringing life cycle approaches to food system sustainability to the fore.

  19. From BIM to life cycle information management in infrastructure

    NARCIS (Netherlands)

    Nederveen, G.A. van; Wolfert, R.; Ruitenbeek, M. van de

    2014-01-01

    In principle, Building Information Modelling (BIM) should provide a basis for infrastructure information management during the whole life-cycle. In practice however, the use of BIM is normally limited to the design and construction phases. It seems that the use of BIM information in other life-cycle

  20. Managing the Work-Life Balancing Act: An Introductory Exercise.

    Science.gov (United States)

    Thompson, Cynthia A.

    2002-01-01

    In an exercise to raise business students' awareness of work-family/work-life dilemmas, students undertake small-group discussions and role playing of employees' and managers' concerns. The objective is to demonstrate that employees' and organizations' needs are not necessarily opposed and that working together to resolve work-life conflicts can…

  1. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

    Jong, A.E. de; Blom, F.J.; Leilich, J.

    2012-01-01

    Borssele NPP plans to extend its operating life with 20 years until 2034. Borssele has started the project LTO 'bewijsvoering' (LTO 'Justification') in order to meet the requirements of the Dutch regulator. The outline of the project is based on IAEA safety guide 57 'Safe Long Term Operation of Nuclear Power Plants'. This paper describes the contents and coherence of the different parts in the project and how these respond to the IAEA guidelines on LTO. The goal of the project LTO 'bewijsvoering' is to ensure that safety and safety relevant systems, structures and components continue to perform their intended functions during long term operation. The outcome of the project LTO 'bewijsvoering' will be used for a license change application and this will be submitted to the Dutch regulator KFD for approval of prolonged operation of Borssele NPP after 2013. (author)

  2. EASEWASTE-life cycle modeling capabilities for waste management technologies

    DEFF Research Database (Denmark)

    Bhander, Gurbakhash Singh; Christensen, Thomas Højlund; Hauschild, Michael Zwicky

    2010-01-01

    Background, Aims and Scope The management of municipal solid waste and the associated environmental impacts are subject of growing attention in industrialized countries. EU has recently strongly emphasized the role of LCA in its waste and resource strategies. The development of sustainable solid...... waste management systems applying a life-cycle perspective requires readily understandable tools for modelling the life cycle impacts of waste management systems. The aim of the paper is to demonstrate the structure, functionalities and LCA modelling capabilities of the PC-based life cycle oriented...... waste management model EASEWASTE, developed at the Technical University of Denmark specifically to meet the needs of the waste system developer with the objective to evaluate the environmental performance of the various elements of existing or proposed solid waste management systems. Materials...

  3. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

    Skanata, D.; Kroselj, V.; Jankovic, M.

    2007-01-01

    In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

  4. NPP long term operation in Spain - First application for license renewal

    International Nuclear Information System (INIS)

    Francia, L.; Gorrochategui, I.; Marcos, R.

    2007-01-01

    Full text: In the operation of the Spanish nuclear power plants (NPP), safety is always the prime consideration. Plant Life Management Programmes have been set up with the strategic objective to operate the NPPs as long as they are considered safe and reliable. The safety of each NPP is reviewed by the Spanish nuclear regulatory authority (CSN) under a continuous process. In addition, experience is gained from operating the plants and from exchanges with operators of similar units. Current Spanish regulatory framework for renewing NPP operating licenses requires performing a Periodic Safety Review (PSR) to be performed every 10 years and submitted when applying for a new renewal of the NPP operating license. A few years ago, CSN issued a document regarding the licensing requirements that nuclear power plants should meet in order to be granted with an operating license for long term operation (i.e, operation beyond the original plant design life, typically 40 years). Besides the traditional PSR requirements, specific requirements regarding to long term operation (LTO) include: - An Aging Management and Evaluation Program, including the identification and evaluation of Time Limited Aging Analysis (TLAA). - An updated Radiological Impact Study. - A review and assessment of regulation/standard applicability. Garona NPP (GE, BWR/3 design) operated by Spanish utility Nuclenor from 1971 has a current operating license up to 2009. A decision was made to apply for a new operating license, being Garona plant the first one in Spain to face with the new long term operation requirements. The paper will provide an overview of the methodology used in Spain to address and perform the required analyses to support the LTO application for the operating license renewal. In particular, focus will be paid on the project developed in Garona (2002-2006) whose result has been the first Spanish application for License Renewal for LTO. Also it will be reported the ongoing work necessary to

  5. Life cycle assessment of waste paper management

    DEFF Research Database (Denmark)

    Merrild, Hanna Kristina; Damgaard, Anders; Christensen, Thomas Højlund

    2008-01-01

    The significance of technical data, as well as the significance of system boundary choices, when modelling the environmental impact from recycling and incineration of waste paper has been studied by a life cycle assessment focusing oil global warming potentials. The consequence of choosing...... results. The modelling showed that recycling of paper, from a life cycle point of view, is environmentally equal or better than incineration with energy recovery only when the recycling technology is at a high environmental performance level. However, the modelling also showed that expanding the system...... a specific set of data for the reprocessing technology, the virgin paper manufacturing technology and the incineration technology, as well as the importance of the recycling rate Was Studied. Furthermore, the system was expanded to include forestry and to include fossil fuel energy substitution from saved...

  6. Dukovany NPP operation

    International Nuclear Information System (INIS)

    Vlcek, Jaroslav

    2010-01-01

    The topics discussed include: Dukovany NPP among CEZ Group power plants; International missions at the plant; Plant operation results; and Strategic goals and challenges. Historical data are presented in the graphical form, such as the unit capacity factor, unplanned capability loss factor, unplanned automatic scrams, fuel reliability, industrial safety accident rate, collective radiation exposure, WANO index, power generation data, and maximum achievable power by the end of year. Also discussed were the company culture and human resources, maintenance, power uprate, and related phenomena. (P.A.)

  7. Cernavoda NPP Knowledge Transfer

    International Nuclear Information System (INIS)

    Valache, C. M.

    2016-01-01

    Full text: The paper presents a description of the Knowledge Transfer (KT) process implemented at Cernavoda NPP, its designing and implementation. It is underlined that applying a KT approach should improve the value of existing processes of the organization through: • Identifying business, operational and safety risks due to knowledge gaps, • Transfer of knowledge from the ageing workforce to the peers and/or the organization, • Continually learning from successes and failures of individual or teams, • Convert tacit knowledge to explicit knowledge, • Improving operational and safety performance through creating both new knowledge and better access to existing knowledge. (author

  8. Supplier Relationship Management at Army Life Cycle Management Commands: Gap Analysis of Best Practices

    Science.gov (United States)

    2012-01-01

    contracts. - 76 - In step 9, maintaining momentum in supplier management , the relationship between the customer and supplier continues to develop...REPORT DATE 2012 2. REPORT TYPE 3. DATES COVERED 00-00-2012 to 00-00-2012 4. TITLE AND SUBTITLE Supplier Relationship Management at Army Life... Relationship Management at Army Life Cycle Management Commands Gap Analysis of Best Practices Nancy Y. Moore, Amy G. Cox, Clifford A. Grammich

  9. Life cycle assessment of shredder residue management

    DEFF Research Database (Denmark)

    Boldrin, Alessio; Damgaard, Anders; Brogaard, Line Kai-Sørensen

    wood waste, wood waste for recycling and district heating pipes. The LCA was conducted using the EASETECH LCA model developed by DTU Environment for the environmental assessment of waste management systems and environmental technologies. The LCA was conducted in accordance with the LCA principles...

  10. Nuclear plant life cycle management implementation guide. Final report

    International Nuclear Information System (INIS)

    Sliter, G.E.; Negin, C.A.

    1998-11-01

    Nuclear power plants, as baseload suppliers of electricity, are major corporate assets. As the nuclear industry enters its fourth decade as a major producer of clean electricity, the structure of the utility industry is undergoing a historical landmark transition from economic deregulation to a competitive, market-driven industry. An integral part of competition is to manage the operation of the key asset, the plant, in the long term, thereby enhancing its long-term profitability. Life cycle management (LCM) is a well-known technical-economic decision-making process for any large industrial facility. LCM optimizes the service life of a facility and maximizes its life-cycle asset value. LCM integrates aging management (maintaining the availability of costly-to-replace components and structures) with asset management (plant valuation and investment strategies that account for economic, performance, regulatory, and environmental uncertainties). LCM involves predicting maintenance, repair, and other capital costs for a nuclear unit far into the future, as well as planning and managing strategic issues such as waste disposal, fuel storage, decommissioning, and public acceptance. This Life Cycle Management Implementation Guide introduces the reader to the LCM concept and its benefits, describes the elements and activities associated with an LCM program (most of which already exist in all plants), gives an overview of asset and aging management, and provides key references related to life cycle management for nuclear power plants. It also summarizes the major elements of life cycle management required for license renewal or, for newer plants, keeping open the option of license renewal

  11. Chernobyl NPP decommissioning efforts - Past, Present and Future. Decommissioning Efforts on Chernobyl NPP site - Past, Present

    International Nuclear Information System (INIS)

    Kuchinskiy, V.

    2017-01-01

    Two unique large-scale projects are underway at the moment within the Chernobyl - Exclusion zone - Shelter object transformation into ecologically safe system and the decommissioning of 3 Chernobyl NPP Units. As a result of beyond design accident in 1986 the entire territory of the industrial site and facilities located on it was heavily contaminated. Priority measures were carried out at the damaged Unit under very difficult conditions to reduce the accident consequences and works to ensure nuclear and radiation safety are continuous, and the Unit four in 1986 was transformed into the Shelter object. Currently, works at the Shelter object are in progress. Under assistance of the International Community new protective construction was built above the existing Shelter object - New Safe Confinement, which will ensure the SO Safety for the long term - within up to 100 years. The second major project is the simultaneous decommissioning of Chernobyl NPP Units 1, 2 and 3. Currently existing Chernobyl NPP decommissioning Strategy has been continuously improved starting from the Concept of 1992. Over the years the following was analyzed and taken into account: the results of numerous research and development works, international experience in decommissioning, IAEA recommendations, comments and suggestions from the governmental and regulatory bodies in the fields of nuclear energy use and radioactive waste management. In 2008 the final decommissioning strategy option for Chernobyl NPP was approved, that was deferred gradual dismantling (SAFSTOR). In accordance with this strategy, decommissioning will be carried out in 3 stages (Final Shutdown and Preservation, Safe Enclosure, Dismantling). The SAFSTOR strategy stipulates: -) the preservation of the reactor, the primary circuit and the reactor compartment equipment; -) the dismantling of the equipment external in relation to the reactor; -) the safe enclosure (under the supervision); -) the gradual dismantling of the primary

  12. 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)

  13. NPP Temelin. Status of safety improvements

    International Nuclear Information System (INIS)

    1999-01-01

    The WWER-1000 Temelin NPP under construction has been subjected as other NPPs of the same type to numerous project reviews resulting in quite a number of recommendations for design changes. Results of the IAEA mission to review the resolution of WWER-1000 safety issues at Temelin NPP are cited in this paper. The main conclusions emphasize that a combination of eastern and western technology and practices led to safety improvements in comparison with the international practices. Plant managers are clearly committed to implementation of operational programs which are consistent with effective western operational safety practices. Considerable effort remains to bring planned programs to successful implementation, in particular in meeting the need to foster strong safety culture among all personnel

  14. Contribution of the Slovak University of Technology Bratislava to the Education of NPP Operation Staff in Slovakia

    International Nuclear Information System (INIS)

    Hascik, J.; Slugen, V.; Hinca, R.; Miglierini, M.

    2006-01-01

    Paper is focused on the preparation of NPP VVER -440 staff in Slovak conditions. The realisation is managed via special technical courses, seminars, workshops, and trainings on selected experimental facilities at domestic as well as international level. Post-gradual re-qualification study: Safety aspects of NPP operation is discussed in detail. Six-year experience with NPP operating staff education can be shared and recommended also at international level. Based on these courses, special training for optimal preparation of NPP supervising physicists was started in 2002. In addition to all our activities, the international course: Safety aspects of NPP operation for subcontractors was prepared and realised in 2005.(author)

  15. Prioritization of Delay Factors for NPP Construction Risk in International Project by Using AHP Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Hossen, Muhammed Mufazzal; Kang, Sunkoo; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    It is crucial for the nuclear power plant project decision makers and management personnel to identify the actual factors of construction delay and their ranking in order to take preventive actions. NPP project is complex in nature and the construction phase is one of the most key phase which is subject to many factors result from many sources. From experience, nuclear projects have faced challenges similar to other complex mega projects with additional nuclear specific issues and life time cost of nuclear reactor is concentrated upfront as capital cost, and therefore delays in construction may become intolerable in terms of both lost revenues and interest on the capital. Budget over-runs and delays on next generation new build nuclear projects in recent years clearly demonstrate that the nuclear industry continues to repeat its failed management and project control processes of the past. Similar to major infra-structure projects, actual completion times can vary substantially from initial estimates but this uncertainty is too crucial to the nuclear industry due to high levels of capital at risk, for every year a project is delayed the levelized cost of electricity increases by approximately 8-10%. causes of delay, to develop a generalized AHP model for delay factors, and to prioritize the risk in different factors in various levels of construction phase in international turnkey NPP project. This paper describes and prioritizes Nuclear Power Plant (NPP) construction schedule delay factor for turnkey international project. This study also determines the different party's importance in percentage behind the construction schedule delay of NPP which constitutes main contractor (28.4%), regulatory authority (27.3%), financial and country factor (23.5%), and utility (20.8%). Decision makers of nuclear industry can understand the significance of different factors on NPP construction phase and they can apply risk informed decision making to avoid unexpected

  16. Prioritization of Delay Factors for NPP Construction Risk in International Project by Using AHP Methodology

    International Nuclear Information System (INIS)

    Hossen, Muhammed Mufazzal; Kang, Sunkoo; Kim, Jonghyun

    2014-01-01

    It is crucial for the nuclear power plant project decision makers and management personnel to identify the actual factors of construction delay and their ranking in order to take preventive actions. NPP project is complex in nature and the construction phase is one of the most key phase which is subject to many factors result from many sources. From experience, nuclear projects have faced challenges similar to other complex mega projects with additional nuclear specific issues and life time cost of nuclear reactor is concentrated upfront as capital cost, and therefore delays in construction may become intolerable in terms of both lost revenues and interest on the capital. Budget over-runs and delays on next generation new build nuclear projects in recent years clearly demonstrate that the nuclear industry continues to repeat its failed management and project control processes of the past. Similar to major infra-structure projects, actual completion times can vary substantially from initial estimates but this uncertainty is too crucial to the nuclear industry due to high levels of capital at risk, for every year a project is delayed the levelized cost of electricity increases by approximately 8-10%. causes of delay, to develop a generalized AHP model for delay factors, and to prioritize the risk in different factors in various levels of construction phase in international turnkey NPP project. This paper describes and prioritizes Nuclear Power Plant (NPP) construction schedule delay factor for turnkey international project. This study also determines the different party's importance in percentage behind the construction schedule delay of NPP which constitutes main contractor (28.4%), regulatory authority (27.3%), financial and country factor (23.5%), and utility (20.8%). Decision makers of nuclear industry can understand the significance of different factors on NPP construction phase and they can apply risk informed decision making to avoid unexpected

  17. 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)

  18. Revision of Krsko NPP Quality Assurance Plan

    International Nuclear Information System (INIS)

    Biscan, R.; Fifnja, I.; Kavsek, D.

    2012-01-01

    International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

  19. Knowledge Mangement and Management of Working-life

    DEFF Research Database (Denmark)

    Ipsen, Christine

    2003-01-01

    Knowledge Management and the Management of Working Life Research paper – case study Oral presentation Keywords: Knowledge work, knowledge management, working life and knowledge-intensive companies. A single case study has indicated that there is a clear connection between the organizational work......, managerial style and the working environment in knowledge-intensive companies. Furthermore the study indicates that the knowledge-workers only to a limited extent use the formalised working environment–system. Instead current issues are dealt with in a more informal manner. A subsequent systematic search...... on the working conditions within the practice of Knowledge Management, and the organizing of the knowledge work. The overall objective is to analyse the possibilities for knowledge-intensive companies to integrate working environment management and ensure improved working conditions. The methodology employed...

  20. American Society for Pain Management Nursing position statement: pain management at the end of life.

    Science.gov (United States)

    Reynolds, Janice; Drew, Debra; Dunwoody, Colleen

    2013-09-01

    Pain at the end of life continues to be of great concern as it may be unrecognized or untreated. While nurses have an ethical obligation to reduce suffering at the end of life, barriers remain regarding appropriate and adequate pain management at the end of life. This position statement from the American Society for Pain Management Nursing contains recommendations for nurses, prescribers, and institutions that would improve pain management for this vulnerable population. Copyright © 2013 American Society for Pain Management Nursing. Published by Elsevier Inc. All rights reserved.

  1. 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)

  2. Managing work-life balance of working mothers

    OpenAIRE

    2014-01-01

    M.Comm. (Business Management) Changes in the corporate landscape and an increase in female participation rates in corporate workforces necessitate a better understanding of female career paths and how organisations can accommodate them better. The purpose of this study is to identify the most appropriate work-life balance benefits organisations can offer to female employees to assist them in achieving greater work-life balance. The study further aims to identify learning and development op...

  3. NPP Prevlaka - Preparation of construction

    International Nuclear Information System (INIS)

    Bojic, K.

    1984-01-01

    On the basis of study 'Optimal electricity generation structure till the year 2000' production of 3 x 500 MWe in nuclear power plants has been anticipated. Second Croatian-Slovenian NPP project will be based on the same principles the first one (NPP Krsko) was based on. Preconstruction investigation studies are performed at site Prevlaka on river Sava downstream of Zagreb. Licensing procedure has started with republic Urban countryside planning activities. Preconstruction activities are planned to be finished by the end of 1986. while the construction is expected to start during 1987. Parallel to investigation studies for NPP Prevlaka, evaluation of nuclear technology and reactor type is planned to be made. (author)

  4. The seismic reassessment Mochovce NPP

    International Nuclear Information System (INIS)

    Baumeister, P.

    2004-01-01

    The design of Mochovce NPP was based on the Novo-Voronez type WWER-440/213 reactor - twin units. Seismic characteristic of this region is characterized by very low activity. Mochovce NPP site is located on the rock soil with volcanic layer (andesit). Seismic reassessment of Mochovce NPP was done in two steps: deterministic approach up to commissioning confirmed value Horizontal Peak Ground Acceleration HPGA=0.1 g and activities after commissioning as a consequence of the IAEA mission indicate higher hazard values. (author)

  5. Technology for NPP decantate treatment realized at Kola NPP

    International Nuclear Information System (INIS)

    Stakhiv, Michael; Avezniyazov, Slava; Savkin, Alexander; Fedorov, Denis; Dmitriev, Sergei; Kornev, Vladimir

    2007-01-01

    At Moscow SIA 'Radon' jointly with JSC 'Alliance Gamma', the technology for NPP Decantate Treatment was developed, tested and realized at Kola NPP. This technology consists of dissolving the salt residue and subsequent treatment by ozonization, separation of the deposits formed from ozonization and selective cleaning by ferro-cyanide sorbents. The nonactive salt solution goes to an industrial waste disposal site or a repository specially developed at NPP sites for 'exempt waste' products by IAEA classification. This technology was realized at Kola NPP in December 2006 year. At this time more than 1000 m 3 of decantates log time stored are treated. It allows solving very old problem to empty decantates' tanks at NPPs in environmentally safe manner and with high volume reduction factor. (authors)

  6. Optimization of radiation protection at Bohunice NPP

    International Nuclear Information System (INIS)

    Dobis, L.; Svitek, J.

    2003-01-01

    Bohunice Nuclear Power Plant is situated in south - western part of Slovakia about 50 km away from Bratislava. There are four PWR reactors 440 MW e each - two units with reactors WWER - 230 (V1 NPP) and two units with WWER - 213 (V2 NPP). requirements for the optimization process are given in the mentioned Code No.12 of Ministry of Health. Code 12 stipulates the technical and organizational requirements for proving the Rational Achievable Level (RAL) of radiation protection. This level can be proved by means of the comparison of the dose distribution to the costs of protection. An example of two figures of dose constraints is: collective dose 20 man mSv for the specific task; individual exposure 1 mSv per day. The values of the financial equivalents of personal exposure - so called the alpha coefficients - are used for the calculation of the benefit of proposed measures. Impact of legislative changes into Bohunice NPP and optimization process are presented. Apparently the new law and the associate code created a base of transparent and understandable policy of radiation protection and optimization in Slovak Republic. The radiation protection legislative was implemented into the praxis and persons became familiar with it. Defining clear and unambiguous terms facilitated the communication between users and the regulatory body - State Health Institute. Optimization was generally accepted by the workers and managers and began to be a part of safety culture of operation at nuclear power plants. (authors)

  7. NPOESS Preparatory Project (NPP) Science Overview

    Science.gov (United States)

    Butler, James J.

    2011-01-01

    NPP Instruments are: (1) well understood thanks to instrument comprehensive test, characterization and calibration programs. (2) Government team ready for October 25 launch followed by instrument activation and Intensive Calibration/Validation (ICV). NPP Data Products preliminary work includes: (1) JPSS Center for Satellite Applications and Research (STAR) team ready to support NPP ICV and operational data products. (2) NASA NPP science team ready to support NPP ICV and EOS data continuity.

  8. Management of depression in the last month of life.

    Science.gov (United States)

    Eychmueller, Steffen

    2009-09-01

    In clinical practice, assessment and adequate treatment of depression in the last month of life remain a difficult task. Although assessment instruments and criteria for depression are available for use in the palliative care population, few have been applied for the last weeks of life. The same is true for clinical management including antidepressants. Assessment aids such as Hospital Anxiety and Depression Scale or Hamilton Depression Rating Scale are available and validated for the last days or weeks of life, but its clinical impact remains unclear. The wish to die may symbolize more the acceptance that life comes to an end instead of reflecting a depressive or anxiety disorder. Communication about concrete preparation for death, life completion discussions, expressing religious struggle and giving back a sense of coherence seem to be promising non-pharmacological strategies and may lead to improved social function and better management of physical symptoms. Good news for researchers comes from a recent study highlighting the fact that psychosocial research seems to be of more potential benefit than burden for the patient. No recent literature can be found on the pharmacological management of depression in the last weeks of life. Few studies demonstrate the usefulness of concrete end of life preparation discussions that underpins the importance and impact of best carer-patient relationship during this last phase of life. A Cochrane protocol on antidepressants in severely physically ill patients has been undertaken recently to highlight this important clinical question, but results may reflect the lack of studies focusing on the last weeks or days of life.

  9. 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

  10. Managing Inflections in Life and Career: Tale from a Physicist

    Science.gov (United States)

    Bhattacharya, Santanu

    2010-03-01

    By training, a physicist possesses one of the rarest qualities ever imparted in an educational degree program, namely, the ability to take on complex problems, divide them into ``solvable'' parts, derive solutions and put them back as insightful outputs. Dr Bhattacharya, CEO of Salorix, a research, analytics and consulting firm, explains how he has used these skills learned at the graduate school to build a career as a scientist, management consultant and entrepreneur. He will also speak about how the real-life skillsets of understanding and dealing with ``Inflections'', self discovery and introspection can be a great tool for managing one's life and career progression.

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

    International Nuclear Information System (INIS)

    Kichev, E.

    1999-01-01

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

  12. Supercompaction of radioactive waste at NPP Krsko

    International Nuclear Information System (INIS)

    Fink, K.; Sirola, P.

    1996-01-01

    The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as a political tool, brought the final radioactive repository siting effort to a stop. Although small amounts of radioactive waste are produced in research institutes, hospitals and industry, major source of radioactive waste in Slovenia is the Nuclear Power Plant Krsko. When Krsko NPP was originally built, plans were made to construct a permanent radioactive waste disposal facility. This facility was supposed to be available to receive waste from the plant long before the on site storage facility was full. However, the permanent disposal facility is not yet available, and it became necessary to retain the wastes produced at the plant in the on-site storage facility for an extended period of time. Temporary radioactive storage capacity at the plant site has limited capacity and having no other options available NPP Krsko is undertaking major efforts to reduce waste volume generated to allow normal operation. This article describes the Radioactive Waste Compaction Campaign performed from November, 1994 through November, 1995 at Krsko NPP, to enhance the efficiency and safety of storage of radioactive waste. The campaign involved the retrieval, segmented gamma-spectrum measurement, dose rate measurement, compaction, re-packaging, and systematic storage of radioactive wastes which had been stored in the NPP radioactive waste storage building since plant commissioning. (author)

  13. Work-Life Balance, Management Practices and Productivity

    OpenAIRE

    Nick Bloom; Tobias Kretschmer; John Van Reenen

    2006-01-01

    Do “Anglo-Saxon” management practices generate higher productivity only at the expense of lousy work-life balance (WLB) for workers? Many critics of “neo-libéralisme sauvage” have argued that increased competition from globalisation is damaging employees’ quality of life. Others have argued the opposite that improving work-life balance is actually a competitive tool that companies can use to raise productivity. We try to shed some empirical light on these issues using an innovative survey too...

  14. Improving Life-Cycle Cost Management of Spacecraft Missions

    Science.gov (United States)

    Clardy, Dennon

    2010-01-01

    This presentation will explore the results of a recent NASA Life-Cycle Cost study and how project managers can use the findings and recommendations to improve planning and coordination early in the formulation cycle and avoid common pitfalls resulting in cost overruns. The typical NASA space science mission will exceed both the initial estimated and the confirmed life-cycle costs by the end of the mission. In a fixed-budget environment, these overruns translate to delays in starting or launching future missions, or in the worst case can lead to cancelled missions. Some of these overruns are due to issues outside the control of the project; others are due to the unpredictable problems (unknown unknowns) that can affect any development project. However, a recent study of life-cycle cost growth by the Discovery and New Frontiers Program Office identified a number of areas that are within the scope of project management to address. The study also found that the majority of the underlying causes for cost overruns are embedded in the project approach during the formulation and early design phases, but the actual impacts typically are not experienced until late in the project life cycle. Thus, project management focus in key areas such as integrated schedule development, management structure and contractor communications processes, heritage and technology assumptions, and operations planning, can be used to validate initial cost assumptions and set in place management processes to avoid the common pitfalls resulting in cost overruns.

  15. A study on the Methodology for Integrated Safety Assessment for Accidental Analysis on LILW managed in Temporary Storage Facility (TSF) at NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Min Ho; Lee, Kun Jai [Korea Advanced Institute of Science and Technology, 335 Gwahak-ro, yuseong-gu, Daejeon 305-701 (Korea, Republic of); Choi, Kyung Woo [Korea Institute of Nuclear Safety, 34 Gwahak-ro, yuseong-gu, Daejeon 305-338 (Korea, Republic of)

    2010-07-01

    dose assessment were considered: {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 58}Co, {sup 60}Co, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 137}Cs, and {sup 144}Ce. According to the U.S. NRC Regulatory Guide 1.145, the atmospheric dispersion factors (?/Q) for workers and public were derived by meteorological data measured in Kori NPP: wind speed, wind direction, and atmospheric stability. For the evaluation of internal exposure, the breathing rate (m{sup 3}/sec) described in U.S. NRC Regulatory Guide 1.8 was considered. In conclusion: Based on the MLD method, the dropping of drums and fire were used to evaluate the exposure dose by arbitrary accidents originating in the TSF for LILW management. For the exposure dose assessment, a variety of parameters were considered: the amount of radionuclides released (Bq), the atmospheric dispersion factor for workers and public (sec/m{sup 3}), the breathing rate for internal exposure (m{sup 3}/sec), and the dose conversion factor for internal and external exposure (mSv/Bq, mSv/hr per Bq/m{sup 3}). Furthermore, an exposure dose assessment was conducted in terms of the effective dose and the thyroid equivalent dose for workers and public, considering the release rates of the radionuclides stemming from the dropping of drums and fire. The number of damaged drums was taken as 2 for the dropping of drums and 40 for fire relative to each waste stream. Seven waste streams were considered: the general DAW (200 L), the shielded DAW (200 L), the concentrated waste solidified by cement (200 L), the concentrated waste stabilized by paraffin (200 L), the general spent resin (200 L), the spent resin solidified by cement (200 L), and the general spent filter (200 L). The effective doses resulted from the dropping of drums were in the range of 4.95 E-15 to 2.19 E- 7 mSv for workers and 9.21 E-17 to 1.34 E-9 mSv for public. Also the thyroid equivalent doses originating from the dropping of drums were in the range of 3

  16. Nurse managers' work life quality and their participation in knowledge management: a correlational study.

    Science.gov (United States)

    Hashemi Dehaghi, Zahra; Sheikhtaheri, Abbas; Dehnavi, Fariba

    2015-01-01

    The association between quality of work life and participation in knowledge management is unknown. This study aimed to discover the association between quality of work life of nurse managers and their participation in implementing knowledge management. This was a correlational study. All nurse managers (71 people) from 11 hospitals affiliated with the Social Security Organization in Tehran, Iran, were included. They were asked to rate their participation in knowledge management and their quality of work life. Data was gathered by a researcher-made questionnaire (May-June 2012). The questionnaire was validated by content and construct validity approaches. Cronbach's alpha was used to evaluate reliability. Finally, 50 questionnaires were analyzed. The answers were scored and analyzed using mean of scores, T-test, ANOVA (or nonparametric test, if appropriate), Pearson's correlation coefficient and linear regression. Nurse managers' performance to implement knowledge management strategies was moderate. A significant correlation was found between quality of work life of nurse managers and their participation in implementing knowledge management strategies (r = 0.82; P The strongest correlations were found between implementation of knowledge management and participation of nurse managers in decision making (r = 0.82; P knowledge management.

  17. THE RELATIONSHIP BETWEEN PROFESSIONAL AND PRIVATE LIFE OF ROMANIAN MANAGERS

    Directory of Open Access Journals (Sweden)

    Mirela CIOLAC

    2014-12-01

    Full Text Available Purpose–The investigation of relationship between professional and family life of managers from Romania in terms of time allocated to these aspects. Design/methodology/approach – This study was conducted on 111 managers from Arad County (56 men and 55 women from various fields of activity. Findings – The results support the idea that leisure time decreases after taking over the position of manager. Practical implications/originality/value – There is no significant association between gender and the amount of leisure time. Although we expected women to report less leisure time after taking over the top management position (and men more leisure time this situation cannot be reported. Explanations: 1. there are differences but they could not be depicted through the manner the data were collected 2. Women managers get help from other people (parents, in-laws, husband, housekeeper after taking over management positions.

  18. Examining End-of-Life Case Management: Systematic Review

    Directory of Open Access Journals (Sweden)

    Roger E. Thomas

    2014-01-01

    Full Text Available Case management was initiated in the 1970s to reduce care discontinuity. A literature review focused on end-of-life (EOL case management identified 17 research articles, with content analysis revealing two themes: (a seeking to determine or establish the value of EOL case management and (b identifying ways to improve EOL case management. The evidence, although limited, suggests that EOL case management is helpful to dying individuals and their families. Research is needed to more clearly illustrate its usefulness or outcomes and the extent of need for it and actual availability. Among other benefits, EOL case management may help reduce hospital utilization, a major concern with the high cost of hospital-based care and the increased desire for home-based EOL care.

  19. Shock absorber in Ignalina NPP

    International Nuclear Information System (INIS)

    Bulavas, A.; Muralis, J.

    1996-09-01

    Theoretical calculation and experimental analysis of models of shock absorber in Ignalina NPP is presented. The results obtained from the investigation with model of shock absorber coincide with the theoretical calculation. (author). 2 figs., 3 refs

  20. Dukovany NPP - Safely 16 TERA

    International Nuclear Information System (INIS)

    Vlcek, J.

    2008-01-01

    In this presentation increasing of power output of the Dukovany NPP is reviewed. To operate all Dukovany Units safely with the perspective of long-term operation (LTO) of 50 - 60 years it is proposed.

  1. Selection of NPP for Kazakhstan

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.

    2003-01-01

    Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

  2. Psychology of NPP operation safety

    International Nuclear Information System (INIS)

    Tret'yakov, V.P.

    1993-01-01

    The book is devoted to psychologic investigations into different aspects of NPP operative personnel activities. The whole set of conditions on which successful and accident-free personnel operation depends, is analysed. Based on original engineering and socio-psychologic investigations complex psychologic support for NPP personnel and a system of training and upkeep of operative personnel skills are developed. The methods proposed have undergone a practical examination and proved their efficiency. 154 refs., 12 figs., 9 tabs

  3. Developing Asset Life Cycle Management capabilities through the implementation of Asset Life Cycle Plans – an Action Research project

    OpenAIRE

    Ruitenburg, Richard; Braaksma, Anne Johannes Jan

    2017-01-01

    Asset Life Cycle Management is a strategic approach to managing physical assets over their complete life cycle. However, the literature and the recent ISO 55,000 standard do not offer guidance as to how to develop such an approach. This paper investigates the main capabilities for Asset Life Cycle Management by means of a four year Action Research project implementing Asset Life Cycle Plans. Five main capabilities emerged: 1. strategic information use; 2. alignment of operations and strategy;...

  4. Spent fuel pool risk analysis for the Dukovany NPP

    Energy Technology Data Exchange (ETDEWEB)

    Hust' ak, S.; Jaros, M.; Kubicek, J. [UJV Rez, a.s., Husinec-Rez (Czech Republic)

    2013-07-01

    UJV Rez, a.s. maintains a Living Probabilistic Safety Assessment (Living PSA) program for Dukovany Nuclear Power Plant (NPP) in the Czech Republic. This project has been established as a framework for activities related to risk assessment and to support for risk-informed decision making at this plant. The most extensively used PSA application at Dukovany NPP is risk monitoring of instantaneous (point-in-time) risk during plant operation, especially for the purpose of configuration risk management during plant scheduled outages to avoid risk significant configurations. The scope of PSA for Dukovany NPP includes also determination of a risk contribution from spent fuel pool (SFP) operation to provide recommendations for the prevention and mitigation of SFP accidents and to be applicable for configuration risk management. This paper describes the analysis of internal initiating events (IEs) in PSA for Dukovany NPP, which can contribute to the risk from SFP operation. The analysis of those IEs was done more thoroughly in the PSA for Dukovany NPP in order to be used in instantaneous risk monitoring. (orig.)

  5. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias

    2013-06-01

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  6. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias

    2013-06-01

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  7. ORSEC technological risks, Blayais NPP

    International Nuclear Information System (INIS)

    2016-01-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Blayais NPP (Gironde, France)

  8. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  9. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  10. Economics and policies of nuclear plant life management

    International Nuclear Information System (INIS)

    Yamagata, H.

    1998-01-01

    NEA provides an opportunity for international exchange of information on the economics and policies of nuclear plant life management for governments and plant owners. The NEA Secretariat is finalising the 'state-of-the-art report' on the economics and policies of nuclear plant life management, including the model approach and national summaries. In order to meet power supply obligations in the early 2000, taking into account energy security, environmental impact, and the economics of nuclear power plants whose lives have been extended, initiatives at national level must be taken to monitor, co-ordinate, and support the various industry programmes of nuclear plant life management by integrated and consistent policies, public acceptance, R and D, and international co-operation. Nuclear power owners should establish an organisation and objectives to carry nuclear plant life management in the most economic and smoothest way taking into consideration internal and external influences. The organisation must identify the critical item and the ageing processes, and optimise equipment reliability and maintenance workload. (author)

  11. Managing work-life policies : disruption versus dependency arguments

    NARCIS (Netherlands)

    Dulk, Laura den; Ruijter, Judith de

    2008-01-01

    What factors shape managerial attitudes towards the utilization of work-life policies? The influence of disruptiveness (Powell and Mainiero 1999) and dependency (Klein, Berman and Dickson 2000) arguments on managerial attitudes is examined using a vignette design. In this study, managers in four

  12. Innovative predictive maintenance concepts to improve life cycle management

    NARCIS (Netherlands)

    Tinga, Tiedo

    2014-01-01

    For naval systems with typically long service lives, high sustainment costs and strict availability requirements, an effective and efficient life cycle management process is very important. In this paper four approaches are discussed to improve that process: physics of failure based predictive

  13. Optimizing Battery Usage and Management for Long Life

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Kandler; Shi, Ying; Wood, Eric; Pesaran, Ahmad

    2016-06-16

    This presentation discusses the impact of system design factors on battery aging and end of life. Topics include sizing of the state-of-charge operating window, cell balancing, and thermal management systems and their value in reducing pack degradation rates and cell imbalance growth over lifetime.

  14. Optimizing Battery Usage and Management for Long Life

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Kandler; Shi, Ying; Wood, Eric; Pesaran, Ahmad

    2016-06-16

    This presentation discusses the impact of system design factors on battery aging and end of life. Topics include sizing of the SOC operating window, cell balancing and thermal management systems and their value in reducing pack degradation rates and cell imbalance growth over lifetime.

  15. International database on ageing management and life extension

    International Nuclear Information System (INIS)

    Ianko, L.; Lyssakov, V.; McLachlan, D.; Russell, J.; Mukhametshin, V.

    1995-01-01

    International database on ageing management and life extension for reactor pressure vessel materials (RPVM) is described with the emphasis on the following issues: requirements of the system; design concepts for RPVM database system; data collection, processing and storage; information retrieval and dissemination; RPVM information assessment and evaluation. 1 fig

  16. European top managers' support for work-life arrangements

    NARCIS (Netherlands)

    Been, W.M.|info:eu-repo/dai/nl/357424662

    2015-01-01

    In recent decades, work-life arrangements increasingly became an integral part of the organization of work. Arrangements such as telecommuting, flextime, part-time hours, and various types of leave arrangements are available to employees in many organizations. Top managers, such as CEOs, CFOs and

  17. Suomi NPP Ground System Performance

    Science.gov (United States)

    Grant, K. D.; Bergeron, C.

    2013-12-01

    The National Oceanic and Atmospheric Administration (NOAA) and National Aeronautics and Space Administration (NASA) are jointly acquiring the next-generation civilian weather and environmental satellite system: the Joint Polar Satellite System (JPSS). JPSS will replace the afternoon orbit component and ground processing system of the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA. The JPSS satellites will carry a suite of sensors designed to collect meteorological, oceanographic, climatological and geophysical observations of the Earth. The first satellite in the JPSS constellation, known as the Suomi National Polar-orbiting Partnership (Suomi NPP) satellite, was launched on 28 October 2011, and is currently undergoing product calibration and validation activities. As products reach a beta level of maturity, they are made available to the community through NOAA's Comprehensive Large Array-data Stewardship System (CLASS). CGS's data processing capability processes the satellite data from the Joint Polar Satellite System satellites to provide environmental data products (including Sensor Data Records (SDRs) and Environmental Data Records (EDRs)) to NOAA and Department of Defense (DoD) processing centers operated by the United States government. CGS is currently processing and delivering SDRs and EDRs for Suomi NPP and will continue through the lifetime of the Joint Polar Satellite System programs. Following the launch and sensor activation phase of the Suomi NPP mission, full volume data traffic is now flowing from the satellite through CGS's C3, data processing, and data delivery systems. Ground system performance is critical for this operational system. As part of early system checkout, Raytheon measured all aspects of data acquisition, routing, processing, and delivery to ensure operational performance requirements are met, and will continue to be met throughout the mission. Raytheon developed a tool to measure, categorize, and

  18. Industrial open source solutions for product life cycle management

    Directory of Open Access Journals (Sweden)

    Jaime Campos

    2014-12-01

    Full Text Available The authors go through the open source for product life cycle management (PLM and the efforts done from communities such as the open source initiative. The characteristics of the open source solutions are highlighted as well. Next, the authors go through the requirements for PLM. This is an area where more attention has been given as the manufacturers are competing with the quality and life cycle costs of their products. Especially, the need of companies to try to get a strong position in providing services for their products and thus to make themselves less vulnerable to changes in the market has led to high interest in product life cycle simulation. The potential of applying semantic data management to solve these problems discussed in the light of recent developments. In addition, a basic roadmap is presented as to how the above-described problems could be tackled with open software solutions.

  19. Security Risks: Management and Mitigation in the Software Life Cycle

    Science.gov (United States)

    Gilliam, David P.

    2004-01-01

    A formal approach to managing and mitigating security risks in the software life cycle is requisite to developing software that has a higher degree of assurance that it is free of security defects which pose risk to the computing environment and the organization. Due to its criticality, security should be integrated as a formal approach in the software life cycle. Both a software security checklist and assessment tools should be incorporated into this life cycle process and integrated with a security risk assessment and mitigation tool. The current research at JPL addresses these areas through the development of a Sotfware Security Assessment Instrument (SSAI) and integrating it with a Defect Detection and Prevention (DDP) risk management tool.

  20. The chooz a expert survey program and its main conclusions for plant life management

    International Nuclear Information System (INIS)

    Barthelet, B.; Heuze, A.; Hennart, J.C.; Havard, P.

    2001-01-01

    Because of the importance of PWR components life management represents for Electricity Companies, significant R and D programs are dedicated to identifying and analysing mechanisms and damage rates of the different degradation modes of these components, systems and structures. To assess R and D assumptions and to validate non destructive test results through reviews, expert survey programs on in-situ equipment may enhance the knowledge about most of the various phenomena involved. In this regard, an extensive program was launched after the Chooz A NPP was decommissioned in 1991, after 24 years in operation. This program gathered EDF, IPSN, FRAMATOME, ELECTRABEL and TRACTEBEL into partnership. The expert survey program was performed in various laboratories between 1995 and 1999 and includes: - on-site non destructive testing before sampling, - and metallurgical and mechanical tests performed on samples taken from the nuclear and non nuclear part of the unit. The expert survey program performed by Utilities in various laboratories involved the following equipment: - reactor vessel and internal equipment, - reactor coolant system (dissimilar metal welds, SS welds, cast austenitic ferritic steels), - feedwater plant piping (erosion-corrosion), - electric cables susceptible of temperature and irradiation induced ageing, - anchoring in civil engineering structures, - main primary circuit concerning activation measurement. In conclusion, the extensive Chooz A expert survey program yields numerous significant results. The main outcomes will contribute to validate non destructive tests and enhance our knowledge of some degradation mechanisms of often quite similar components present in units in operation. It is worthy to note that this program is of prime importance for operation feedback; the cost of the whole study amounts to approximately 10 Million Euros. (author)

  1. Corrosion strength monitoring of NPP component residual lifetime

    International Nuclear Information System (INIS)

    Denisov, V.G.; Belous, V.N.; Arzhaev, A.I.; Shuvalov, V.A.

    1994-01-01

    Importance of corrosion and fatigue monitoring; types of corrosion determine the NPP equipment life; why automated on-line corrosion and fatigue monitoring is preferable; major stages of lifetime monitoring system development; major groups of sensors for corrosion and strength monitoring system; high temperature on-line monitoring of water chemistry and corrosion; the RBMK-1000 NPP unit automatic water chemistry and corrosion monitoring scheme; examples of pitting, crevice and general corrosion forecast calculations on the basis of corrosion monitoring data; scheme of an experimental facility for water chemistry and corrosion monitoring sensor testing. 2 figs., 4 tabs

  2. Project Management Life Cycle Models to Improve Management in High-rise Construction

    Science.gov (United States)

    Burmistrov, Andrey; Siniavina, Maria; Iliashenko, Oksana

    2018-03-01

    The paper describes a possibility to improve project management in high-rise buildings construction through the use of various Project Management Life Cycle Models (PMLC models) based on traditional and agile project management approaches. Moreover, the paper describes, how the split the whole large-scale project to the "project chain" will create the factor for better manageability of the large-scale buildings project and increase the efficiency of the activities of all participants in such projects.

  3. Project Management Life Cycle Models to Improve Management in High-rise Construction

    Directory of Open Access Journals (Sweden)

    Burmistrov Andrey

    2018-01-01

    Full Text Available The paper describes a possibility to improve project management in high-rise buildings construction through the use of various Project Management Life Cycle Models (PMLC models based on traditional and agile project management approaches. Moreover, the paper describes, how the split the whole large-scale project to the "project chain" will create the factor for better manageability of the large-scale buildings project and increase the efficiency of the activities of all participants in such projects.

  4. Jpss System Architecture Npp to the Future

    Science.gov (United States)

    Furgerson, J.; Trumbower, G.

    2012-12-01

    The National Oceanic and Atmospheric Administration (NOAA) is acquiring the next-generation weather and environmental satellite system, named the Joint Polar Satellite System (JPSS). The National Aeronautics and Space Administration (NASA) serves as the acquisition and development agent. JPSS replaces the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA in the 1330 local time of ascending node (LTAN) orbit. The Suomi National Polar-orbiting Partnership (NPP) was launched into the 1330 LTAN orbit on October 28, 2011, and carries advanced sensors which will be featured on JPSS. It serves as a bridge mission and provides continuity for the NASA Earth Observation System and the POES. JPSS-1 is scheduled to launch in 2017. The Defense Meteorological Satellite Program (DMSP) managed by the DoD is operating in the 1730 LTAN orbit. The DoD is developing the Defense Weather Satellite Follow-on (WSF) system which will continue in the 1730 orbit. NASA is developing the Common Ground System (CGS) with the capability to process data from both the JPSS and WSF constellations. The CGS will be operated by NOAA. This poster will provide a top level status update of the program, as well as an overview of the JPSS system architecture. The space segment carries a suite of sensors that collect meteorological, oceanographic, and climatological observations of the earth and atmosphere. The system design allows centralized mission management and delivers high quality environmental products to military, civil and scientific users through a Command, Control, and Communication Segment (C3S). The data processing for NPP/JPSS is accomplished through an Interface Data Processing Segment (IDPS)/Field Terminal Segment (FTS) that processes NPP/JPSS satellite data to provide environmental data products to NOAA and DoD processing centers as well as remote terminal users.

  5. Corporate portal system at PAKS NPP, Hungary

    International Nuclear Information System (INIS)

    2009-01-01

    The new Corporate Portal System (CPS) of Paks NPP was launched in November 2006. The portal is based on one of the latest technologies, Plumtree Enterprise WEB 5.0. The main purpose of the installation of the new technology was to serve the working culture change, to give a platform to access all information and applications including the integrated process model used at the NPP. The new technology also supports those goals which were defined in the organization development programme: e.g. to improve internal communication with the establishment of communities of practice. Installation of the CPS has provided a powerful tool for knowledge management; it is possible to share and find all information through a controlled access in documents from various sources, to have links to people, portlets and different communities. Document management of the Paks NPP is supported by the integration of the Document 5 application, as the new Electronic Data Management System (EDMS) and the CPS. Depending on their access rights, all users of the CPS, through Microsoft Internet Explorer, can access technical, economic and human resources documents which are stored anywhere on the internal network (file servers, EDMS, old INRANET). The CPS is also accessible from the internet through a secure connection. The main concept is the integration of all applications to one platform and to help users to find all information they need. An access control list specifies which users and groups have access to an object (and what kind of access privileges they have such as read, select, edit, admin)

  6. Safety Culture Survey in Krsko NPP

    International Nuclear Information System (INIS)

    Strucic, M.; Bilic Zadric, T.

    2008-01-01

    results very reliable. Survey results were statistically analyzed and presented to Krsko NPP management board. More specific qualitative analyses were performed for departments. With assistance of Safety Culture Self Assessment team members, leaders of these departments developed specific action plans and disseminated major identified issues. By these feedbacks Krsko NPP ensured better employees understanding of the results of the survey. It is very exceptive that employee's responses will contribute to the overall process and establishment of safety conscious work environment.(author)

  7. Asset life cycle plans: twelve steps to assist strategic decision-making in asset life cycle management

    NARCIS (Netherlands)

    Ruitenburg, Richard Jacob; Braaksma, Anne Johannes Jan; van Dongen, Leonardus Adriana Maria; Carnero, Maria Carmen; Gonzalez-Prida, Vicente

    2017-01-01

    Effective management of physical assets should deliver maximum business value. Therefore, Asset Management standards such as PAS 55 and ISO 55000 ask for a life cycle approach. However, most existing methods focus only on the short term of the asset's life or the estimation of its remaining life.

  8. Developing Asset Life Cycle Management capabilities through the implementation of Asset Life Cycle Plans – an Action Research project

    NARCIS (Netherlands)

    Ruitenburg, Richard; Braaksma, Anne Johannes Jan

    2017-01-01

    Asset Life Cycle Management is a strategic approach to managing physical assets over their complete life cycle. However, the literature and the recent ISO 55,000 standard do not offer guidance as to how to develop such an approach. This paper investigates the main capabilities for Asset Life Cycle

  9. 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

  10. Line Manager Involvement in Work-Life Balance and Career Development: Can't Manage, Won't Manage?

    Science.gov (United States)

    Dick, Penny; Hyde, Rosie

    2006-01-01

    Line manager involvement in HRM is an increasing trend across Europe. With the numbers of employees taking advantage of work-life balance policies also on the increase, line manager responsibility for this specific policy area is likely to become more marked. In this paper, we argue that line managers have a critical role to play in the career…

  11. 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

  12. Steam generator life cycle management: Ontario Power Generation (OPG) experience

    International Nuclear Information System (INIS)

    Maruska, C.C.

    2002-01-01

    A systematic managed process for steam generators has been implemented at Ontario Power Generation (OPG) nuclear stations for the past several years. One of the key requirements of this managed process is to have in place long range Steam Generator Life Cycle Management (SG LCM) plans for each unit. The primary goal of these plans is to maximize the value of the nuclear facility through safe and reliable steam generator operation over the expected life of the units. The SG LCM plans integrate and schedule all steam generator actions such as inspection, operation, maintenance, modifications, repairs, assessments, R and D, performance monitoring and feedback. This paper discusses OPG steam generator life cycle management experience to date, including successes, failures and how lessons learned have been re-applied. The discussion includes relevant examples from each of the operating stations: Pickering B and Darlington. It also includes some of the experience and lessons learned from the activities carried out to refurbish the steam generators at Pickering A after several years in long term lay-up. The paper is structured along the various degradation modes that have been observed to date at these sites, including monitoring and mitigating actions taken and future plans. (author)

  13. 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

  14. 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

  15. Essential Partnerships in the Data Management Life Cycle

    Science.gov (United States)

    Kinkade, D.; Allison, M. D.; Chandler, C. L.; Copley, N. J.; Gegg, S. R.; Groman, R. C.; Rauch, S.

    2015-12-01

    An obvious product of the scientific research process is data. Today's geoscience research efforts can rapidly produce an unprecedented volume of multidisciplinary data that can pose management challenges for the facility charged with curating that information. How do these facilities achieve efficient data management in a high volume, heterogeneous data world? Partnerships are critical, especially for small to mid-sized data management offices, such as those dedicated to academic research communities. The idea of partnerships can encompass a wide range of collaborative relationships aimed at helping these facilities meet the evolving needs of their communities. However, one basic and often overlooked partnership in the data management process is that of the information manager and the Principal Investigator (PI) or data originator. Such relationships are critical in discerning the best possible management strategy, and in obtaining the most robust metadata necessary for reuse of multidisciplinary datasets. Partnerships established early in the data life cycle enable efficient management and dissemination of data in high volumes and heterogeneous formats. The Biological and Chemical Oceanography Data Management Office (BCO-DMO) was created to fulfill the data management needs of PIs funded by the NSF Ocean Sciences Biological and Chemical Sections, and Division of Polar Programs. Since its inception, the Office has relied upon the close relationships it cultivates between its data managers and PIs in order to provide effective data management for a wide variety of ecological and biogeochemical oceanographic data. This presentation will highlight some of the successful partnerships BCO-DMO has made with individual and collaborative investigators, as well as those with other data managers representing specific research communities.

  16. Feature extraction and sensor selection for NPP initiating event identification

    International Nuclear Information System (INIS)

    Lin, Ting-Han; Wu, Shun-Chi; Chen, Kuang-You; Chou, Hwai-Pwu

    2017-01-01

    Highlights: • A two-stage feature extraction scheme for NPP initiating event identification. • With stBP, interrelations among the sensors can be retained for identification. • With dSFS, sensors that are crucial for identification can be efficiently selected. • Efficacy of the scheme is illustrated with data from the Maanshan NPP simulator. - Abstract: Initiating event identification is essential in managing nuclear power plant (NPP) severe accidents. In this paper, a novel two-stage feature extraction scheme that incorporates the proposed sensor type-wise block projection (stBP) and deflatable sequential forward selection (dSFS) is used to elicit the discriminant information in the data obtained from various NPP sensors to facilitate event identification. With the stBP, the primal features can be extracted without eliminating the interrelations among the sensors of the same type. The extracted features are then subjected to a further dimensionality reduction by selecting the sensors that are most relevant to the events under consideration. This selection is not easy, and a combinatorial optimization technique is normally required. With the dSFS, an optimal sensor set can be found with less computational load. Moreover, its sensor deflation stage allows sensors in the preselected set to be iteratively refined to avoid being trapped into a local optimum. Results from detailed experiments containing data of 12 event categories and a total of 112 events generated with a Taiwan’s Maanshan NPP simulator are presented to illustrate the efficacy of the proposed scheme.

  17. Study on the risk-informed regulation of NPP

    International Nuclear Information System (INIS)

    Wang Chaogui

    2007-01-01

    The risk-informed regulation is a modern type of NPP safety management mode using both deterministic and probabilistic approaches. It is necessary to entirely and systematically study the associated regulations, standards and practices in order to promote the developments of risk-informed regulations in China. This paper introduces the risk-informed regulation, gives out the basic principles, method and acceptance risk criteria of risk-informed decision,making, discusses the PSA requirements for risk-informed decision-making and makes some suggestions about the application of risk-informed regulations in Chinese NPP. (authors)

  18. Application of Cloud Storage on BIM Life-Cycle Management

    Directory of Open Access Journals (Sweden)

    Lieyun Ding

    2014-08-01

    Full Text Available Because of its high information intensity, strong consistency and convenient visualization features, building information modelling (BIM has received widespread attention in the fields of construction and project management. However, due to large amounts of information, high integration, the need for resource sharing between various departments, the long time-span of the BIM application, challenges relating to data interoperability, security and cost all slow down the adoption of BIM. This paper constructs a BIM cloud storage concept system using cloud storage, an advanced computer technology, to solve the problem of mass data processing, information security, and cost problems in the existing application of BIM to full life-cycle management. This system takes full advantage of the cloud storage technique. Achievements are reached in four areas of BIM information management, involving security and licensing management, file management, work process management and collaborative management. The system expands the time and space scales, improves the level of participation, and reduces the cost of BIM. The construction of the BIM cloud storage system is one of the most important directions of the development of BIM, which benefits the promotion and further development of BIM to better serve construction and engineering project management.

  19. Setting priorities for the proactive management of longterm challenges and opportunities in Asset Life Cycle Management

    NARCIS (Netherlands)

    Ruitenburg, Richard Jacob; Braaksma, Anne Johannes Jan; van Diepen, T.

    2016-01-01

    Asset Life Cycle Management concerns the effective management of physical assets over their complete lifetimes, typically lasting decades. Therefore, a large number and a wide variety of challenges and opportunities may need to be dealt with proactively, using limited resources. Therefore, we

  20. Implementation of the II. Stage decommissioning of A1 NPP

    International Nuclear Information System (INIS)

    Ficher, T.

    2015-01-01

    Presentation is focused on the implementation of the II. stage decommissioning of A1 NPP. Introductory part focuses on brief characteristics of the power plant with a history of operation, basic technical parameters and actions that were made after operation. The next section describes the basic schedule for decommissioning, structure of management and implementation of the II. stage decommissioning of the A1 NPP and objectives of the individual stages. The last and largest part of the presentation is devoted to detailed description of the II. stage decommissioning of the A1 NPP, its individual tasks and verbal and visual description of the activities that were performed. Presented is decommissioning of the technology and construction of external objects NPP A1 including storage tanks for liquid RAW, next are presented activities carried out in the Main Production Unit - decommissioning of non-operating technologies in various places/rooms, management of waste arising from these activities, treatment of case of A1 long-term spent fuel storage and long-term spent fuel storage. The subsequent section is devoted to the management and handling of contaminated soil, concrete and construction waste, including management of VLLW. (authors)

  1. The Ignalina NPP and Y2K Problem

    International Nuclear Information System (INIS)

    Medeliene, D.

    2000-01-01

    Work on preparing the hardware and software of the Ignalina NPP for the year 2000 was started in December 1998. First of all, a Y2K project team was formed comprising 29 specialists. Some of these are the most experienced computer specialist, others co-ordinate work on the Y2K problem at the divisions of the NPP using computers or microprocessors. The project head was appointed and the schedule of work confirmed. In accordance with the schedule, the work was divided into twelve stages. The results showed that the preparations were adequate. On the New Year night the specialists of the Ignalina NPP Emergency Operation Centre worked together with the managers of the plant. Relation with other Lithuanian and international organisations was established. No any Y2K related event happened

  2. Spain in South Ukraine NPP

    International Nuclear Information System (INIS)

    Ibanez, M.

    1994-01-01

    A Technical Assistance Protocol was signed between the Governments of the GIS and the Commission of the European Union (CEU) on August 2, 1991 and this was the starting point of the TACIS program. In this article, the activities described are those related to the TACIS-92/93/94 on site technical assistance to South Ukraine NPP (SUK NPP). Within the scope of the TACIS 92 Program the CEU and the Ukrainian Authorities agreed a list of projects to be implemented at South Ukraine NPP with the aim to improve the operational safety of the plant. This part of the program is called TACIS 92 on-site activities. The total budget allocated to these projects is a MECU. The European Union ''utility'' selected to lead this program at South Ukraine NPP was UNESA and the first contract to cover our activities was signed in July 1993 between the CEU (Mr. Pablo Benavides) and UNESA (Mr. Pedro Rivero). The projects will be implemented at SUK NPP but according to the contract UNESA is ''The Consultant'' and GOSKOMATON (The Ukrainian Sate Committee on Nuclear Power Utilization) is the ''Recipient Institution''. (Author)

  3. Integrated waste management and the tool of life cycle inventory : a route to sustainable waste management

    Energy Technology Data Exchange (ETDEWEB)

    McDougall, F.R.; White, P.R. [Procter and Gamble Newcastle Technical Centre, Newcastle (United Kingdom). Corporate Sustainable Development

    2000-07-01

    An overall approach to municipal waste management which integrates sustainable development principles was discussed. The three elements of sustainability which have to be balanced are environmental effectiveness, economic affordability and social acceptability. An integrated waste management (IWM) system considers different treatment options and deals with the entire waste stream. A life cycle inventory (LCI) and life cycle assessment (LCA) is used to determine the environmental burdens associated with IWM systems. LCIs for waste management are currently available for use in Europe, the United States, Canada and elsewhere. LCI is being used by waste management companies to assess the environmental attributes of future contract tenders. The models are used as benchmarking tools to assess the current environmental profile of a waste management system. They are also a comparative planning and communication tool. The authors are currently looking into publishing, at a future date, the experience of users of this LCI environmental management tool. 12 refs., 3 figs.

  4. [Impression management and self-presentation in occupational life].

    Science.gov (United States)

    Stresemann, E

    2013-06-01

    Impression management serves self-preservation as part of self-experience. It is adapted to a given situation as an expression of understanding of the role it plays in striving for success. Impression management and self-presentation mutually influence each other throughout life. Clichés in the traditional self-presentation of men and woman in their gender-specific domain in occupation belong to the past. In employment, contentment as much as discontent are of prime importance for success or failure in the workplace. As role models attract mainly juveniles, they should be held up to critical scrutiny.

  5. 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

  6. Life cycle assessment of waste management systems: Assessing technical externalities

    DEFF Research Database (Denmark)

    Brogaard, Line Kai-Sørensen

    The life cycle assessment (LCA) of a waste management system relies on many internal characteristics such as pollution control systems and recovery efficiencies. It also relies on technical externalities supporting the waste management system in terms of capital goods and energy and material...... for the primary and secondary production of materials, 366 datasets were gathered. The materials in focus were: paper, newsprint, cardboard, corrugated board, glass, aluminium, steel and plastics (HDPE, LDPE, LLDPE, PET, PS, PVC). Only one quarter of these data concerned secondary production, thus underlining...

  7. Reactor safety instrumentation of Paks NPP (experience and perspective)

    International Nuclear Information System (INIS)

    Elo, S.; Hamar, K.

    1993-01-01

    The majority of the existing control and protection systems in nuclear power plants use old analog technology and design philosophy. Maintenance and the procurement of spare parts is becoming increasingly difficult. In general there is an age degradation concern. Aging degradation in nuclear power plants must be effectively managed to avoid a loss of vital safety function, shutdown of the station, a reduced power generation, or any failure leading to expensive repair. Even with the best efforts in developing reliable and long life instrumentation and control systems for nuclear power plants it is expected that these systems for most plants will require replacements during the life of the plants. The instrumentation and control system of the nuclear power plants designed during the 70's and constructed in the 80's went out-of-date since nuclear safety is not a static concept and the digital computer technology has undergone rapid improvements during the 70's and 80's. Simultaneously the operation and the maintenance of the I ampersand C system of those plants described above becomes more and more difficult and expensive. In this context the pure quality of the former Soviet designed process instrumentation system increases the needs of upgrading this system. The author reviews the main design characteristics of the reactor safety instrumentation of the Paks NPP. Further he attempts to convey the perspective on upgrading the reactor safety instrumentation as seen by the HAEC and its Nuclear Safety Inspectorate

  8. 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.)

  9. Life cycle assessment of construction and demolition waste management

    DEFF Research Database (Denmark)

    Butera, Stefania; Christensen, Thomas Højlund; Astrup, Thomas Fruergaard

    2015-01-01

    Life cycle assessment (LCA) modelling of construction and demolition waste (C&DW) management was carried out. The functional unit was management of 1 Mg mineral, source separated C&DW, which is either utilised in road construction as a substitute for natural aggregates, or landfilled. The assessed...... of the use of C&DW. Typical uncertainties related to contaminant leaching were addressed. For most impact categories, utilisation of C&DW in road construction was preferable to landfilling; however, for most categories, utilisation resulted in net environmental burdens. Transportation represented the most...... of the impact assessment was critical for modelling the leaching impacts. Compared with the overall life cycle of building and construction materials, leaching emissions were shown to be potentially significant for toxicity impacts, compared with contributions from production of the same materials, showing...

  10. Quality of life considerations and pain management in hidradenitis suppurativa

    DEFF Research Database (Denmark)

    Jemec, Gregor Be

    2017-01-01

    perceived as unclean and stigmatizing by the patients, but also cause pain and scarring making this inflammatory skin disorder unique. It is obvious that the disease has a significant negative impact on the patients' quality of life (QOL). The impact is influenced not only by the pain which is a significant...... independent contributor to the patients' life quality, but by the clinically significant comorbidity associated with HS. In particular, the psychological comorbidities of depression and anxiety both further compound QOL impairment and pain. It is strongly recommended that these factors be taken into account...... when planning a treatment strategy for patients with HS, and that specific steps are taken to manage pain and comorbidities associated with the reduced QOL generally experienced by this group of patients. Basic pain management includes anti-inflammatory treatments as well as local- and central...

  11. Self-management in daily life with psoriasis

    DEFF Research Database (Denmark)

    Rasmussen, Gitte Susanne; Maindal, Helle Terkildsen; Lomborg, Kirsten

    2012-01-01

    The aim of this integrative review is to identify and discuss patient needs for education to support self-management in daily life with psoriasis. As psoriasis increasingly gains recognition as a serious chronic autoimmune skin disease with long-term impairment on the life course, and not mainly...... a cosmetic problem, nurses are highly challenged to develop efficient education to support patient self-management. The paper includes five stages: (1) problem identification, (2) literature search, (3) data evaluation, (4) data analysis and synthesis, and (5) presentation, based on theoretic scaffolding...... around the concept "need." Nineteen of 164 original papers within nursing, medicine and psychology, and reflecting patient perspective were included. To capture the patients' cultural understanding of the implications of the disease and care, we developed an interlevel model indicating that self...

  12. The enhancement of Ignalina NPP in design and operational safety

    International Nuclear Information System (INIS)

    Negrivoda, G.

    1999-01-01

    Enhancement of Ignalina NPP design include: core design improvements; fuel channel integrity (multiple pressure tube rupture); improvements of shutdown systems; improvements of instrumentation and control devices; containment strength and tightness; design basis accident analysis; improvements of safety and support systems; seismic safety enhancement; Year 2000 project; cracks in pipes. Enhancement of operational safety includes: quality assurance; configuration management; safety management and safety culture; emergency operating procedures; training and full scope simulator; in-service inspection; fire protection and ageing monitoring and management

  13. Some problems of NPP personnel training

    International Nuclear Information System (INIS)

    Vajshnis, P.P.; Kumkov, L.P.; Omel'chuk, V.V.

    1984-01-01

    Shortcomings of NPP personnel training are discussed. Development of full-scale training systems is necessary for qualitative training operative personnel. Primary problems that should be necessarily solved for ensuring effective training NPP personnel are considered

  14. Computerization of effluent management and external dose calculation using the 'ODCM' methodology applied to Almaraz-NPP; Mecanizacion informatica de la gestion de efluentes y calculo de dosis al exterior usando la metodologia MCDE aplicada a C.N. Almaraz

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Gutierrez, M E [Empresarios Agrupados, A.I.E., Madrid (Spain); Sustacha Duo, D [C.N. Almaraz, Caceres (Spain)

    1993-12-15

    The ODCM (Offsite Dose Calculation Manual), the official operational document for all nuclear power plants develops the details for the technical specifications for discharges and governs their practical application. The use of ODCM methodology for managing and controlling data associated with radioactive discharges, as well as the subsequent processing of this data to assess the radiological impact, requires and generates a large volume of data, which demands the frequent application of laborious and complex calculation processes, making computerization necessary. The computer application created for Almaraz NPP has the capacity to store and manage data on all discharges, evaluate their effects, presents reports and copies the information to be sent periodically to the CSN (Spanish Nuclear Regulatory Commission) on a magnetic tape. The radiological impact of an actual or possible discharge can be evaluated at anytime and, furthermore, general or particular reports and graphs on the discharges and doses over time can be readily obtained. The application is run on a personal computer under a relational database management system. This interactive application is based on menus and windows. (author)

  15. 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.

  16. 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.)

  17. 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.

  18. 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.

  19. Application of product life cycle concept to private label management

    Directory of Open Access Journals (Sweden)

    Sandra Horvat

    2013-06-01

    Full Text Available Private labels have recorded significant growth rates worldwide, becoming a serious threat to manufacturer brands. Development of private labels in many different product categories increased the complexity of their management. Therefore, this paper examines the possibility of using the product life cycle concept in private label management. Given that private labels are a specific brand type, it is necessary to adjust certain elements of the product life cycle concept, as it was developed on the basis of manufacturer brands. For instance, in the growth stage of the product life cycle, retailers expand private labels to a number of product categories and use the push strategy while manufacturers tend to expand their distribution network in the expansion of their brands and predominantly use the pull strategy in doing so. Furthermore, there is a focus shift from low-price strategy, predominantly used in the introduction phase, to increasing the quality and private label value in the later stages of the product life cycle.

  20. Applying life cycle management of colombian cocoa production

    Directory of Open Access Journals (Sweden)

    Oscar Orlando Ortiz-R

    2014-03-01

    Full Text Available The present research aims to evaluate the usefulness of the application of Life Cycle Management in the agricultural sector focusing on the environmental and socio-economic aspects of decision making in the Colombian cocoa production. Such appraisal is based on the application of two methodological tools: Life Cycle Assessment, which considers environmental impacts throughout the life cycle of the cocoa production system, and Taguchi Loss Function, which measures the economic impact of a process' deviation from production targets. Results show that appropriate improvements in farming practices and supply consumption can enhance decision-making in the agricultural cocoa sector towards sustainability. In terms of agri-business purposes, such qualitative shift allows not only meeting consumer demands for environmentally friendly products, but also increasing the productivity and competitiveness of cocoa production, all of which has helped Life Cycle Management gain global acceptance. Since farmers have an important role in improving social and economic indicators at the national level, more attention should be paid to the upgrading of their cropping practices. Finally, one fundamental aspect of national cocoa production is the institutional and governmental support available for farmers in face of socio-economic or technological needs.

  1. 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

  2. Rest-lifetime evaluation of equipment and facilities of NPP Kozloduy 3 and 4 and development of an ageing management program

    International Nuclear Information System (INIS)

    Erve, M.; Schmidt, J.; Kastner, B.; Gledatchev, I.; Sabinov, S.; Stoev, M.; Korneev, V.; Strombach, Y.

    2001-01-01

    The task indicated in the title is part of a comprehensive upgrading program for Units 3 and 4 of the Kozloduy plant executed in a Consortium between Framatome ANP (a Framatome and Siemens company) and the Russian company Atomstroyexport. It comprises an evaluation of the residual service life of components/systems/plants subject to acceptance by international experts, identifying the need for further investigations/calculations in certain cases, and finding solutions for improvements that achieve a consensus of safety and economy. The initial results are: Walkdowns revealed no clear knock-out point for the plants, however there are preliminary hints for necessary further improvements. Investigations of templates taken from the RPV of Unit 1 were started: the results are still preliminary, but can be considered very positive; their transfer to the RPV of Unit 3 would mean that the latest safety analyses of the Unit 3 RPV are conservative. The general work program was successfully applied on the batteries as a pattern for the electrical equipment: parameters for the computer database and proposals for an effective aging management program were addressed. (author)

  3. Environmental qualification program for Krsko NPP

    International Nuclear Information System (INIS)

    Cerjak, J.; Klenovsek, P.; Pavsek, J.; Freeland, K.R.; Spalj, S.

    1998-01-01

    NEK plant components, including those critical to safe plant operation, deteriorate and wear over service life due to the effects of aging and harsh environmental conditions. Since the plant environment is a source of common-cause failures, an Environmental Qualification (EQ) program is required to ensure and demonstrate the ability of safety-related equipment to perform its design safety function during a design-basis (DBE), even after aging over its service life in the plant. EQ is a requirement for plants licensed by the US NRC, in accordance with 10 CFR 50.49, Regulatory Guide 1.89, NUREG-0588, and IEEE-323. This paper presents the current EQ Program status at Krsko NPP.(author)

  4. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Kastchiev, G.

    1999-01-01

    Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

  5. Individual protection of NPP personnel

    International Nuclear Information System (INIS)

    Koshcheev, V.S.; Gol'dshtejn, D.S.; Chetverikova, Z.S.

    1983-01-01

    Specific features of NPP personnel individual protection are considered, mainly with respect to maintenance and repair works on various type reactors. The major concern is given to the selection and application reglamentations of the individual protection system (IPS), employment of sanitary locks, the organization of individual protection under the conditions of a heating microclimate. The ways are specified to the development and introduction of the most effective IPS and improvement of the entire NPP personnel individual protection system with respect to providing the necessary protection effect for maintaining high working capability of the personnel and minimizing the IPS impact on human organism functional systems. The accumulated experience in the personnel individual protection can be applied during construction and operation of NPP's in CMEA member-countries [ru

  6. A Multinational perspective to managing end-of-life electronics

    Energy Technology Data Exchange (ETDEWEB)

    Herold, M.

    2007-07-01

    This thesis focuses on how multinational electronics manufacturers manage used products in the EU, USA, Japan and China. Managing used or end-of-life products has interesting environmental and commercial implications. Recovering end-of-life products can reduce the environmental effects of disposal, raw material extraction, transport, and production. Whereas the commercial effects include image benefits and savings on raw material costs. Manufacturer involvement in end-of-life management is especially topical in the electronics industry, which is the focus of this thesis. Electronics products, such as TVs and computers, have been targeted with extended producer responsibility (EPR) legislation in different countries across the world. EPR is an environmental policy approach that forces manufacturers to take physical and/or financial responsibility for end-of-life products. The main objective of this dissertation was to increase understanding of how multinational manufacturers manage end-of-life products in the EU, in the USA, and in China and Japan, and the regional and company-specific factors explain their levels of involvement. This study consisted of an inductive 16-case multiple case study. The products and companies included in the study were as follows: Refrigerators (Bosch und Siemens Hausgeraete, Electrolux, Whirlpool); TVs (Samsung, Philips, Hitachi); PCs (Hewlett Packard, NEC, Fujitsu Limited and Fujitsu-Siemens Computers and an anonymous company, Alpha Computers); Mobile phones (Nokia, Motorola, Samsung); Telecommunication network equipment (Nokia, Motorola, Huawei). A manufacturer's level of involvement in end-of-life management can be characterized in terms of the level of organizational capabilities. These capabilities range from none to running a treatment facility and recovering value from own branded products. Levels in between can be characterized by outsourcing end-of-life management to industry-wide schemes, managing contracts for treating

  7. 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

  8. Equipment performance monitoring in NPP Krsko (Summarized system health report)

    International Nuclear Information System (INIS)

    Djetelic, N.; Cicvaric, D.

    2004-01-01

    Management common goal is safe, reliable, effective, acceptable to public and conservative/cautious operation of NPP Krsko. A set of programs, including Corrective Action Program, Performance Indicators, Operating Experience, Self Assessment and System Health Report, is developed to assist NPP Krsko management in fulfilling those goals. System Health Report is a tool that management can use to quickly assess how selected systems are performing, to determine where additional management attention is required and to determine if appropriate corrective actions have been established. Summarized System Health Report is developed for management's quick overview of systems status, important system malfunctions and problems as well as major changes from previous assessment period. Summarized Report contains nine sections: status difference including brief explanation, selected performance indicators, new equipment problems, functional failures, important problem analyses, action plan for systems with Potential Danger (RED) status, maintenance rule status overview and systems availability (planned and unplanned).(author)

  9. On the accounting of technology progress rates and obsolescence of production funds when determining depreciation for NPP renovation

    International Nuclear Information System (INIS)

    Khachyan, G.A.; Petrov, I.M.; Vorob'ev, I.E.; Nizhnik, I.A.; Pylypyuk, R.V.

    1986-01-01

    Questions, related to determining the economically grounded service life of NPP main production funds are considered. It is recommended to differentiate the depreciation standards by the operation duration. It is proposed to arrange the NPP buildings taking into account modern rates of technical progress in power engineering

  10. New Emergency control center of Slovenske Elektrarne Bohunice NPP

    International Nuclear Information System (INIS)

    Pecko, E.

    2012-01-01

    Emergency preparedness of nuclear power plant and operation assurance in case of a possible emergency calls to have devices for emergency response with equipment for rapid detection and continuous evaluation of anticipated events. Chief executive body designated to manage a nuclear power plant during major events is the emergency committee (EC). Emergency Committee is a part of the Emergency Response Organization (ERO). The following centers are on alert to ensure the activities of the ERO - Emergency Response office: - control room (CR) and emergency control room (ECR); - emergency management center (EMC); - Monitoring Centre (MC); - emergency backup control center (EBCC); - congregations of civil protection (CP) and CP shelters; - communications with warning and notification system (VARVYR). From a historical and practical point of view in the vicinity of Jaslovske Bohunice has been set up a joint emergency control center. The center was located on the territory of the former already inoperative V1 NPP. V1 NPP is currently integrated into the organizational structure of JAVYS. Operating Bohunice V2 NPP plant is a designated part of the Slovenske Elektrarne, a. s., whose majority owner is an Italian operator ENEL. In terms of various relevant factors, it was decided to build a new emergency management center on the territory of operating V2 NPP, meet the current standards.

  11. NPP Krsko secondary side analysis

    International Nuclear Information System (INIS)

    Fabijan, Lj.

    1987-01-01

    The purpose of this work is to analyze secondary side thermohydraulics response on steam generator tube plugging in order to ensure nominal NPP power. We had established that the additional opening of the governing valve No. 3 and 4 can compensate pressure drop caused by steam generator tube plugging. Two main steam flows with four governing valves were simulated. Steam expansion in turbine and feed water system was modeled separately. All important process point and steam moisture changes impact on nominal NPP power were analysed. (author)

  12. Life cycle assessment applied to nanomaterials in solid waste management

    DEFF Research Database (Denmark)

    Laurent, Alexis

    While the generation of solid waste is globally increasing, much effort is concentrated to minimise the environmental impacts related to their management. With respect to nanoproducts (products containing nanomaterials), a growing amount of ‘nanowaste’ can be expected to enter the waste streams...... on specific waste types and waste management systems, all primarily reflecting situations in economicallydeveloped countries. At the same time, methodological practice was found in many studies not to be compliant with current reference guidance, such as the ISO standards and the ILCD Handbook. Likewise......, thus potentially posing problems on human health, e.g. through occupational exposure to engineered nanoparticles. In that setting, through its holistic quantification of environmental impacts, life cycle assessment (LCA) can be a useful decisionsupport tool for managing environmental sustainability...

  13. Was Project Management Life Really Better in Apollo?

    Science.gov (United States)

    2010-01-01

    This slide presentation discusses the question of "Was Project Management Life Really Better in Apollo?" Was money really flowing freely all through Apollo? Are we wallowing in nostalgia and comparing current circumstances to a managerial time which did not exist? This talk discusses these and other questions as background for you as today s project managers. There are slides showing the timelines from before the speech that Kennedy gave promising to land a man on the moon, to the early 60's, when the manned space center prepared the preliminary lunar landing mission design, an NASA organization chart from 1970, various photos of the rockets, and the astronauts are presented. The next slides discuss the budgets from the 1960's to the early 1970's. Also the results of a survey of 62 managers, who were asked "What problems pose the greatest obstacles to successful project performance?"

  14. Animosity, antagonism, and avatars: teaching conflict management in second life.

    Science.gov (United States)

    Evans, Dena A; Curtis, Anthony R

    2011-11-01

    Conflict exists in all health care organizations and may take many forms, including lateral or horizontal violence. The Essentials of Baccalaureate Nursing Education identified the development of conflict resolution strategies as core knowledge required of the bachelor's of science in nursing generalist. However, learning the art of conflict management takes both time and practice. With competition for clinical space increasing, class time in short supply, and traditional clinical opportunities for teaching conflict management lacking, a virtual approach to teaching conflict resolution was explored through the use of Second Life®. The project presented here explored students' perceptions of this unique approach to learning conflict management and sought to examine the effectiveness of this teaching method. Copyright 2011, SLACK Incorporated.

  15. Plant life management optimized utilization of existing nuclear power plants

    International Nuclear Information System (INIS)

    Watzinger, H.; Erve, M.

    1999-01-01

    For safe, reliable and economical nuclear power generation 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. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

  16. Institutional disposition and management of end-of-life electronics.

    Science.gov (United States)

    Babbitt, Callie W; Williams, Eric; Kahhat, Ramzy

    2011-06-15

    Institutions both public and private face a challenge to develop policies to manage purchase, use, and disposal of electronics. Environmental considerations play an increasing role in addition to traditional factors of cost, performance and security. Characterizing current disposition practices for end-of-life electronics is a key step in developing policies that prevent negative environmental and health impacts while maximizing potential for positive social and economic benefits though reuse. To provide a baseline, we develop the first characterization of quantity, value, disposition, and flows of end-of-life electronics at a major U.S. educational institution. Results of the empirical study indicate that most end-of-first-life electronics were resold through public auction to individuals and small companies who refurbish working equipment for resale or sell unusable products for reclamation of scrap metal. Desktop and laptop computers sold for refurbishing and resale averaged U.S. $20-100 per unit, with computers sold directly to individuals for reuse reaching $250-350 per unit. This detailed assessment was coupled with a benchmarking survey of end-of-life electronics management practices at other U.S. universities. Survey results indicate that while auctions are still commonplace, an increasing number of institutions are responding to environmental concerns by creating partnerships with local recycling and resale entities and mandating domestic recycling. We use the analyses of current disposition practices as input to discuss institutional strategies for managing electronics. One key issue is the tension between benefits of used equipment sales, in terms of income for the institution and increased reuse for society, and the environmental risks because of unknown downstream practices.

  17. Blending of Low-Level Radioactive Waste for NPP Decommissioning

    International Nuclear Information System (INIS)

    Kessel, David S.; Kim, Chang Lak

    2016-01-01

    Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes

  18. Blending of Low-Level Radioactive Waste for NPP Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Kessel, David S.; Kim, Chang Lak [KEPCO, Ulsan (Korea, Republic of)

    2016-05-15

    Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes.

  19. The installation of a modern training facility for the Kalinin NPP

    International Nuclear Information System (INIS)

    Parfenov, A.; Gronau, D.; Birnie, S.

    1996-01-01

    Kalinin NPP Management has initiated an ambitious programme of improvements to its overall training commitment. With the assistance of the consultancy services provided by Siemens, it is planned to realize this programme in terms of training and training premises conforming to the stated goal of the NPP Management, on a timescale only made possible by adopting a pragmatic approach to the systematic approach to training. 1 ref

  20. 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)

  1. Forsmark NPP I and C modernization strategy

    International Nuclear Information System (INIS)

    Hallen, J.; Rydahl, I.; Kloow, L.

    2003-01-01

    By the year 2000, the Forsmark NPP was halfway through the planned plant life. As early as 1995, Forsmark realized that the old analog I and C equipment would need to be replaced before 2005. At the Forsmark NPP they had strength of a vision of an integrated modernization and a strategy to reach the vision. Without vision and strategy, the plant could end up with a fragmented plant I and C-architecture that is not cost-effective or operable. This paper will address several questions that led to the current modernization program in Forsmark, the more important questions are: What would happen if the modernization would be postponed? Which main requirements were to be achieved by means of the modernization strategy? The goal of a completed plant modernization program is a totally integrated system solution and what factors were considered during the modernization? How to gain acceptance from the operational staff in designing Control Room and Soft Control Displays? What are the important roles for the staff and organization to reach the end goal? What has been the experience to date and what are the lessons learned? Thanks to the long term co-operation between Forsmark and Westinghouse the modernization has been very successful for both parties. (orig.)

  2. Equipment Reliability Process in Krsko NPP

    International Nuclear Information System (INIS)

    Gluhak, M.

    2016-01-01

    To ensure long-term safe and reliable plant operation, equipment operability and availability must also be ensured by setting a group of processes to be established within the nuclear power plant. Equipment reliability process represents the integration and coordination of important equipment reliability activities into one process, which enables equipment performance and condition monitoring, preventive maintenance activities development, implementation and optimization, continuous improvement of the processes and long term planning. The initiative for introducing systematic approach for equipment reliability assuring came from US nuclear industry guided by INPO (Institute of Nuclear Power Operations) and by participation of several US nuclear utilities. As a result of the initiative, first edition of INPO document AP-913, 'Equipment Reliability Process Description' was issued and it became a basic document for implementation of equipment reliability process for the whole nuclear industry. The scope of equipment reliability process in Krsko NPP consists of following programs: equipment criticality classification, preventive maintenance program, corrective action program, system health reports and long-term investment plan. By implementation, supervision and continuous improvement of those programs, guided by more than thirty years of operating experience, Krsko NPP will continue to be on a track of safe and reliable operation until the end of prolonged life time. (author).

  3. Performance improvement: an active life cycle product management

    Science.gov (United States)

    Cucchiella, Federica; Gastaldi, Massimo; Lenny Koh, S. C.

    2010-03-01

    The management of the supply chain has gained importance in many manufacturing firms. Operational flexibility can be considered a crucial weapon to increase competitiveness in a turbulent marketplace. It reflects the ability of a firm to properly and rapidly respond to a variable and dynamic environment. For the firm operating in a fashion sector, the management of the supply chain is even more complex because the product life cycle is shorter than that of the firm operating in a non-fashion sector. The increase of firm flexibility level can be reached through the application of the real option theory inside the firm network. In fact, real option may increase the project value by allowing managers to more efficiently direct the production. The real option application usually analysed in literature does not take into account that the demands of products are well-defined by the product life cycle. Working on a fashion sector, the life cycle pattern is even more relevant because of an expected demand that grows according to a constant rate that does not capture the demand dynamics of the underlying fashion goods. Thus, the primary research objective of this article is to develop a model useful for the management of investments in a supply chain operating in a fashion sector where the system complexity is increased by the low level of unpredictability and stability that is proper of the mood phenomenon. Moreover, unlike the traditional model, a real option framework is presented here that considers fashion product characterised by uncertain stages of the production cycle.

  4. 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

  5. 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)

  6. How drug life-cycle management patent strategies may impact formulary management.

    Science.gov (United States)

    Berger, Jan; Dunn, Jeffrey D; Johnson, Margaret M; Karst, Kurt R; Shear, W Chad

    2016-10-01

    Drug manufacturers may employ various life-cycle management patent strategies, which may impact managed care decision making regarding formulary planning and management strategies when single-source, branded oral pharmaceutical products move to generic status. Passage of the Hatch-Waxman Act enabled more rapid access to generic medications through the abbreviated new drug application process. Patent expirations of small-molecule medications and approvals of generic versions have led to substantial cost savings for health plans, government programs, insurers, pharmacy benefits managers, and their customers. However, considering that the cost of developing a single medication is estimated at $2.6 billion (2013 dollars), pharmaceutical patent protection enables companies to recoup investments, creating an incentive for innovation. Under current law, patent protection holds for 20 years from time of patent filing, although much of this time is spent in product development and regulatory review, leaving an effective remaining patent life of 7 to 10 years at the time of approval. To extend the product life cycle, drug manufacturers may develop variations of originator products and file for patents on isomers, metabolites, prodrugs, new drug formulations (eg, extended-release versions), and fixed-dose combinations. These additional patents and the complexities surrounding the timing of generic availability create challenges for managed care stakeholders attempting to gauge when generics may enter the market. An understanding of pharmaceutical patents and how intellectual property protection may be extended would benefit managed care stakeholders and help inform decisions regarding benefit management.

  7. Life cycle cost and risk estimation of environmental management options

    International Nuclear Information System (INIS)

    Shropshire, D.; Sherick, M.

    1996-01-01

    The evaluation process is demonstrated in this paper through comparative analysis of two alternative scenarios identified for the management of the alpha-contaminated fixed low-level waste currently stored at INEL. These two scenarios, the Base Case and the Delay Case, are realistic and based on actual data, but are not intended to exactly match actual plans currently being developed at INEL. Life cycle cost estimates were developed for both scenarios using the System Cost Model; resulting costs are presented and compared. Life cycle costs are shown as a function of time and also aggregated by pretreatment, treatment, storage, and disposal activities. Although there are some short-term cost savings for the Delay Case, cumulative life cycle costs eventually become much higher than costs for the Base Case over the same period of time, due mainly to the storage and repackaging necessary to accommodate the longer Delay Case schedule. Life cycle risk estimates were prepared using a new risk analysis method adapted to the System Cost Model architecture for automated, systematic cost/risk applications. Relative risk summaries are presented for both scenarios as a function of time and also aggregated by pretreatment, treatment, storage, and disposal activities. Relative risk of the Delay Case is shown to be higher than that of the Base Case. Finally, risk and cost results are combined to show how the collective information can be used to help identify opportunities for risk or cost reduction and highlight areas where risk reduction can be achieved most economically

  8. Disposal of spent nuclear fuel from NPP Krsko

    International Nuclear Information System (INIS)

    Mele, I.

    2004-01-01

    In order to get a clear view of the future liabilities of Slovenia and Croatia regarding the long term management of radioactive waste and spent nuclear fuel produced by the NPP Krsko, an estimation of disposal cost for low and intermediate level waste (LILW) as well as for spent nuclear fuel is needed. This cost estimation represents the basis for defining the target value for the financial resources to be accrued by the two national decommissioning and waste disposal funds, as determined in the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko from March 2003, and for specifying their financial strategies. The one and only record of the NPP Krsko spent fuel disposal costs was made in the NPP Krsko Decommissioning Plan from 1996 [1]. As a result of incomplete input data, the above SF disposal cost estimate does not incorporate all cost elements. A new cost estimation was required in the process of preparation of the Joint Decommissioning and Waste Management Programme according to the provisions of the above mentioned agreement between Slovenia and Croatia. The basic presumptions and reference scenario for the disposal of spent nuclear fuel on which the cost estimation is based, as well as the applied methodology and results of cost estimation, are presented in this paper. Alternatives to the reference scenario and open questions which need to be resolved before the relevant final decision is taken, are also briefly discussed. (author)

  9. Achieving zero fuel failure rates at Armenian NPP

    International Nuclear Information System (INIS)

    Muradyan, T.

    2015-01-01

    In spite of the zero fuel failure rates in Armenian NPP there is a continued high level of interest. The generally accepted goal of achieving a zero failure rate requires detailed knowledge of existing failure mechanisms, their root causes and remedies. In this paper the foreign material management; water-chemistry regime; refuel machine management system and the transition into the use of vibration proof fuel of average enrichment 3,82% are presented

  10. Corrective action program at Krsko NPP

    Energy Technology Data Exchange (ETDEWEB)

    Skaler, F; Divjak, G; Kavsek, D [NPP Krsko, Krsko (Slovenia)

    2004-07-01

    The Krsko NPP develops software that enables electronic reporting of all kind of deviations and suggestions for improvement at the plant. All the employees and permanent subcontractors have the access to the system and can report deviations. NPP has centralized decision process for the distribution of reported deviation. At this point all direct actions are electronically tracked. The immediate benefits of this new tool were: Reporting threshold has been lowered; Number of reporting people has increased; One computerized form for all processes; Decision, which process will solve the deviation, is centralized; All types of deviation are in the same environment; Our experiences of the processes are incorporated in the program; Control of work that has been done; Archiving is electronic only. Software basic data: Application system Corrective action program is a WEB application. Data is stored in Oracle 8.1.7 i database. Users access application through PL/SQL gateway on Oracle 9i Application Server 1.0.2. using Microsoft Internet Explorer browsers(Version 5 or later). Reports are implemented by Oracle Reports 6i. Menus are designed by Apycom Java Menus and Buttons v4.23. Our Presentation will include: Basic idea; Implementation change management; Demonstration of the program.(author)

  11. Brief Assessment of Krsko NPP Decommissioning Costs

    International Nuclear Information System (INIS)

    Skanata, D.; Medakovic, S.; Debrecin, N.

    2000-01-01

    The first part of the paper gives a brief description of decommissioning scenarios and models of financing the decommissioning of NPPs. The second part contains a review of decommissioning costs for certain PWR plants with a brief description of methods used for that purpose. The third part of the paper the authors dedicated to the assessment of decommissioning costs for Krsko NPP. It does not deal with ownership relations and obligations ensuing from them. It starts from the simple point that decommissioning is an structure of the decommissioning fund is composed of three basic cost items of which the first refers to radioactive waste management, the second to storage and disposal of the spent nuclear fuel and the third to decommissioning itself. The assessment belongs to the category of preliminary activities and as such has a limited scope and meaning. Nevertheless, the authors believe that it offers a useful insight into the basic costs that will burden the decommissioning fund of Krsko NPP. (author)

  12. Corrective action program at Krsko NPP

    International Nuclear Information System (INIS)

    Skaler, F.; Divjak, G.; Kavsek, D.

    2004-01-01

    The Krsko NPP develops software that enables electronic reporting of all kind of deviations and suggestions for improvement at the plant. All the employees and permanent subcontractors have the access to the system and can report deviations. NPP has centralized decision process for the distribution of reported deviation. At this point all direct actions are electronically tracked. The immediate benefits of this new tool were: Reporting threshold has been lowered; Number of reporting people has increased; One computerized form for all processes; Decision, which process will solve the deviation, is centralized; All types of deviation are in the same environment; Our experiences of the processes are incorporated in the program; Control of work that has been done; Archiving is electronic only. Software basic data: Application system Corrective action program is a WEB application. Data is stored in Oracle 8.1.7 i database. Users access application through PL/SQL gateway on Oracle 9i Application Server 1.0.2. using Microsoft Internet Explorer browsers(Version 5 or later). Reports are implemented by Oracle Reports 6i. Menus are designed by Apycom Java Menus and Buttons v4.23. Our Presentation will include: Basic idea; Implementation change management; Demonstration of the program.(author)

  13. 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

  14. 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

  15. 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

  16. New challenges for Life Sciences flight project management

    Science.gov (United States)

    Huntoon, C. L.

    1999-01-01

    Scientists have conducted studies involving human spaceflight crews for over three decades. These studies have progressed from simple observations before and after each flight to sophisticated experiments during flights of several weeks up to several months. The findings from these experiments are available in the scientific literature. Management of these flight experiments has grown into a system fashioned from the Apollo Program style, focusing on budgeting, scheduling and allocation of human and material resources. While these areas remain important to the future, the International Space Station (ISS) requires that the Life Sciences spaceflight experiments expand the existing project management methodology. The use of telescience with state-the-art information technology and the multi-national crews and investigators challenges the former management processes. Actually conducting experiments on board the ISS will be an enormous undertaking and International Agreements and Working Groups will be essential in giving guidance to the flight project management Teams forged in this matrix environment must be competent to make decisions and qualified to work with the array of engineers, scientists, and the spaceflight crews. In order to undertake this complex task, data systems not previously used for these purposes must be adapted so that the investigators and the project management personnel can all share in important information as soon as it is available. The utilization of telescience and distributed experiment operations will allow the investigator to remain involved in their experiment as well as to understand the numerous issues faced by other elements of the program The complexity in formation and management of project teams will be a new kind of challenge for international science programs. Meeting that challenge is essential to assure success of the International Space Station as a laboratory in space.

  17. [A Medical Devices Management Information System Supporting Full Life-Cycle Process Management].

    Science.gov (United States)

    Tang, Guoping; Hu, Liang

    2015-07-01

    Medical equipments are essential supplies to carry out medical work. How to ensure the safety and reliability of the medical equipments in diagnosis, and reduce procurement and maintenance costs is a topic of concern to everyone. In this paper, product lifecycle management (PLM) and enterprise resource planning (ERP) are cited to establish a lifecycle management information system. Through integrative and analysis of the various stages of the relevant data in life-cycle, it can ensure safety and reliability of medical equipments in the operation and provide the convincing data for meticulous management.

  18. Automated personal dosimetry monitoring system for NPP

    International Nuclear Information System (INIS)

    Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D.

    2006-01-01

    Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using thermoluminescent

  19. Effects of stress management training and problem solving on quality of life and life expectancy among infertile women

    Directory of Open Access Journals (Sweden)

    Mohammad Reza Zarbakhsh Bahri

    2013-08-01

    Full Text Available Introduction: This study aims to evaluate the effectiveness of stress management training and problem-solving training on quality of life and life expectancy of infertile women was conducted.Material and Methods: The method of this study was experimental with pretest – posttest design with a control group. population of 400 infertile women who referred to infertility center in Rasht were randomized to 250 of them were selected and the quality of life and life expectancy of the study were the 45 members of the quality of life and life expectancy lower were more randomly in three groups of 15 people, including two experimental groups and one control group were replaced. Each experimental groups were trained for 10 sessions of 90 minutes, respectively, stress management and problem-solving. Upon completion of the training program, participants were assessed again.Results: The result of present study showed that there was a significant difference between the experimental groups and control group in the scores of quality of life and life expectancy (p0.05.Conclusion: Stress management and problem solving training were effective on life expectancy and quality of life of infertile women but there was no significant difference between the effectiveness of these two methods on life expectancy and quality of life of infertile women.

  20. 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