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Sample records for cernavoda npp training

  1. Overview of Cernavoda NPP training programme

    International Nuclear Information System (INIS)

    Valache, Cornelia

    2005-01-01

    Full text: The paper presents a general assessment of Cernavoda NPP personnel training programme, highlighting the role of training in human performance improvement. Cernavoda NPP Personnel Training and Authorization Department (PTAD) is the one responsible for the training of Unit 1 and 2 staff. PTAD is structured in such a manner as to support and respond to all Cernavoda NPP training, qualification and authorization requirements. The training of personnel is continuously adapted based on IAEA Guides and INPO/WANO recommendations, to keep with world standards, based on the internal and external reviews. At Cernavoda NPP the Training Concept and the Training Programmes are based on SAT - Systematic Approach to Training. The Training Concept is established on a set of training documents (RD's, SI's, IDP's), which address all the SAT phases: Analysis, Design, Development, Implementation and Evaluation. The Training Programmes are structured on the initial and continuing personnel training. Their content and goals respond to the training specific needs for each plant major job family. In order to successfully support NPP training programmes, CNPP training center has upgraded classrooms with new presentation facilities and there are plans to expand the space of the building, to develop additional operator and maintenance skills facilities. There are also a number of general areas for improvement of PTAD activity, such as operators and maintenance training, initial and continuing training of both Unit 1 and 2 staff. By responding in a timely and completely manner to all plant training requirements PTAD will help in rising human performance of Cernavoda NPP personnel, supporting the safe, efficient and cost effective production of power. (author)

  2. Full scope simulator commissioning and training experience at Cernavoda NPP

    International Nuclear Information System (INIS)

    Balan, M.

    2000-01-01

    The paper presents the experience gained during commissioning and the initial use of the CANDU training full-scope simulator for operation personnel at Cernavoda NPP. The full-scope simulator as an integral part of the training programs that take place in Cernavoda Nuclear Training Department (CNTD), is mainly used for the development of operational skills, knowledge and attitudes required to operate the plant in a safe and efficient manner. (author)

  3. Training needs analysis at Cernavoda NPP - Romania

    International Nuclear Information System (INIS)

    Georgescu, L.M.

    2002-01-01

    The paper is mainly on training needs analysis applied at Cernavoda NPP and will outline the Cernavoda (CNPP) approach in establishing what kind of training is necessary for CNPP employees, from the moment they are hired until they become qualified. The training methodology adapted at CNPP is one which adheres to the principles of the Systematic Approach to Training (SAT). SAT adoption at CNPP provides a broad integrated approach emphasizing not only technical knowledge and skills but also human factors knowledge, skills and attitudes. The analysis of SAT at CNPP consists of a 'table-top' analysis of training and qualification requirements. This paper will illustrate how a 'table-top' analysis by Subject Matter Experts is organized, carried out and recorded, and which categories of staff have begun this table-top analysis at CNPP. It will also give an example how this analysis is done: how the tasks of each job are rated, which are the used criteria, and how to proceed with the incorporation of the tasks into initial and continuing training, as appropriate. (author)

  4. Training change control process at Cernavoda NPP

    International Nuclear Information System (INIS)

    Valache, Cornelia Mariana

    2005-01-01

    The paper presents the process of 'Training Change Control' at Cernavoda NPP. This process is a systematic approach that allows determination of the most effective training and/or non-training solutions for challenges that may influence the content and conditions for a training program or course. Changes may be the result of: - response to station systems or equipment modifications; - new or revised procedures; - regulatory requirements; - external organizations requirements; - internal evaluations meaning feedback from trainees, trainers, management or post-training evaluations; - self-assessments; - station condition reports; - operating experience (OPEX); - modifications of job scope; - management input. The Training Change Control Process at Cernavoda NPP includes the following aspects. The first step is the identification of all the initiating factors for a potential training change. Then, retain only those, which could have an impact on training and classify them in two categories: as deficiencies or as enhancement suggestions. The process is different for the two categories. The deficiency category supposes the application of the Training Needs Analysis (TNA) process. This is a performance-oriented process, resulting in more competent employees, solving existing and potential performance problems. By using needs analysis to systematically determine what people or courses and programs are expected to do and gathering data to reveal what they are really doing, we can receive a clear picture of the problem and then we can establish corrective action plans to fix it. The process is supported by plant subjects matter and by training specialists. On the other hand, enhancements suggestions are assessed by designated experienced persons and then are implemented in the training process. Regarding these two types of initiating factors for the training change control process, the final result consists of a training improvement, raising the effectiveness, efficiency or

  5. Operator refresher training and requalification at Cernavoda NPP

    International Nuclear Information System (INIS)

    Timoftei, D.

    2002-01-01

    The paper presents the Operator's training program for refresher and requalification purposes, which were developed using the CANDU training full-scope simulator at Cernavoda NPP. First the purpose of both programs is described, and then more details on how these programs are delivered are given. The Refresher Training Program, part of the Operator Continuing Training Program, and the Requalification Training Program are periodically training given to the previously authorised operating personnel. The training and the evaluation are conducted both on an individual and on the team basis. Both programs are tailored according with Systematic Approach to Training concept. In addition to that the importance of the training on simulator arises from the fact that the training is mostly related to plant transients/accidents that in real life may never happens, but the operators should be always prepared for the worst. Continuing Training Program (CTP) applies to the authorized positions of Shift Supervisor (SS) and Control Room Operator (CRO) at CNE-PROD Cernavoda. Also, the program is establishing the criteria and the process, which will allow the authorised SS and CRO to maintain their authorised status. (author)

  6. 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)

  7. 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

  8. Experience in the application of S.A.T. for maintenance training at Cernavoda N.P.P. - U1

    International Nuclear Information System (INIS)

    Erdinici, Abdula

    1999-01-01

    A short history of Maintenance Training at Cernavoda NPP Unit 1 will be presented highlighting the fact that: - Cernavoda NPP Unit 1 is the first nuclear power plant in Romania; - Construction/Commissioning and initial operation was done under the direct supervision of expert specialists (from Canada, Italy and US). In addition, the application of Systematic Approach to Training (S.A.T.) principles at Cernavoda NPP for all training activities will be addressed. A short history of how maintenance training activity developed over time will be detailed to address the following issues: - how the S.A.T. stages were applied; - how maintenance experience was gained during Unit 1 Construction/Commissioning initial operation and how this experience has been evaluated, credited and transferred; - how maintenance training was documented; - how the maintenance training activity is organized; - on-the-job training for maintenance personnel. Concerning other training activities at Cernavoda NPP the maintenance begins with a training needs analysis for each maintenance position. These needs are documented through Job Related Training requirements (JRTR's) produced for each maintenance position. During commissioning/initial operation, only necessary maintenance training has been delivered, such as: pump alignments, use of maintenance procedure, application of maintenance documentation. The 'hands-on' activities under expatriates specialists supervision was the main training activity. Training coordinators for each maintenance activity (Mechanical, EI. I-and-C, and Services maintenance) have been appointed to administer maintenance training. Following the declaration of the unit in commercial operation, a new approach has been taken related to maintenance Bucharest A Task Force to evaluate maintenance training status and experience has been established. This group was initiated at the Training Department initiative and it was initially co-ordinated by a Canadian maintenance

  9. Cernavoda NPP simulator - next generation

    International Nuclear Information System (INIS)

    Tatar, F.; Ionescu, T.; Dascalu, M.

    2003-01-01

    Demand for extending the amount of training and scope for Cernavoda Unit 1 as well as the new trend in the simulator owners world, led to a change in the Romanian philosophy of simulator specification. Up to now the training was conducted on a Full Scope simulator, a 1:1 replica of Cernavoda Unit 1 reference plant. The present task is to define the simulation facilities and structure capable to meet the requirements for training, qualification and licensing of personnel for both Cernavoda Unit 1 and Unit 2. Obviously, the Cernavoda Unit 2 belongs to the same technological family but has rather different control room layout. Since this target requires a new simulator the costs would be rather high in accordance to the degree of automation of Cernavoda NPP. Therefore, depending on training requirements and financing, the Cernavoda Unit 1 simulator modernization, which also provides an alternative to full scope control room simulator, may be a viable option. Therefore the solution that with discuss for Cernavoda training extension is the migration of Cernavoda Unit 1 simulator to state-of-the-art. Consequently, the Cernavoda Unit 1 simulator modernization task will be organized as project including the following major items: 1. Rehost existing U1 simulation software from VAX 4500 to: - Best commercial multi-processor server for simulation server (HP, O/S Linux); - Best commercial single processor PC for I/O communications (HP, O/S Linux); 2. Replace DCC with enhanced emulated version: Best commercial individual PC for DCC emulation (HP, O/S Windows); Support for actual keyboards; Replacement of RAMTEK System and CONRAC Monitors with X terminals or PC's; 3. Conversion of AutoCAD-based panel graphic pages to RAVE-based; 4. Install the required software tools for developing enhanced simulation modules; 5. Replace the simulation modules with advanced modules; 6. Replace the present Windows Instructor Facilities with ISIS; 7. Development of a selection of MCR-U1 virtual

  10. Cernavoda NPP operations training programs

    International Nuclear Information System (INIS)

    1993-01-01

    The purpose of this document is to describe the philosophy, content and minimum requirements for the Cernavoda Training Programs for all Station staff and to identify the training department organization and respective responsibilities necessary to provide the required training. The hierarchical documentation and requirements related to these programs is shown in figure Rd-TR1-1

  11. Results and development prospects for the Cernavoda NPP

    International Nuclear Information System (INIS)

    Rotaru, Ioan

    2001-01-01

    The new competitive market in the power sector offers favorable conditions for continual developing of Nuclear Power in Romania. The principal arguments in this respect are: the CANDU technology is a western technology recognized world wide both for its operation reliability and its economical performances. The results obtained by Cernavoda NPP Unit 1 over a period of four years and a half commercial operation confirms the validity of the CANDU project in Romania in the new conditions of competitive market. Accomplishing the Unit 2 of Cernavoda NPP represents for the time being one of the most cost-effective investment in the Romanian power sector. Also, the participation of the local industry to the project implementation is important as it ensures the initial heavy water and nuclear fuel charging, specific materials and equipment production, design and construction works, etc. Heaving in view all these favorable arguments, the construction of Unit 2 of Cernavoda NPP represents one of the highest priorities of the State Budget of the present administration in year 2001. The Nuclear Power Project in Romania, based on CANDU technology meets national as well as EU regulations concerning nuclear power and as such its development poses no significant problems both in the context of EU extension and in the frame of the developing competitive market in the power sector. For SNN SA the main objectives in view for the next stage are: operating Cernavoda NPP Unit 1 in conditions of highest nuclear safety and economical efficiency; finalizing the Cernavoda NPP Unit 2 and creation of an organisation for operating the two units; promoting of a functional system characteristic to the competitive market economy and open to privatization; creating opportunities for exporting electrical energy. The contribution contains the following sections: 1. General overlook; 2. Performance of the power production in the year 2000; 2.1. Unit 1 of Cernavoda NPP; 2.2. Nuclear Fuel Plant

  12. Cernavoda NPP impact study on terrestrial and aquatic biota. Preliminary results

    International Nuclear Information System (INIS)

    Bobric, Elena; Bucur, Cristina; Popescu, Ion; Simionov, Vasile; Titescu, Gheorghe; Varlam, Carmen

    2010-01-01

    Recently, the awareness of the vulnerability of the environment has increased and the need to protect it against industrial pollutants has been recognized. The concept of sustainable development, requires new and developing international policies for environmental protection. See 'Protection of the environment from the effects of ionizing radiation' IAEA-TECDOC-1091, International Atomic Energy Agency, Vienna. As it is recommended in 'Cernavoda Unit No. 2 NPP Environmental Impact Assessment CES-03702-IAD-006', it is Cernavoda NPP responsibility to conduct an Ecological Risk Assessment study, mainly to assess the impact of nuclear power plant operation on terrestrial and aquatic biota. Long records from normal operation of Cernavoda Unit 1, wind pattern, meteorological conditions, and source terms data were used to evaluate areas of interest for environmental impact, conducting to a circle of 20 km radius around mentioned nuclear objective. The screening campaign established tritium level (because Cernavoda NPP is a CANDU type reactor, and tritium is the most important radioisotope evacuated in the environment) in air, water, soil and vegetation, focusing the interest area on particular ecosystem. Using these primary data it was evaluated which are the monitored ecological receptors and which are the measurement endpoints.This paper presents the Ecological Risk Assessment at Cernavoda NPP technical requirements, and the preliminary results of evaluating criteria for representative ecosystem components at Cernavoda NPP. (authors)

  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. Radiological impact on the surrounding area of Cernavoda NPP operation

    International Nuclear Information System (INIS)

    Busnita, M.; Penescu, M.; Neacsu, L.; Ion, M.; Moldoveanu, E.

    1996-01-01

    The objective of this paper is to present the protective measures provided to Cernavoda NPP for population and environment in case of normal operation and accidental situations. The paper describes the nuclear safety concept with the two aspects, the technical safety and the radiation protection, respectively, which represent the theoretical basis of the NPP design, construction and operation. The assessment of the potential radiological effects of Cernavoda NPP operation on the population and other environmental factors have been done by using the following input data: the natural and social characteristics of the site and the technical characteristics of the plant. The effects of Cernavoda NPP operation are also exposed in health risks which are compared with the daily risks of the population exposed of the natural phenomena or to the activities like transportation, domestics or industrial. (author). 1 tab., 6 refs

  15. 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)

  16. 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)

  17. 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)

  18. 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

  19. 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.

  20. The contract for the completion and commissioning of Cernavoda NPP - Unit

    International Nuclear Information System (INIS)

    2001-01-01

    On May 18, 2001 the commercial contract for the completion and commissioning of the Cernavoda NPP Unit 2 has been signed by Nuclearelectrica National Company (SNN SA) and its partners, AECL-Canada and ANSALDO-Italy. This contract represents a continuation of the cooperation with AECL-Canada (the owner of the licence and the designer of the nuclear part of Cernavoda NPP Unit1) and ANSALDO-Italy (the designer of the conventional part of Cernavoda NPP Unit1). The completion is scheduled to last for 54 months (4.5 years) since the date the contract takes effect and the nuclear reactor start-up (the first criticality) is scheduled for the 49 th month. The total negotiated cost for the completion was estimated to amount to 689 million dollars, against the 750 million dollars initially estimated. The works at the site will be managed by an integrated staff team of specialized personnel form AECL-Canada (111 positions), ANSALDO-Italy (72 positions) and Romania (1200 positions)

  1. Cernavoda NPP Unit 1 - a plant of several generations

    International Nuclear Information System (INIS)

    Rotaru, I.; Metes, M.; Anghelescu, M.S.

    2001-01-01

    The paper reflects some key aspects related to the shift of generations during the project's development, including the present stage. Further, the place of Cernavoda NPP Unit 1 in the Romanian power sector and among other nuclear stations in the world is presented. The operational performances achieved 'in service' up to the end of 1999, with reference to the performance indicators for electrical energy production, nuclear safety, radiation protection, radioactive wastes and nuclear fuel are illustrated. For all of these items, comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. Finally, some comments about Cernavoda NPP Unit 2 project status and need to completion and commissioning it are included. (authors)

  2. 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

  3. 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)

  4. Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

    International Nuclear Information System (INIS)

    Bobric, E.; Murgoci, S.; Popescu, I.; Ibadula, R.

    2001-01-01

    Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

  5. The influence of increased temperature of waters from Cernavoda NPP on underground water sources

    International Nuclear Information System (INIS)

    Isbasoiu, Eugen Constantin; Marinov, Anca Mariana; Moraru, Carina Nicoleta; Rizescu, Gheorghe

    1997-01-01

    The operation of Cernavoda NPP implies the change of thermal regime of waters in the Danube-Black Sea channel zone. The Danube water is used to cool the NPP systems before being delivered into channel and used in irrigations. The temperature increase of water in Cernavoda NPP installations is between 7 and 12 deg. C. The negative effects of this warming are: 1. limitation of water use for irrigations; 2. occurrence and persistence of fog in channel area; 3. thermal pollution of underground waters and limitation of underground potable water supply. The paper presents a general approach of thermal pollution problems of an aquifer and a mathematical model of forecasting the underground water temperature variation in Danube-Black Sea channel area. (authors)

  6. The environmental constraint needs for design improvements to the Saligny I/LLW-repository near Cernavoda NPP

    International Nuclear Information System (INIS)

    Barariu, Gheorghe

    2007-01-01

    The paper presents the new perspectives on the development of the L/ILW Final Repository Project which will be built near Cernavoda NPP. The Repository is designed to satisfy the main performance objectives in accordance to IAEA recommendation. Starting in October 1996, Romania became a country with an operating nuclear power plant. Reactor 2 reached the criticality on May 6, 2007 and it will be put in commercial operation in September 2007. The Ministry of Economy and Finance has decided to proceed with the commissioning of Units 3 and 4 of Cernavoda NPP till 2014. The Strategy for radioactive waste management was elaborated by National Agency for Radioactive Waste (ANDRAD), the jurisdictional authority for definitive disposal and the coordination of nuclear spent fuel and radioactive waste management (Order 844/2004) with attributions established by Governmental Decision (GO) 31/2006. The Strategy specifies the commissioning of the Saligny L/IL Radwaste Repository near Cernavoda NPP in 2014. When designing the L/IL Radwaste Repository, the following prerequisites have been taken into account: 1) Cernavoda NPP will be equipped with 4 Candu 6 units. 2) National Legislation in radwaste management will be reviewed and/or completed to harmonize with UE standards 3) The selected site is now in process of confirmation after a comprehensive set of interdisciplinary investigations. (author)

  7. 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)

  8. Public debates - key issue in the environmental licensing process for the completion of the Cernavoda NPP Unit 2

    International Nuclear Information System (INIS)

    Rotaru, Ioan; Jelev, Adrian

    2003-01-01

    SN 'NUCLEARELECTRICA' S.A., the owner of Cernavoda NPP, organized, in 2001, several public consultations related to environmental impact of the completion of the Cernavoda NPP Unit 2, as required by the Romanian environmental law, part of project approval. Public consultations on the environmental assessment for the completion of the Cernavoda NPP - Unit 2 took place in 2001 between August 15 and September 21 in accordance with the provisions of Law No. 137/95 and Order No. 125/96. Romanian environmental legislation, harmonization of national environmental legislation with European Union, Romanian legislative requirements, information distributed to the public, issues raised and follow-up, they all are topics highlighted by this paper and they are addressing the environmental licensing process of the Cernavoda 2 NPP. The public consultation process described fulfils all the Romanian requirements for carrying out meaningful consultation with its relevant shareholders. The process also satisfies EDC (Export Development Corporation - Canada) requirements for public consultation and disclosure with relevant shareholders in the host country. SNN is fully committed to consulting as necessary with relevant shareholders throughout the construction and operation of the Project. Concerns of the public have been taken into account with the operations of Unit 1 and will continue to be addressed during the Unit 2 Project

  9. Cernavoda NPP Unit 1 - a plant of several generations

    International Nuclear Information System (INIS)

    Rotaru, I.; Metes, M.; Anghelescu, M.S.

    2000-01-01

    Cernavoda NPP Unit 1, the first nuclear power unit in Romania, has a long and tormented history. It represents a rather unique case in Eastern Europe. The project started well before 1989 (the construction phase lasted 17 years and generations were involved in its completion), but it is effectively based on western technology (Candu). Meanwhile, the national nuclear program underwent many changes, affecting the lives and careers of Romanian nuclear professionals. Finally, on December 2 nd 1996, the unit began its c ommercial operation , being operated at its nominal power rating of 706 MW e . It now provides a reliable source of electricity for Romanian economy, supplying to the national grid about 10% of the country's average annual demand. The paper reflects some aspects related to the shift of generations during the project's development, including the present stage. The operational performances achieved 'in service' by Cernavoda NPP Unit 1 up to the end of 1999 , are also presented. Reference to the electrical energy production, performance indicators, production costs, nuclear safety, radiation protection, radioactive wastes, nuclear fuel consumption and nuclear fuel performances are included. Comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. (authors)

  10. Modelling the impact of Cernavoda NPP on the environment

    International Nuclear Information System (INIS)

    Constantin, A.-I.

    2001-01-01

    In connection with a stay as a visiting researcher at VTT Energy (Technical Research Center of Finland), a study was conducted related to the atmospheric dispersion and dose assessment for radioactive releases from nuclear power plants. The most important aspects of this study are described in this paper. These include: the application of the TRADOS dispersion and dose assessment model in the case of the Cernavoda NPP and the development of a special program INTEGRATION for the calculation of cloud gamma dose rate of 72 nuclides. (authors)

  11. ICEMENERG technologies of water treatment applied at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Stanca, Angela; Bolma, Aurelia; Serbanescu, Agnes; Raducanu, Alice

    2002-01-01

    The paper presents the ICEMENERG technologies for water treatment applied at Cernavoda Unit 1, the treatment of the additional water for power steam generators and the chemical treatment of cooling system water. The requirements for quality of water totally demineralized as imposed by the AECL-ANSALDO consortium are as following: electrical conductivity, < 0.2 mS/cm; total silicon, <0.02 mg/L; ionic silicon, <0.01 mg/L; sodium, < 0.05 mg/L; TOC, <0.300 mg/L. These requirements raise rather difficult problems to be solved because the raw water source in case of Cernavoda NPP is Danube River which presents a raising trend of organic and inorganic contamination. Accordingly, experiments at laboratory scale reproducing the entire technological flow were conducted. The following operations were studied: pretreatment with limewash, ferric chloride (with and without coagulation additives); demineralization with ion exchangers of Purolite and Amberlite types. The system consisted of a cationic stage, formed of an strongly acid step with countercurrent recovery and an anionic stage formed of two steps, namely, a weakly basic step and a strongly basic step with recovery inserted; finishing on mixed bed. The paper presents also the chemical treatment/conditioning of the cooling loop of turbine condenser. The Cernavoda NPP cooling system is an open system with a single flow of cooling water comprising two systems, namely, the circulation water system ensuring the steam condenser cooling and the servicing water system ensuring the cooling of heat exchangers in the recirculated water circuit (RCWS), the turbine oil coolants, the coolants of auxiliary steam as well as the emergency core cooling system. Studies were conducted to ensure the chemical conditioning of the raw water from Danube River, particularly, to destroy and remove the shells, the algae and other components. Finally, the following four steps of conditioning the water of the cooling system are summarized: 1

  12. The GMF (Group of European Municipalities with Nuclear Facilities) conference at Cernavoda. Opening talk

    International Nuclear Information System (INIS)

    Chirica, Teodor

    2006-01-01

    The conference 'Local Competence Building and Public Information in European Nuclear Territories', part of an European Commission project, took place at the Training Center of Cernavoda NPP, on 5-6 April, 2006. Organized by GMF with the support of the town hall and of the Cernavoda NPP, the manifestation gathered over 200 participants, among which representatives of the local public administration in Cernavoda, SN Nuclearelectrica SA, Ministry of Economy and Commerce, Nuclear Agency, CNCAN, ANDRAD, Local Communities and NGOs. The main topics of discussion was the collaboration relationship between local authorities and representatives of the plant regarding public safety and local development. The Mayor of Cernavoda, Gheorghe Hansa and the director of the NPP, Ionel Bucur, stressed that the location of the nuclear plant brings important contributions to the local budget, the socio-economical development of the area, ensuring jobs for most of the town's inhabitants. Speeches were given by Mr Gheorghe Hansa, Ms Blohm-Hieber, the director of the Transport and Energy Division from European Commission, and Mr Ionel Bucur who spoked about the relationship of the plant with the local community. Representatives from France, Slovenia, Sweden, Spain, Hungary and Romania shared their experience about 'The impact on the neighboring areas and the demands from the local authorities'. In his opening talk Mr Chirica Teodor, director general of SN Nuclearelectrica SA, showed that nuclear power in Romania has been based from its very inception on the Western safe technology, as reflected by the excellent safety an economical performances of Cernavoda NPP-Unit 1. Based on the long-term-commitment to nuclear power of the Romanian Government, the commercial operation of Cernavoda NPP Unit 2 is scheduled for the mid of 2007, and will supply 17-18% of the electricity production in Romania. The Romanian Government stressed his strong intention to complete Unit 3 and possibly Unit 4 at

  13. Financing Nuclear Projects. Case Study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, Teodor; Constantin, Carmencita; Dobrin, Marian

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) is a major undertaking for all entities involved, due to the necessity of planning work and coordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the public. Having in view the specific investment costs (relatively high) for a NPP, finding an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and secondly, the mathematical modelling of the financing structure effects on the projects. In this respect, the paper will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentation requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, purchase contract, etc). The case study will be focused on the phases achieved in order to promote the Unit 2 NPP Cernavoda completion works project. (authors)

  14. Financing nuclear projects. Case study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, T.; Pall, S.; Lebedev, A.; Dobrin, M.

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) in a country is a major undertaking for all entities involved, due to the necessity of planning work and co-ordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the people. Having in view the specific investment cost (relatively high) for a NPP, to find an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and second, the mathematical modelling of the financing structure effects on the project. In this respect, the paper proposed will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentations requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, power purchase contract, etc.) The case study will be focused on the phases achieved in order to promote the Unit 2 Cernavoda NPP completion works project. (author)

  15. Experimental determinations of the turbine condenser operation at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Romascu, Gabriel; Dragusin, Dumitru; Rogociu, Ioan; Macodean, Luminita; Marciulescu, George

    1999-01-01

    The condenser system represents one of the most important BOP (balance of plant) systems of the CANDU 700 MW Unit at Cernavoda NPP. The paper presents theoretical calculation elements, mathematical model for simulation of condenser operation and the results obtained by model implementation as compared to operation data. The model could be adapted to other turbine and operation regime types. (authors)

  16. Probabilistic safety assessment (Cernavoda). Experience and strategies

    International Nuclear Information System (INIS)

    Mircea, Mariana

    2000-01-01

    An IAEA project named 'Support for PSA related activities for Cernavoda NPP' was agreed at the beginning of 2000. The objectives were: upgrading of capability and framework to perform deterministic analyses as support for PSA (accident analyses and severe accident analyses); upgrading of capability and framework to extend the scope of PSA model for Cernavoda NPP to include internal and external hazards (internal fire, internal flooding, earthquake); upgrading of capability and framework to perform the Level 2 PSA for Cernavoda NPP. valuation was done for the status of the development of the seismic PSA, fire PSA and flooding PSA. For seismic PSA it was concluded by IAEA experts that this work needs adequate human and financial resources. Decision was taken to coordinate this project from Cernavoda but using specialists from external institutions. A Fire Hazard Assessment-FHA is in progress for Unit 1. First stage, regarding the methodology, was reviewed by IAEA experts in November 1999. In present, work is done for Reactor and Service Buildings. Work on flooding PSA was not started yet. To extend the PSA scope: Capability will be extended to develop the seismic PSA, fire PSA, flooding PSA (procurement of supplementary computer codes and specialist training); the extension of PSA scope to include internal and external hazards will continue after the completion of deterministic studies and is expected that the effective inclusion in the PSA model will start at the end of 2002

  17. Characterization of the solid radioactive waste from Cernavoda NPP

    International Nuclear Information System (INIS)

    Iordache, M.; Lautaru, V.; Bujoreanu, D.

    2005-01-01

    During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from each other. For a CANDU type reactor, the occurrence of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

  18. 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

  19. ALARA and radiation protection optimization status of Cernavoda NPP

    International Nuclear Information System (INIS)

    Hau, D.I.

    2000-01-01

    ALARA in Radiation Protection is specifically applied as a tool in lowering B the risk of high exposure when performing necessary activities by reducing the doses as much and as reasonably possible. Is ALARA also a matter of IMAGE? ALARA is one of the main aspects that contributes to forming the image of a certain facility. Many experiences in the world show a decrease in the collective dose per station after proper ALARA implementation. This trend is more relevant for 'adult' nuclear sites. At Cernavoda NPP the authorization process itself included implementation of an effective ALARA program. (author)

  20. Technical solutions for tritium removal from Cernavoda NPP heavy water systems

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Panait, Adrian

    2002-01-01

    In CANDU nuclear plants 2400 KCi/GW(e) - year tritium is generated. At a CANDU - 600 reactor similar to Cernavoda NPP Unit 1, 1500 KCi/year of tritium is generated 95% being in the D 2 O moderator, which can achieve a radioactivity level of 80 - 100 Ci/kg. Tritium in heavy water contributes with 30 - 50% to the doses received by operation personnel and with 20% to the radioactivity released to the environment. The extraction of tritium heavy water at CANDU reactors implies the following possibilities: - the radioactivity level reduction in the operation area; - the maintenance and repair cost reduction due to reduction of personnel protection measures and increased labor productivity; - the increase of NPP utilization factor by shutdown time reduction for maintenance and repair; - tritium concentration reduction from technological systems, ensuring thus the possibility of redesigning the systems in order to lower the cost of investment; - profitable use of extracted tritium. Technical measures provided by AECL project for CANDU 600 at Cernavoda make possible to satisfy the current standards concerning tritium concentration in the operation area atmosphere of 5 x 10 -6 Ci/m 3 . The regulations recommend that the radioactivity level should be maintained as low as possible in conformity with ALARA principles. Also, it is possible that norms will become more restrictive in the future, so the tritium removal technology is a good preventive measure which may become very necessary. The methods, which currently reached the industrial or pilot stages, are based on catalyzed chemical exchange, the heavy water electrolysis, and deuterium distillation. They are known as: VPCE - Vapour Phase Catalytic Exchange; LPCE - Liquid Phase Catalytic Exchange; DE - Direct Electrolysis; CD - Cryogenic Distillation. As transfer processes the catalyzed chemical exchange and heavy water electrolysis are used while concentration of tritium gas is done by cryogenic distillation. At present the

  1. Design configuration for Cernavoda - 2

    International Nuclear Information System (INIS)

    Lindsay, R.I.; Keil, H.; Hapwood, J.M.; Hum, J.

    1998-01-01

    The Cernavoda - 2 NPP project is based on a repeat of the recently completed plant, Cernavoda - 1 NPP which has been operating well, and the other CANDU 6 units in Canada, Argentina and Korea, which have had an excellent operating record. The reference plant design for Cernavoda - 2 is Cernavoda - 1 with appropriate design enhancements incorporating lessons learned from CANDU 6 and other nuclear operations, and including appropriate design enhancements from the most recent CANDU 6 projects at Wolsung in Korea, and Qinshan in China, while recognizing the significant degree of project completion. The results of this combination of proven design with systematic design feedback, will be a unit which combines reliability supported by the many years of successful operation of CANDU 6 units, together with a significant number of design enhancements. (authors)

  2. Characterization of the solid radioactive waste From Cernavoda NPP

    International Nuclear Information System (INIS)

    Iordache, M.; Laotaru, V.

    2005-01-01

    Full text: During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from which other. For a CANDU type reactor, the appearance of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

  3. NPP Cernavoda Unit 2 Financing Completion Works

    International Nuclear Information System (INIS)

    Chirica, T.; Stefanescu, A.; Constantin, C.; Dobrin, M.

    2002-01-01

    NPP Cernavoda Unit 2 completion is the highest priority of the Romanian power sector strategy. The nuclear energy represents, through its technological features of adopted solution (a CANDU nuclear power plant) and also through technological and economical performance indicators, the best solution to fulfill the demands concerning the sustainable development and the electricity request. The guidelines of energy strategy regarding the nuclear sector development in Romania are framing in the general policy for energy system development at least costs and they are responding to requests concerning the environment and people protection. The paper presents the financing alternatives for Unit 2 completion works taking into consideration the financing market conditions. The paper presents the impact of the financing conditions on the project efficiency, as well as the facilities offered by the Romanian Government in order to support this project. (author)

  4. Cernavoda power simulator modernization - A step forward in Romanian low cost maintenance simulation technology

    International Nuclear Information System (INIS)

    Bucur, I.; Tatar, F.; Ionescu, Teodor

    2004-01-01

    At Cernavoda NPP the training is conducted on a Full Scope Simulator, a 1:1 replica of Cernavoda Unit 1 reference plant. For the improvement of training delivery the current task is to define the simulation facilities and structure capable to meet the increased requirements for training, qualification and licensing of nuclear personnel. Besides, this upgrade of simulation facilities should be considered if we are addressing the task of extension of training for Cernavoda Unit 2. In order to achieve this target, if we take into account the deployment of a new simulator, the costs would be extremely high. Many utilities carried out similar strategies, utilizing alternative simulators as a complement to full scope simulator in the areas of training and model maintenance. Therefore, depending upon training requirements and finances, the Cernavoda Unit 1 Simulator modernization providing also an alternative to full scope control room simulator may be a viable option. In this case, the solution that we discuss for Cernavoda training extension is the migration of Cernavoda Unit 1 Simulator to state-of-the-art. The paper has the following contents: - Considerations; - Benefits; - Required tasks; - Simulator Modernization Hardware; - Software Scope; - Executive System Programs; - Development and Debug Programs; - Modeling Software; - Plant System Models; - Graphical Model Builder; - Emulation Software; - Instructor Station Software; - Cernavoda 2 simulation facilities; - Limitations

  5. Status of the spent fuel dry storage programme for Cernavoda NPP

    International Nuclear Information System (INIS)

    Radu, M.

    1999-01-01

    The Cernavoda NPP Unit 1 (600 MWe Standard type) is in operation since December 1996. Within the framework of the R and D Radioactive Waste and Spent Fuel Management Programme, investigations, studies and research are carried out on site identification and conceptual designs for both a Spent Fuel Interim Storage Facility and a Spent Fuel Disposal Facility. The status of the work performed in the framework of this programme as well as the situation of the spent fuel resulting from the Research Institutes will be presented in the paper. (author)

  6. Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

    International Nuclear Information System (INIS)

    Stanciu, Marcela; Mateescu, Silvia; Pantazi, Doina; Penescu, Maria

    2000-01-01

    At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

  7. The Romanian experience on introduction of CANDU-600 reactor at the Cernavoda NPP

    International Nuclear Information System (INIS)

    Rapeanu, S.N.; Bujor, A.; Comsa, O.

    1998-01-01

    The Cernavoda Nuclear Power Plant (NPP) Project is a key component of the Romanian nuclear development program. Selection of the CANDU design represents a major contribution to this development, due to the technological feasibility for manufacturing of parts, components and the nuclear fuel based on the uranium resources in Romania. The Romanian nuclear development program also involves a nuclear fuel manufacturing plant, a heavy water production plant and organizations specialized in research, engineering, manufacturing and completion for systems and components. The agreement on technological transfer between Canada and Romania is supporting the Romanian involvement to the achievement of the Project, with a degree of participation that is gradually increasing from the first to the last NPP Unit. (author)

  8. Qualified operator training in the simulated control room environment

    International Nuclear Information System (INIS)

    Ionescu, Teodor; Studineanu, Emil; Radulescu, Catalina; Bolocan, Gabriel

    2005-01-01

    Full text: Mainly designed for the training of the Cernavoda NPP Unit 2 operators, the virtual simulated environment allows the training of the already qualified operators for Cernavoda NPP Unit 1, adding to the already trained knowledge, the differences which has occurred in the Unit 2 design. Using state-of-the-art computers and displays and qualified software, the virtual simulated panels could offer a viable alternative to classic hardware-based training. This approach allows quick training of the new procedures required by the new configuration of the re-designed operator panels in the main control room of Cernavoda NPP Unit 2. (authors)

  9. Qualified operator training in the simulated control room environment

    International Nuclear Information System (INIS)

    Ionescu, Teodor; Studineanu, Emil; Radulescu, Catalina; Bolocan, Gabriel

    2005-01-01

    Mainly designed for the training of the Cernavoda NPP Unit 2 operators, the virtual simulated environment allows the training of the already qualified operators for Cernavoda NPP Unit 1, adding to the already trained knowledge, the differences which have occurred in the Unit 2 design. Using state-of-the-art computers and displays and qualified software, the virtual simulated panels could offer a viable alternative to classic hardware-based training. This approach allows quick training of the new procedures required by the new configuration of the re-designed operator panels in the main control room of Cernavoda NPP Unit 2. (authors)

  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. Cernavoda NPP: Training for safety and reliability

    International Nuclear Information System (INIS)

    Postolache, Laura Lia

    2001-01-01

    The safe and reliable operation of NPP require successful integration of plant and system design (1), programmes and procedures (2) and qualified human resources (3). Of these three components, station personnel and management have capability to influence and improve programmes and competence of qualified personnel. Qualifying personnel includes selection, training and evaluation that meet the established performance standards. Training, therefore prepares people to achieve such competence. The critical role of operations personnel has been rightly emphasized by every country with a nuclear power programme. So far as operation team is concerned, they have to work, on the one hand with exacting safety rules and at the same time, they have to do the right thing at all times. In essence, they have to be prepared for new, emergency situations as well as for routine work. The plant operation in the Control Room is essentially a man - machine interaction and a safe and reliable operation requires them to take high quality decisions even under stressful conditions. Here lies therefore the need for high competent and licensed operations engineers who will ensure operation within the operating license of the station under the all conditions. The development of a long-term comprehensive training for Operation Staff is a requirement. The program addresses the qualification requirements of the various nuclear positions on shift, the outline content of the required training programs and the evaluation per the Systematic Approach to Training (SAT). A nuclear operator's training begins the moment he/she enters the station. It takes four to six years to develop the skills required to demonstrate that the candidate is an appropriate choice for the position. Then there's a further about two years of intense training at the Training Center on a simulator. After successful completion of the program, the candidate is authorized by the CNCAN (National Commission for Control of Nuclear

  12. Modelling of preheated regenerative chain in Cernavoda NPP using MMS calculation code

    International Nuclear Information System (INIS)

    Bigu, M.; Nita, I.; Prisecaru, I.; Dupleac, D.

    2005-01-01

    Full text: In this work it was studied operation of preheated regenerative chain from NPP Cernavoda. To obtain this analysis coupled analyses of condensate system, water supply system, and drain cooler system were effected. The analysis boundaries are: Upstream: - Steam condensers - Turbine Bleed Steam Downstream: - Steam Generators. The analysis was made in two steps: 1) Getting of hydraulic characteristic of pipe network from steam condensers to steam generators at nominal regime; this step was obtained with hydraulic package called PIPENET. 2) Real thermal hydraulic analyses were done based on hydraulic characteristic of pipe network and supplementary data required for heat transfer calculation in equipment of preheated regenerative chain. Thermal analyses were done using MMS package and refered to normal operating regimes, namely, nominal operating regime required for calibration of calculating model, shutdown regime, start-up regime from zero power hot to nominal power and to abnormal operating regimes, namely, turbine trip, reactor trip and loss of two condensate pumps. The results were compared with already existing analysis and showed the largest differences at interface areas (i.e. 5%). This led us to idea of extending analysis to all secondary circuits in order to reduce the number of boundary conditions which can generate uncertainty in analysis. In this analysis we obtained an advanced model of preheated regenerative chain of secondary circuit in Cernavoda NPP which could be extended up to cover the whole secondary circuit by including the analysis of steam generators, turbine, and steam condenser. (authors)

  13. Modelling of preheated regenerative chain in Cernavoda NPP using MMS calculation code

    International Nuclear Information System (INIS)

    Bigu, M.; Nita, I.; Prisecaru, I.; Dupleac, D.

    2005-01-01

    In this work it was studied operation of preheated regenerative chain from NPP Cernavoda. To obtain this analysis coupled analyses of condensate system, water supply system, and drain cooler system were effected. The analysis boundaries are: Upstream: - Steam condensers - Turbine Bleed Steam Downstream: - Steam Generators. The analysis was made in two steps: 1) Getting of hydraulic characteristic of pipe network from steam condensers to steam generators at nominal regime; this step was obtained with hydraulic package called PIPENET. 2) Real thermal hydraulic analyses were done based on hydraulic characteristic of pipe network and supplementary data required for heat transfer calculation in equipment of preheated regenerative chain. Thermal analyses were done using MMS package and referred to normal operating regimes, namely, nominal operating regime required for calibration of calculating model, shutdown regime, start-up regime from zero power hot to nominal power and to abnormal operating regimes, namely, turbine trip, reactor trip and loss of two condensate pumps. The results were compared with already existing analysis and showed the largest differences at interface areas (i.e. 5%). This led US to idea of extending analysis to all secondary circuits in order to reduce the number of boundary conditions which can generate uncertainty in analysis. In this analysis we obtained an advanced model of preheated regenerative chain of secondary circuit in Cernavoda NPP which could be extended up to cover the whole secondary circuit by including the analysis of steam generators, turbine, and steam condenser. (authors)

  14. Cernavoda NPP: The contribution of ANSALDO ENERGIA to the development of the Nuclear Program in Romania

    International Nuclear Information System (INIS)

    Graziosi, G.; Benvenuto, F.

    2005-01-01

    Full text: The development of east European countries has been very slow during the second part of the 20th century, but, with the end of the cold war, they are recovering through a continuous improvement of their economy. The continuous improvement of the countries is usually accompanied by an increase of the energy demand and, as consequence, a rapid increase of their energy production is taking place. It is strategic that the energy production of these countries be based on earliest technologies available today, in order to avoid the worsening of the problems deriving from the energy policies adopted by the western countries: one for all the CO 2 emission in the atmosphere. Clearly to promote the use of new technologies in the growing east European countries, a tied collaboration between western and eastern European countries is essential. This is the case of Romania. The agreement reached by Romania with the Italian and Canadian industries (Ansaldo Energia and AECL) has permitted: - The construction and commissioning of Cernavoda Unit 1 NPP, realized adopting CANDU technology and in operation since 1996; - The continuous maintenance / surveillance / improvement (through a specific service agreement) that assures the safe production of the energy; - The realization of a new Nuclear Power Station: Cernavoda Unit 2, adopting the last technology available for the CANDU type. Its operation is expected to start in 2007. Furthermore, benefit/cost evaluation is under analysis in order to verify the possibility to realize Cernavoda Unit 3 NPP. (authors)

  15. Cernavoda NPP: The contribution of ANSALDO ENERGIA to the development of the Nuclear Program in Romania

    International Nuclear Information System (INIS)

    Graziosi, G.; Benvenuto, F.

    2005-01-01

    The development of east European countries has been very slow during the second part of the 20th century, but, with the end of the cold war, they are recovering through a continuous improvement of their economy. The continuous improvement of the countries is usually accompanied by an increase of the energy demand and, as consequence, a rapid increase of their energy production is taking place. It is strategic that the energy production of these countries be based on earliest technologies available today, in order to avoid the worsening of the problems deriving from the energy policies adopted by the western countries: one for all the CO 2 emission in the atmosphere. Clearly to promote the use of new technologies in the growing east European countries, a tied collaboration between western and eastern European countries is essential. This is the case of Romania. The agreement reached by Romania with the Italian and Canadian industries (ANSALDO ENERGIA and AECL) has permitted: - The construction and commissioning of Cernavoda Unit 1 NPP, realized adopting CANDU technology and in operation since 1996; - The continuous maintenance / surveillance / improvement (through a specific service agreement) that assures the safe production of the energy; - The realization of a new Nuclear Power Station: Cernavoda Unit 2, adopting the last technology available for the CANDU type. Its operation is expected to start in 2007. Furthermore, benefit/cost evaluation is under analysis in order to verify the possibility to realize Cernavoda Unit 3 NPP. (authors)

  16. Characterisation of radioactive waste at Cernavoda NPP Unit 1 during normal operation

    International Nuclear Information System (INIS)

    Iordache, M.; Bujoreanu, L.; Popescu, I. V.

    2008-01-01

    During the operation of a nuclear plant significant quantities of radioactive waste results that have a very large diversity. At Cernavoda NPP the important waste categories are non-radioactive wastes and radioactive wastes, which are manipulated completely different from which other. For a CANDU type reactor, the production of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products of materials which form part of the technological systems; - activated products of process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination activities. The most important types of solid wastes that are obtained and then handled, processed (if required) and temporarily stored are: solid low level radioactive wastes (classified as compact and non-compact), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, decontamination and maintenance operations. Radioactive gas wastes occur subsequent to the fission process inside the fuel elements as well as due to the process fluids neutron activation in the reactor systems. As result of the plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed to the ventilation stack in a controlled manner so that an exceeding of the maximum permissible concentrations of radioactive material to the environment should not occur. (authors)

  17. Implementing Data Acquisition Systems DAS1 and DAS2 at Cernavoda Full-Scope Simulator Main Control Room based on the SIEN2007 solution

    International Nuclear Information System (INIS)

    Ionescu, Ana Maria; Tutuianu, Bogdan; Ionescu, Teodor

    2009-01-01

    Modern personnel training, re-training and licensing is a guarantee of NPP's safe reliable operation. Cernavoda NPP personnel training system is the main objective of its specialized department built up as Training Center (TC), directly supervised by Administration of the National Nuclearelectrica Society (SNN) and National Regulatory Body for Nuclear Activities (CNCAN). It was implemented to ensure the abilities, skills and knowledge required by the safe reliable operation of the nuclear reactor by the Main Control Room (MCR) operators. This objective was reached through training lessons taught and tested on the Full Scope Simulator (FSS), the TC's main training tool, a replica of the MCR of the real plant. Its description is the subject of this paper. The TC's FSS includes a computer network equipped with a software connected to the specialized program DATAPATH supplied for Cernavoda FSS by the FSS provider, delivered by L-3/ MAPPS. An alternative to DATAPATH Communication of the L 3/MAPPS Simulation System, developed by Cernavoda Full Scope Simulator Staff, was presented in the previous edition of the symposium (see the SIEN 2007 paper). This original solution is now already applied in order to connect to simulation process Data Acquisition Systems DAS1 and DAS2, two new systems already installed in the real MCR but not included by the Cernavoda FSS initial design. Communication between simulation software and DAS1 and DAS2, considered to be simple receivers of simulated data both as much alike as the two DASs from real plant, is performed in parallel with DATAPATH in a safe mode and without affecting simulation process. This paperwork presents the above mentioned application of this communication solution, developed by the Cernavoda NPP Full Scope Simulator Staff with details about the hardware/software solutions and their performance, training impact, cost and benefits. (authors)

  18. Autoevaluation process at SNN SA-CNE PROD Cernavoda

    International Nuclear Information System (INIS)

    Florescu, N.

    2005-01-01

    Implementation of the autoevaluation process requires identification of the activities carried with performance under the limits imposed by international standards. The following activity areas were established for autoevaluation at Cernavoda NPP: 1. General activities; 2. Operation activities; 3. Work control; 4. Maintenance activities; 5. Preparing activities; 6. Technical activities; 7. Radioprotection activities; 8. Emergency plans; 9. Environment control activities; 10. Chemical control; 11. Materials control; 12. Physical protection; 13. Document control; 14. Fuel manipulation. In order to improve the performances at Cernavoda NPP the WANO autoevaluation model was adopted

  19. 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)

  20. 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)

  1. Diagnosis methods based on noise analysis at Cernavoda NPP, Romania

    International Nuclear Information System (INIS)

    Banica, Constantin; Dobrea, Dumitru

    1999-01-01

    This paper describes a recent noise analysis of the neutronic signals provided by in-core flux detectors (ICFD) and ion chambers (IC). This analysis is part of on-going program developed for Unit 1 of the Cernavoda NPP, Romania, with the following main objectives: - prediction of detector failures based on pattern recognition; - determination of fast excursions from steady states; - detection of abnormal mechanical vibrations in the reactor core. The introduction presents briefly the reactor, the location of ICFD's and IC's. The second section presents the data acquisition systems and their capabilities. The paper continues with a brief presentation of the numerical methods used for analysis (section 3). The most significant results can be found in section 4, while section 5 concludes about useful information that can be obtained from the neutronic signals at high power steady-state operation. (authors)

  2. New approach of second Romanian NPP siting

    International Nuclear Information System (INIS)

    Mauna, Traian

    2010-01-01

    The NPP sitting studies in Romania began before 1975. The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units. Gained the experience from Cernavoda NPP sitting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the NPP Cernavoda project to the new parameters of close water cooling circuit and hard less and no rock foundation strata. The studies were carrying out in different stages on the inner rivers Olt, Mures, Somes in Transylvania historical region. This paper tries to reconsider shortly the old analysis according to the last IAEA Safety Standards, taking into account the new NPP generation requirement. Paper is focused on geological aspects and other local sites characteristics. (authors)

  3. Cernavoda - Unit 2. A strategic project for Romania

    International Nuclear Information System (INIS)

    Saroudis, J.I.; Chirica, T.; Villabruna, G.

    1999-01-01

    The paper presents some key aspects of the Romanian nuclear program, focusing on Cernavoda NPP Unit No. 2 and the partnership with Atomic Energy of Canada Ltd. (AECL) and ANSALDO Italy for completion of this project. A brief historical presentation of the Romanian nuclear program is included. The success of Cernavoda NPP Unit 1 represents an important element in finalizing Unit 2 in an advanced state of equipment installation and more than 40 % complete. Also, the national infrastructure, including the legal framework and new Electricity Law represents a positive element for Project completion. The Romanian Nuclear Regulatory Body represents the guarantee for the safe operation of CANDU reactors in Romania.(author)

  4. Development of new process network for gas chromatograph and analyzers connected with SCADA system and Digital Control Computers at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Deneanu, Cornel; Popa Nemoiu, Dragos; Nica, Dana; Bucur, Cosmin

    2007-01-01

    The continuous monitoring of gas mixture concentrations (deuterium/ hydrogen/oxygen/nitrogen) accumulated in 'Moderator Cover Gas', 'Liquid Control Zone' and 'Heat Transport D 2 O Storage Tank Cover Gas', as well as the continuous monitoring of Heavy Water into Light Water concentration in 'Boilers Steam', 'Boilers Blown Down', 'Moderator heat exchangers', and 'Recirculated Water System', sensing any leaks of Cernavoda NPP U1 led to requirement of developing a new process network for gas chromatograph and analyzers connected to the SCADA system and Digital Control Computers of Cernavoda NPP Unit 1. In 2005 it was designed and implemented the process network for gas chromatograph which connected the gas chromatograph equipment to the SCADA system and Digital Control Computers of the Cernavoda NPP Unit 1. Later this process network for gas chromatograph has been extended to connect the AE13 and AE14 Fourier Transform Infrared (FTIR) analyzers with either. The Gas Chromatograph equipment measures with best accuracy the mixture gases (deuterium/ hydrogen/oxygen/nitrogen) concentration. The Fourier Transform Infrared (FTIR) AE13 and AE14 Analyzers measure the Heavy Water into Light Water concentration in Boilers Steam, Boilers BlownDown, Moderator heat exchangers, and Recirculated Water System, monitoring and signaling any leaks. The Gas Chromatograph equipment and Fourier Transform Infrared (FTIR) AE13 and AE14 Analyzers use the new OPC (Object Link Embedded for Process Control) technologies available in ABB's VistaNet network for interoperability with automation equipment. This new process network has interconnected the ABB chromatograph and Fourier Transform Infrared analyzers with plant Digital Control Computers using new technology. The result was an increased reliability and capability for inspection and improved system safety

  5. Estimation of the future nuclear power research in Romania, based on the present Cernavoda NPP evolution

    International Nuclear Information System (INIS)

    Dumitrache, Ion

    2001-01-01

    For more than four decades, the electric power needs of Romania were evaluated on the basis of the State Plan for Economic Development. To identify the optimal solution, the 'least price per produced MWh' was practically the only criterion. Now, there is no convincing estimation of the future economic development and at least two additional criteria play a significant role, 'the safety in the supply of the needed electric power', and 'the need of limiting the environmental impact of electricity generation'. The analysis dedicated to evaluation of future electric power solutions must take into account several features of the present situation. There are no available internal funds to finance the construction of new generating units of the order of several hundreds of MW. Even the so-called 'refurbishing' of the existing thermal power plants is based on foreign loan. In the 2000 year, about 80 electricity generation units reached 30 years of operation, i.e., the design life. Other thermal power plants proved very modest performances during 15-20 years of operation. Consequently, the future of almost 100 generating units is either in shutdown + decommissioning or shutdown + modernization situation. The Government analyzed the situation and decided to continue the completion of the Cernavoda NPP. The Unit 2 will be commissioned in a couple of years, and there is a schedule of negotiations relating the future of the Unit 3. After almost five years of successful operation of the Unit 1, the collaboration between RDT Institutes and NPP has clear features. Based on the experience related to this collaboration and taking into account the evolution of the Cernavoda NPP, we estimated that five research domains have significant chances to obtain a stable (and, hopefully, consistent) financial support. 1. Nuclear Safety, in particular Accident Analysis. As the Government re-iterated the firm decision to meet the conditions required for European integration, most of the nuclear

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

    International Nuclear Information System (INIS)

    2008-01-01

    The Cernavoda Unit 2 NPP work was originally started in 1982 with work coming to a halt in 1989, and a preservation program implemented in 1991 while work continued on Unit 1. In 1995 attention turned to the completion of Unit 2 and status verification reports were commissioned. Work proceeded, as funds were available, up until 2002 when an interim contract was signed. Subsequently a Contract Completion Effective Date (CCED) was signed in March 2003 with completion duration of 48 months. A project schedule is a necessity for any project whether it is a new build or a restart to a delayed project. There are 5 major elements that are included in all CANDU project schedules, Engineering, Procurement, Construction, Commissioning and the conversion from Construction to Commissioning. The Engineering schedule of deliverables was not fully defined at CCED. Design changes defined prior to CCED were not fully defined and the scope of work associated with these only became known during the actual construction program. A significant number of new design changes were introduced after CCED, which compounded the impact to the construction program. All projects require their budgets to be built up within a defined structure. Delayed projects are no different from other projects in that respect. The standard Work Brakout Structure (WBS), which is applicable to most CANDU projects, is equally applicable for a delayed project. On Cernavoda Unit 2 we used a Budget Breakdown Structure, which was a combination of a traditional WBS and an Organization Structure. This structure was adopted in order to have consistency with the structure, which had been used prior to the delay on the project and also it was a requirement of the three party agreements with funding from different sources and in different currencies. All major construction projects normally carry a contingency allowance for undefined work and a risk allowance for the possibility of major changes. Delayed projects require

  7. 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

  8. Using residual tritiated water from Cernavoda NPP to study Danube - Black Sea Canal hydrodynamics

    International Nuclear Information System (INIS)

    Varlam, C.; Stefanescu, I.; Lazar, R.; Varlam, M.; Patrascu, V.; Bucur, C.; Bobric, E.

    2003-01-01

    By benefiting of Cernavoda NPP's location in the neighbourhood of Danube - Black Sea Canal one suggests extending the area of interest along this canal particularly to use the residual tritiated water from this CANDU type reactor as tracing means in the study of canal's hydrodynamics. This canal appears to be ideal for such a study because releases in normal operation of NPP are occasional. The tritiated water can be used for simulating the transport and dispersion of soluble pollutants because it has the same physical characteristics as the usual water. By measuring response curves produced at injecting a known amount of tracer one can developed an efficient method for estimating: the soluble pollutant velocity along the canal; attenuation rate of concentration peak as a function of time as well as the time required by the propagation front of the soluble pollutant to reach a given point along the canal. In this work the calculation of the mixture length as a function of the particular characteristics of the canal is presented as well as different experimental formulas. Also the reference level of tritium concentration in the investigated area is established for future experiments

  9. Satellite infrared imagery for thermal plume contamination monitoring in coastal ecosystem of Cernavoda NPP

    Science.gov (United States)

    Zoran, M. A.; Zoran, Liviu Florin V.; Dida, Adrian I.

    2017-10-01

    Satellite remote sensing is an important tool for spatio-temporal analysis and surveillance of NPP environment, thermal heat waste of waters being a major concern in many coastal ecosystems involving nuclear power plants. As a test case the adopted methodology was applied for 700x2 MW Cernavoda nuclear power plant (NPP) located in the South-Eastern part of Romania, which discharges warm water affecting coastal ecology. The thermal plume signatures in the NPP hydrological system have been investigated based on TIR (Thermal Infrared) spectral bands of NOAA AVHRR, Landsat TM/ETM+/OLI, and MODIS Terra/Aqua time series satellite data during 1990-2016 period. If NOAA AVHRR data proved the general pattern and extension of the thermal plume signature in Danube river and Black Sea coastal areas, Landsat TM/ETM and MODIS data used for WST (Water Surface Temperature) change detection, mapping and monitoring provided enhanced information about the plume shape, dimension and direction of dispersion in these waters. Thermal discharge from two nuclear reactors cooling is dissipated as waste heat in Danube-Black -Sea Channel and Danube River. From time-series analysis of satellite data during period 1990-2016 was found that during the winter season thermal plume was localized to an area of a few km of NPP, and the mean temperature difference between the plume and non-plume areas was about 1.7 oC. During summer and fall, derived mean temperature difference between the plume and non-plume areas was of about 1.3°C and thermal plume area was extended up to 5- 10 km far along Danube Black Sea Channel.

  10. Economic viability of Cernavoda project

    International Nuclear Information System (INIS)

    Condu, M.; Popescu, D.; Chirica, T.; Glodeanu, F.

    1998-01-01

    Cernavoda project started in 1978, when the CANDU technology procurement contract and other contracts for engineering, technical assistance and procurement were signed with AECL. The works on site started in 1980. In February 1981, a contract was signed with GE - USA and Ansaldo - Italy for balance of plant. After 1989 the concept for project implementation was essentially changed. The completion of Cernavoda NPP Unit-1, established as the first priority by Romanian authorities was implemented by AECL-Ansaldo Consortium (AAC). The objective of the contract signed with AAC consisted in overtaking the management of Cernavoda Unit-1 project, in order to complete, commission and operate the plant for 18 months. The plant was successfully completed, commissioned and commercially operated since December 2, 1996. As concerns Unit-2, only preservation and some remedial works were performed since 1991. In order to support the decision to complete Unit-2, a complete process was initiated: - identification of the activities and associated costs required for plan completion; - plant integration in the utility's least cost development study; - Unit-2 cash flow analysis. A joint RENEL-AECL-ANSALDO team performed a detailed analysis using Cernavoda Unit-1 as reference project and taking advantage of the experience gained during construction, commissioning and operation of the first unit. The least cost power generation development study finalized by SEP and EDF, based on a PHARE funding, ranked Cernavoda Unit-2 on the second place, after two small hydroelectric plants of 53 and 8 Mw e. A cash flow model developed by a RENEL-ANSALDO joint team shows that Cernavoda Unit-2 is an economically feasible project. The financing scenario provides that all resources will be from loans. Other arguments for completion of Cernavoda Unit-2 are: - good performances in operation of Unit-1; - the need to provide jobs for the specialists in the nuclear field; - opportunity for electricity export

  11. Preliminary evaluation of the seismic hazard at Cernavoda NPP site

    International Nuclear Information System (INIS)

    Mingiuc, C.; Serban, V.; Androne, M.

    2001-01-01

    The probabilistic seismic hazard analysis (PSHA) is a methodology by which one evaluates the probability of exceeding different parameters of the ground motions (the maximum ground acceleration - PGA and the ground response spectrum - SA) as effect of the seismic action, on a given site at a future time moment. Due to the large uncertainties in the geological, geophysical, seismological input data, as well as, in the models utilised, various interpretation schemes are applied in the PSHA analyses. This interpretation schemes lead to opinion discrepancies among specialists which finally lead to disagreements in estimating the values of the seismic design for a given site. In order to re-evaluate the methodology and to improve the PSHA result stability, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) and Electric Power Research Institute (EPRI) sponsored a project for defining methodological guides of performing PSHA analyses. The project was implemented by a panel of 7 experts, the Senior Seismic Hazard Analysis Committee - SSHAC. This paper presents a preliminary evaluation of the seismic hazard for the Cernavoda NPP site by application of the methodology mentioned, by taking into account the possible sources which could affect the site (the Vrancea focus, Galati - Tulcea fault, Sabla - Dulovo fault and local earthquakes)

  12. 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)

  13. Conditioning the radioactive oils released from the Cernavoda NPP operation

    International Nuclear Information System (INIS)

    Popescu, I.; Deneanu, N.; Dulama, M.; Baboiescu, E.

    2001-01-01

    The radioactive oils released during the Cernavoda NPP operation are lubricating oils used in the primary circuit pumps, hydraulic oils used in the reactor charging machine, as well as, waste turbine oils. The primary cooling circuit is the main way of contamination. This waste contain variable amounts of tritium of activities up to 10 8 Bq/l and relatively small amounts of β/γ emitting radionuclides. The radioactive oils resulting of the heat transport system may contain as much as 1.8 TBq/l of tritium. At INR Pitesti, Department of Radioactive Waste Processing, studies were done concerning the radioactive oils conditioning in concrete. It was found that the minimal compression level required for disposal, of 50 MPa, was exceeded. As consequence, the conditioned waste fulfils the conditions of acceptance provided by the Radioactive Waste National Repository at Baita-Bihor. The main stages of the process are: - dosing the radioactive oil, water and NOFOX9 and NOFOX4 emulsion additives for the 220 l or 80 l barrel; - mixing these ingredients up to reaching the emulsion state; - dosing the cement and lime; - adding the enhancing silicate and shaking the mixture to get a homogeneous matrix; - closing the barrel; - conditioning the 80 l barrel within the 220 l container. The production capacity is of 5 to 8 barrels/shift

  14. Reliability problems in the recirculated cooling water system at Cernavoda NPP and corrective maintenance operations adopted

    International Nuclear Information System (INIS)

    Bucur, Ionel; Metes, Mircea

    2002-01-01

    Between February 18 and March 5, 2002 the Unit 1 of Cernavoda NPP was shutdown in an un-planned outage necessary to repair a crack on the piping of the Recirculated Cooling Water System. The large pipe diameter and the requirement of maintaining the system in operation during the outage, imposed a special technology for fixing the leak (isolation of the line with ice plugs). The paper presents information about the performed repair work. After repair operations the failed duct was checked by non-destructive methods and the results were submitted and approved by regulation authorities. The repair was considered successfully completed and the Unit restarted on March 5, 2002 at 0.57 am when the electric generator was switched on in parallel to the national electric power system. (authors)

  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. Cernavoda NPP Unit 1: Ensuring heat sink at very low Danube river levels

    International Nuclear Information System (INIS)

    Urjan, D.

    2005-01-01

    Full text: On August 24, 2003 the summer heat wave has caused the Danube River to drop to its lowest level in more than a century, forcing a government commission of experts and a team of technical specialists from Cernavoda NPP to close Romania's unique nuclear reactor in operation at Cernavoda. The paper presents some of the required actions needed for plant shutdown and ensuring adequate fuel cooling at very low suction bay levels, due to the Danube River level drop (Danube waters cools the reactor). The water level in the Danube River at Cernavoda village, where the reactor is located, fell to a depth of less than three meters (10 feet) on Saturday, down from its usual level of almost seven meters (23 feet). Consequently, the Unit 1 nuclear power plant was shut down Sunday due to this record drought, which left insufficient water to cool down the reactor. Operating Instruction procedures were elaborated in order to provide a logical sequence of actions when the bay level decreases under 2.25 m, or the estimated level after 3 days will be lower than 1.8 m. When Raw Service Water (RSW) is lost, Recirculated Cooling Water (RCW) will remain in service only for Moderator, ESC, HT Pumps, HT Purification, D/C Cooler, LAC's, and D 2 O Feed Pump. Alternate water sources, like potable water and water from the fire protection system were taken in consideration in order to ensure heat sink to the RCW loads. At the same time, in case of total loss of Class III and Class IV Power, and Stand-By Diesel Generators unavailable because of the loss of heat sink provided by the RSW, Emergency Power System (EPS) was configured to supply directly the Class III Power 6 kV bus (BUG bus). Economical Impact According to a report, closing the nuclear plant costs Romania $500,000 a day. The total cost includes also losses due to a 40 percent reduction in hydroelectric power generation due to reduced river flow. The country had to cease power exports until the reactor comes back on line

  17. Analysis of electrical systems from Cernavoda NPP - Unit 1 based on commissioning activity

    International Nuclear Information System (INIS)

    Goia, M.L.; Manolescu, I.

    1996-01-01

    Several design solutions regarding the electrical part of Cernavoda NPP Unit 1 station auxiliaries are discussed in this paper. The solutions mentioned may have different variants which should be taken into consideration in the design of Units U2 - U5. This work offers an ample debate on such matters as the supply source connection of the station auxiliaries, the use of two different voltages for the mean voltage (MV) supply, the consequence of the lack of breakers on the 24 kV part of station auxiliary transformers T03 - T04, the protection devices non correlated with the breakers to which they react, as well as the consequences of low subtransient reactance of the new stand-by Diesel generators. Besides these design solutions that can influence the station auxiliaries reliability, matters as malfunctioning of the dry type MV/LV transformers and unreliable behaviour of some MV composite insulators are also discussed. For some of the above mentioned problems the authors proposed several solutions. (authors). 1 fig., 1 tab

  18. Analyses of thermal plume of Cernavoda nuclear power plant by satellite remote sensing data

    Science.gov (United States)

    Zoran, M. A.; Nicolae, D. N.; Talianu, C. L.; Ciobanu, M.; Ciuciu, J. G.

    2005-10-01

    The synergistic use of multi-temporal and multi-spectral remote sensing data offers the possibility of monitoring of environment quality in the vicinity of nuclear power plants (NPP). Advanced digital processing techniques applied to several LANDSAT, MODIS and ASTER data are used to assess the extent and magnitude of radiation and non-radiation effects on the water, near field soil, vegetation and air for NPP Cernavoda , Romania . Cernavoda Unit 1 power plant, using CANDU technology, having 706.5 MW power, is successfully in operation since 1996. Cernavoda Unit 2 which is currently under construction will be operational in 2007. Thermal discharge from nuclear reactor cooling is dissipated as waste heat in Danube-Black -Sea Canal and Danube river. Water temperature distributions captured in thermal IR imagery are correlated with meteorological parameters. Additional information regarding flooding events and earthquake risks is considered . During the winter, the thermal plume is localized to an area within a few km of the power plant, and the temperature difference between the plume and non-plume areas is about 1.5 oC. During the summer and fall, there is a larger thermal plume extending 5-6 km far along Danube Black Sea Canal, and the temperature change is about 1.0 oC. Variation of surface water temperature in the thermal plume is analyzed. The strong seasonal difference in the thermal plume is related to vertical mixing of the water column in winter and to stratification in summer. Hydrodynamic simulation leads to better understanding of the mechanisms by which waste heat from NPP Cernavoda is dissipated in the environment.

  19. Cernavoda NPP Unit 2: 'A year of progress'

    International Nuclear Information System (INIS)

    Cullen, Ronald G.

    2004-01-01

    The year 2004 is now coming to an end and has proven to be 'A Year of Progress' at the Cernavoda 2 nuclear project. Staffing levels have reached their peak in all departments with the exception of Commissioning. The Management Team (MT) now has more than 1600 staff employed. There are 18 contractors working on the site, 3 Romanian Engineering organizations working out of Bucharest and countless manufacturers supplying materials for 2500 Romanian domestic orders, 440 Romanian International orders, 400 Canadian orders and 212 Italian orders. To date the project has met all milestones, most notably in 2004 was the First Energization of the Station Service Transformer in October, marking the start of the commissioning program. The Primary Heat Transport piping was completed ahead of schedule, and installation of the Stand-by Diesel Generators were effected. The D 2 O up-grader building was erected, the Main Moderator pumps, piping and heat exchangers were installed, and the Main Control Room was completed with the majority of the panels installed including the Digital Control Computers. By the end of the year 12 of the more than 290 systems will have been transferred from Construction to Commissioning and the overall project will be approximately 78% complete. A significant event for the year was the approval of the EURATOM loan, which provides financial stability for the remainder of the project. The request for the first draw against this loan has been made and disbursement is expected early in the New Year. There were problems that had to be overcome during the year. Securing qualified construction contractor's staff and qualified vendors has proven to be a major challenge. The introduction of electronic management tools in the Management organization has required significant training and inputting of a backlog of data. Refurbishment of existing equipment on all safety systems and materials has placed an added demand on resources and delays in having material

  20. Systematic evaluation of the Cernavoda nuclear power plant physical protection system

    International Nuclear Information System (INIS)

    Ionescu, D.S.

    2002-01-01

    Full text: For three years at Cernavoda NPP is working a process to systematic evaluating the effectiveness of the Physical Protection System (PPS). Due to the fact that this evaluation has to be continuous, the first important step is to define a baseline to compare periodically the performance of PPS against it. The necessity of that process has been identified as follows: the continuous changes in the field of perceived threats against Cernavoda NPP and the necessary measures to respond to that changing climate; the needful to improve the performance of PPS against certain threats in conjunction with the needful to allocate substantially financial and human resources to cover the discovered weakness in the system; an assistant to take the appropriate measure in case of indisponibility of one or more components or parts of the PPS. The second step is the continuous tracking of the behavior of PPS in order to determine: the maintenance resource allocation and the priorities of the work; the predictive behavior of installed components to determine the future appropriate measures, including budget dimensioning. SAVI is a PC compatible program developed by SANDIA Laboratory (USA) for comprehensive analysis of PPS effectiveness. That program is organized in two modules: the Adversary Sequence Diagram (ASD) module and the outsider module modeling trough specific codes both the characteristics of PPS and of the predicted adversary. Combining the two modules related to a specific PPS and adversary is possible to find out the effectiveness of the physical protection system for each vital zone along to ten possible paths to penetrate by adversary, starting with the most vulnerable one. Because of two conservative assumption considered by the SAVI algorithm (adversary know the PPS characteristics and they use an optimal penetration strategy), the measure of effectiveness (probability of interruption - P I ) is very realistic and conservative related to the necessary

  1. Developing technologies for conditioning the liquid organic radioactive wastes from Cernavoda NPP

    International Nuclear Information System (INIS)

    Deneanu, N.; Popescu, I. V.; Teoreanu, I.

    2004-01-01

    The Institute for Nuclear Research (INR)-Pitesti has developed technologies for conditioning liquid organic radioactive wastes (oils, miscellaneous solvent and liquid scintillation cocktail) for Cernavoda NPP. This paper describes the new and viable solidification technology to convert liquid organic radioactive wastes into a stable monolithic form, which minimizes the probability to release tritium in the environment during interim storage, transportation and final disposal. These are normally LLW containing only relatively small quantities of beta/gamma emitting radionuclides and variable amounts of tritium with activity below E+08Bq/l. The INR research staff in the radwaste area developed treatment/conditioning techniques and also designed and tested the containers for the final disposal, following the approach in the management of radwaste related to the nuclear fuel cycle. Thus, the INR focused this type of activity on treating and conditioning the wastes generated at Cernavoda Nuclear Power Plant consisting of lubricants from primary fuelling machines and turbine, the miscellaneous solvent from decontamination operation and the liquid scintillation cocktail used in radiochemical analysis. Laboratory studies on cementation of liquid organic radioactive wastes have been undertaken at INR Pitesti. One simple system, similar to a conventional cement solidification unit, can treat radioactive liquid wastes, which are the major components of low- and medium-level radioactive wastes generated by a Nuclear Power Plant. It was proved that the solidified waste could meet the Waste Acceptance Criteria of the disposal site, in this case Baita-Bihor National Repository, as follows: - The wastes are deposited in type A packages; - The maximum expected quantities of this waste stream that will be produced in the future are 50 drums per year. The maximum specific tritium activity per drum is 10 9 Bq/m 3 ; - Compressive strengths of the samples should be greater than 50 MPa

  2. An integrated approach for investigation of failed nuclear fuel used at NPP Cernavoda Unit 1

    International Nuclear Information System (INIS)

    Tuturici, I.L.; Parvan, M.; Popov, M.; Dobrin, R.; Staicu, C.

    1996-01-01

    At NPP Cernavoda-Unit 1 the fuel surveillance and the defect detection system in operation are based on monitoring the coolant activity concentration and on measuring the flux of delayed neutrons emitted by some short-lived fission products. In order to identify the failed fuel underwater non-destructive examination has to be performed. The major interest for the availability of underwater examination consists in the necessity of a speedy acquisition of the data on failed fuel in operation and of appropriate follow-up actions to be taken. Often the identification operation will be followed by more detailed examinations on selected fuel rods in the hot cells of the Post-irradiation Examination Laboratory of the Institute for Nuclear Research at Pitesti. Transfer of selected fuel rods will be done by the use of a type B(U) road transportation cask. Such an integrated approach will help to keep the level of activity concentration of the primary circuit well below the authorized limits. (author). 2 figs., 1 tab., 2 refs

  3. 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

  4. Modernization of tritium in air monitoring system for CANDU type NPP

    International Nuclear Information System (INIS)

    Purghel, L.; Iancu, R.; Popescu, M.

    2009-01-01

    Nuclear energy provides at present one third of Europe's electricity with nearly no greenhouse-gas emissions. Sustained efforts are now being conducted to harmonize regulations all over Europe through WENRA and to converge on technical nuclear safety practices within the TSO network ETSON (European Technical Safety Organizations Network). In order to achieve this goals of safety function, IFIN-HH together with CITON developed a new solution to improve the Tritium Monitoring System (TMS) of Cernavoda NPP and the new generation of CANDU type reactors, using Tritium in air Intelligent Monitors (TIM) developed and patented by IFIN-HH. The paper presents a comparative analysis between the technical characteristics of traditional solutions implemented in CANDU type NPP, particularly in Cernavoda NPP Unit 2 and the newly proposed solution. (authors)

  5. Training system of knowledge society

    International Nuclear Information System (INIS)

    Ceclan, M.; Ionescu, T.B.; Ceclan, Rodica Elena; Tatar, Florin; Tiron, C.; Georgescu, Luisa Maria

    2005-01-01

    Full text: The paper aims at presenting the results of Cernavoda NPP Training Department modernization project. In order to achieve a training system of knowledge society in the first stage of the project a Computer Based Training (CBT) or E-Learning platform and several CBT objects/courses were worked out. The conceived E-Learning solution is called CBT Center and it is a complete system offering a variety of teaching and learning services to its users. CBT and/or E-Learning always mean two things: a software platform and content authoring. Ideally, a software platform should be able to import any type of flat documentation and integrate it into a structured database which keeps track of pedagogically meaningful information like the student's progress in studying materials, tests and quiz, marks, etc. At the same time, the materials, the study and the tests have to be organized around certain objectives which play the role of guidelines during the entire educational activity. An example of such a course which has been successfully integrated into CBT Center is the 'Thermodynamics'. CBT technology implementation at NPP Cernavoda Training Department has brought several advantages: the technology improves overall communication between all individuals which are part of the educational process; there is no space problem any more; students can access training materials from their own desk using the NPP intranet; the logistics problem will decrease, while more and more disciplines will be transformed as CBT objects. (authors)

  6. New appraisement of siting for a NPP on Mures river

    International Nuclear Information System (INIS)

    Traian Mauna

    2010-01-01

    The studies for a second NPP siting on inner Romanian rivers began in a careful manner since 1982 as a first part of the Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. The experience gained from Cernavoda NPP siting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the CANDU type NPP Cernavoda project to the new parameters of close water cooling circuit and of hard less or no rock foundation strata. The new sites conditions mean a lot of changes of CANDU license and a decrease the output power supplied to the national electric grid. The studies on the Mures river as alternative site of Olt river in Transylvania region began in 1986 and were stopped after 1990. This paper tries to reconsider shortly the old analysis focused on geological and geotechnical aspects and other local sites characteristics according to the last IAEA Safety Standards taking into account also the last types of NPP generations and the number of units. (author)

  7. Knowledge society training system

    International Nuclear Information System (INIS)

    Ceclan, Mihail; Ionescu, Tudor Basarab; Ceclan, Rodica Elena; Tatar, Florin; Tiron, Cristian; Georgescu, Luisa Maria

    2005-01-01

    The paper aims to present the results of the Cernavoda NPP Training Department modernization project. In order to achieve a knowledge society training system, in the first stage of the project a Computer Based Training (CBT) or E-Learning software platform and several CBT objects/courses have been implemented. The conceived solution is called CBTCenter which is a complete E-Learning and CBT system, offering a variety of teaching and learning tools and services to its users. CBT and/or E-Learning always mean two things: a software platform and content authoring. Ideally, a software platform should be able to import any type of flat documentation and integrate it into a structured database which keeps track of pedagogically meaningful information like the student's progress in studying materials, tests and quizzes, grades, etc. At the same time, the materials, the study and the tests have to be organized around certain objectives which play the role of guidelines during the entire educational activity. An example of such a course which has been successfully integrated into CBTCenter is Labour safety - code name BB-001. The implementation of the CBT technology at NPP Cernavoda Training Department has brought several advantages: the technology improves overall communication between all individuals which take part in the educational process; the classroom space problem has been considerably reduced; students can access training materials from their own desk using the NPP intranet; the logistics problems will decrease with the conversion of more and more conventional courses and materials into CBT objects/courses. (authors)

  8. Upgrading NPP personnel. Competence and training through the systematic approach to training

    International Nuclear Information System (INIS)

    Mautner Markhof, F.

    1998-01-01

    This paper presents the reasons for acceptance of SAT (Systematic Approach to Training) as the best international practice in respect to training of NPP personnel and the differences in comparison to traditional approaches to training. The identification and evaluation of the new training needs, resources and other requirements for implementing SAT are discussed as well as new approaches and existing training capabilities and involvement of Regulatory body in training of NPP personnel. The IAEA Guidebook on NPP Personnel Training (TRS-380) was used a a basis for discussion of the mentioned topics with the emphasis on achieving the best possible training programmes for NPP personnel

  9. From the chronicle of training of Dukovany NPP staff

    International Nuclear Information System (INIS)

    2005-01-01

    The long way the Dukovany NPP had to go before the plant staff was fully qualified and skilled is described. First the training concept was prepared, then the necessary training facilities were set up, lecturers and instructors were hired and trained, training programmes and training materials were developed, and ultimately the first training course was launched in 1979. A training NPP was constructed and a full-scope simulator of the Dukovany NPP was set up. The current status of organization of NPP staff training by the CEZ utility is highlighted. (author)

  10. Determination of the NPP Cernavoda reactor building seismic response

    International Nuclear Information System (INIS)

    Krutzik, N.J.; Rotaru, I.; Bobei, M.; Mingiuc, C.; Serban, V.

    1997-01-01

    Seismic input for systems and equipment installed in buildings depends on: - the seismic movement in free field on site; - the building movement in the soil; - the building deflection. The percentage of the 3 movements for the system and equipment input, depends on the position of the systems and equipment inside the building as well on the type of the foundation soil. The type of the foundation soil is important because if it is stiff it transfers a lot of energy to the building, energy which amplify the movement of the building on the top. If the foundation soil is soft, it accommodates the overall movement of the building in the soil, amplifying the movement to lower levels and the building response is attenuated if a resonance phenomenon between the whole building movement and the seismic excitation does not exist. This input is given with the design floor response spectra (FRS), in the logarithmic scale and seismic anchor movement (SAM). The design floor response spectra for NPP Cernavoda U1 Nuclear Building were determined in several stages starting with simple models (STICK type) without twisting movement and ending with detailed 3-dimensional models. From the point of view of dynamic behavior, the Reactor Building can be considered to be made up of 4 sub-structures: the containment building, internal structures containing separate elements such as the reactor vault, the fuel transfer structure and itself. Each sub-structure has its own movement (some of the structures present also some local effects) which combines with the overall movement of the building in the soil and the seismic excitation produce the total movement so that the response spectrum for each point of the sub-structure is specific. One should note that for structures which also show the twisting effect, the selection of the points on the floor, for the determination on the response spectra, is an engineering decision so that the response should be relevant for the equipment installed on the

  11. Training center of Rovenskaya NPP. The experience of creation

    International Nuclear Information System (INIS)

    Fedorov, O.M.; Aristov, B.N.

    1991-01-01

    Experience in creation of a teaching-training centre at the Rovno NPP, which uses means available at unified NPPs, at most is discussed. The centre hardware complex functions include the event filing and providing for user-friendly interface with NPP technical personnel under training. The system of personnel training at the Rovno NPP teaching-training centre gives an opportunity to analyze accidents and emergency conditions more completely and carefully. The taching analysis of failures and accidents by a NPP operators using the complex of the teaching-training centre hardware sufficiently improves knowledge of particular accidents

  12. 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)

  13. Cernavoda NPP Unit 2 and Romanian nuclear industry

    International Nuclear Information System (INIS)

    Mocanu Horia

    2001-01-01

    On 18 May 2001, in the presence of Mr. Adrian Nastase, the Prime-Minister of Romania, the presidents of AECL, ANSALDO and Director General of SN Nuclearelectrica, the commercial and management contract for completing the Cernavoda NPP Unit 2 was signed. This document stipulates the goal and the partners' commitments, leadership organization, the SN Nuclearelectrica's control of the Budget, costs for the technical assistance (around 180 specialists from abroad), as well as the costs of equipment supplied from Canada and Italy. Services and equipment supplied by Canada and Italy amounts up to around USD 300 millions. Efforts are currently undertaken to obtain a loan of USD 300 millions from EURATOM, beginning from 2003. An auction process, implying around 10 companies, is underway and by the completion of the process, in February 2002, the practical delivery of equipment will start. The so-far invested capital amounts around USD 650 millions while the capital funds remaining to be invested amounts up to about USD 689 millions. From the latter figure, around USD 100 millions represent the costs for heavy water and the initial nuclear fuel charging. The personnel dynamics is presented as well as problems relating with recruitment and salary policy. Romanian nuclear industry is engaged for supply of a series of important components. General Turbo SA, supplied already components of some tens USD millions for the turbogenerator complex. PETROTUB company from Roman, Romania supplied already one thousand tones of non-nuclear carbon steel tubing valued at about USD 300 millions. ARIO, Bistrita, Romania, has signed contracts valued at about USD 400,000 for non-nuclear reinforcing materials. Other companies like AVERSA SA and Ventilatorul SA supplied reliable equipment for Unit 1 and will continue to do the same for Unit 2. Contracts of over one million USD are carried on with VULCAN for carbon steel fittings and with TITAN Nuclear Equipment for components of the fueling

  14. The licensing process of the design modifications of Cernavoda 2 NPP resulting from the operating experience of CANDU plants

    International Nuclear Information System (INIS)

    Goicea, L.

    2005-01-01

    The CANDU 6 plant now under construction in Cernavoda include over two hundred significant improvements made in order to comply with current codes and standards and licensing requirements relative to the operating CANDU 6 in Romania. These evolutionary improvements are incorporated in CANDU 6 design taking advance of CANDU operating experience, of the designer company research and development and technical advances worldwide in order to further enhance safety, reliability and economics. This paper gives a general idea of the evaluation of the modifications of the Cernavoda 2 nuclear power plant against the design of Cernavoda 1 and states the safety principles and requirements which are the basis for this evaluation. (author)

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  16. Training human resource for NPP in Vietnam

    International Nuclear Information System (INIS)

    Nguyen, Trung Tinh; Dam, Xuan Hiep

    2008-01-01

    Vietnam will establish the first NPP in the near future. With us the first important thing is the human resource, but now there is no university in Vietnam training nuclear engineers. In EPU (Electric Power University), now we are preparing for training nuclear engineers. In this paper, we review the nuclear man power and the way to train the high quality human resource for NPP and for other nuclear application in Vietnam. (author)

  17. IAEA activities on NPP personnel training and qualification

    International Nuclear Information System (INIS)

    Kossilov, A.

    1998-01-01

    Activities of IAEA concerning training and qualification of NPP personnel consider the availability of sufficient number of competent personnel which is one of the most critical requirements for safe and reliable NPP operation and maintenance. Competence of personnel is essential for reducing the frequency of events connected to human errors and equipment failures. The IAEA Guidebook on Nuclear Power Plant Personnel Training and its Evaluation incorporates the experience gained worldwide and provides recommendations on the use of SAT being the best practice for attaining and maintaining the qualification and competence of NPP personnel and for quality assurance of training

  18. Management of maintenance activities at Cernavoda NPP

    International Nuclear Information System (INIS)

    Riedel, M.; Urjan, R.; Marinescu, S.; Corlan, L.

    2000-01-01

    After the Construction and Commissioning phases are over, the safety and economic performances of each nuclear unit are determined by the quality of its operation as well as by the combination of reliability and availability of the systems consisting the whole unit. Therefore, the value of a good maintenance program in making a safe and profitable operation is now widely recognized; all stations operating with excellent performance have well-defined policies and effectively administered programs to govern maintenance activities. The Cernavoda maintenance optimization initiative is derived from good practices suggested by such recognized bodies as the IAEA, INPO and EPRI. It should be noted that the program is evolving at this time and that this paper is an attempt to summarize the myriad of activities and plans required to finally implement the maintenance program. Although many of the elements of the program are in place, many are in various stages of completion. The main components of the program (policy's objectives, strategies used, specific subprograms, maintenance plans and their integration) are presented in brief along with the performance indicators used to assess the effectiveness of the program and maintenance activities. The new programs intended to be developed are also specified, as well as the main comments and recommendations received from IAEA experts. (author)

  19. Management of occupational exposure at Cernavoda NPP

    International Nuclear Information System (INIS)

    Chitu, C.; Popescu, I.; Simionov, V.

    2009-01-01

    Full text. Ionising radiations represent a particular risk associated with nuclear power plant operation. An effective and efficient radiation protection program must: - prevent the detriment of health due to deterministic effects; - keep all the exposures as low as reasonably achievable in order to limit the detriment of health due to stochastic effects. - provide safety and health conditions as good as other safe industries. Radiation protection of occupationally exposed workers is part of Health and Safety of Work Program. Effective dose limits, as recommended by ICRP and required by CNCAN regulations are reasonably low in order to avoid deterministic effects and to limit the probability of stochastic effects to an acceptable level. The health status of CNE Cernavoda employees is appropriately surveyed. There were not recorded cases of occupational diseases and / or other indicators of relevant biological effects in order to establish the specific response of the human body to the occupational illness risk factors. Starting since 2002 cytogenesis blood analysis for occupationally exposed individuals have been performed at the beginning of their employment and periodically for those working for more than five years in the plant. A number of up to 1900 employees have been investigated with no indication of genetic modifications. (authors)

  20. Human Resources Training Requirement on NPP Operation and Maintenance

    International Nuclear Information System (INIS)

    Nurlaila; Yuliastuti

    2009-01-01

    This paper discussed the human resources requirement on Nuclear Power Plant (NPP) operation and maintenance (O&M) phase related with the training required for O&M personnel. In addition, this paper also briefly discussed the availability of training facilities domestically include with some suggestion to develop the training facilities intended for the near future time in Indonesia. This paper was developed under the assumptions that Indonesia will build twin unit of NPP with capacity 1000 MWe for each using the turnkey contract method. The total of NPP O&M personnel were predicted about 692 peoples which consists of 42 personnel located in the head quarter and the rest 650 people work at NPP site. Up until now, Indonesia had the experience on operating and maintaining the nonnuclear power plant and several research reactors namely Kartini Reactor Yogyakarta, Triga Mark II Reactor Bandung, and GA Siwabessy Reactor Serpong. Beside that, experience on operating and maintaining the NPP in other countries would act as one of the reference to Indonesia in formulating an appropriate strategy to develop NPP human resources particularly in O&M phases. Education and training development program could be done trough the cooperation with vendor candidates. (author)

  1. NPP Cernavoda unit 2 economic viability: The challenge for an advanced financing scheme

    International Nuclear Information System (INIS)

    Condu, M.; Popescu, D.

    1999-01-01

    The completion of Cernavoda Unit-2 being no doubt, the viability of the project was analyzed and strengthened. Economic justification of the decision to complete Unit-2 is described, including assessment of its safety design guides, design requirements and engineering design solutions in the light of changes in codes, guideline, standards and actual regulatory requirements. Cost-benefit analysis demonstrates the economic viability of the project

  2. Fuel handling at Cernavoda 1 N.P.S. - commissioning and training philosophy

    Energy Technology Data Exchange (ETDEWEB)

    Standen, G W [AECL-Ansaldo Consortium, Cernavoda (Romania); Tiron, C; Marinescu, S [Regia Nationala de Electricitate (RENEL), Cernavoda (Romania); [Filiala Centrala Nuclearo Electrica (FCNE), Cernavoda (Romania)

    1997-12-31

    Efficient operation of a Candu nuclear power plant depends greatly on the reliable and safe operation of the fuel handling system. Successful commissioning of the system is obviously a key aspect of the reliability of the system and this coupled with a rigorous training programme for the fuel handling staff will ensure the system`s safe operation. This paper describes the philosophy used at Cernavoda 1 N.P.S. for the commissioning of the fuel handling systems and for the training of staff for operation and maintenance of these systems. The paper also reviews the commissioning programme, describing the milestones achieved and discussing some of the more interesting technical aspects which includes some unique Romanian input. In conclusion the paper looks at the organization of the mature fuel handling department from the operations, maintenance and technical support points of view and the long term plans for the future. (author). 1 fig.

  3. Fuel handling at Cernavoda 1 N.P.S. - commissioning and training philosophy

    International Nuclear Information System (INIS)

    Standen, G.W.; Tiron, C.; Marinescu, S.

    1996-01-01

    Efficient operation of a Candu nuclear power plant depends greatly on the reliable and safe operation of the fuel handling system. Successful commissioning of the system is obviously a key aspect of the reliability of the system and this coupled with a rigorous training programme for the fuel handling staff will ensure the system's safe operation. This paper describes the philosophy used at Cernavoda 1 N.P.S. for the commissioning of the fuel handling systems and for the training of staff for operation and maintenance of these systems. The paper also reviews the commissioning programme, describing the milestones achieved and discussing some of the more interesting technical aspects which includes some unique Romanian input. In conclusion the paper looks at the organization of the mature fuel handling department from the operations, maintenance and technical support points of view and the long term plans for the future. (author). 1 fig

  4. 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

  5. Perspectives of NPP personnel training in the future?

    International Nuclear Information System (INIS)

    Khess, R.E.

    1996-01-01

    Problems of the NPP personnel education are discussed during radical reorganization of the state regulation of energy production and distribution when nuclear energetics will appears in the market conditions. Effective methods of the NPP personnel training developed by the corporation GPU Nuclear are given. Potentials of the application of simulators and computerized programs for increasing the NPP personnel education efficiency are considered

  6. Maintenance training centre at NPP Paks, Hungary

    International Nuclear Information System (INIS)

    Babos, K.

    1996-01-01

    The lecture shows the feature of WWER-440/213 units maintenance, the existing maintenance training system, the necessity of the change in maintenance training system at NPP Paks. The author introduces the would-be maintenance training centre, the training facilities and the main tasks related to the maintenance training. (author)

  7. Summary of NPP personnel training in Czech Republic

    International Nuclear Information System (INIS)

    1996-01-01

    The preparation of NPP personnel is one of the most important phases of the process of construction, commissioning, operation and maintenance of nuclear power facilities. The objective is to improve personnel abilities so that they would be able to assure reliable, safe and economic operation of these facilities with high investment costs. It is the purpose of Nuclear Training Centre Brno (NTC Brno) to provide training and services which are responsive to the technological demands and emerging educational standards and criteria of the NPP and the nuclear industry. Fulfilling this purpose is a challenging task. The staff of NTC Brno, in a joint effort with NPP Dukovany and NPP Temelin, has responded to the challenge with comprehensive programs aimed at meeting customers needs. The programs are broadly based, yet flexible so that they can incorporate specific customer requirements

  8. Knowledge capture and preservation at Cernavoda Unit 2 Project

    International Nuclear Information System (INIS)

    Condu, M.; Chirica, T.; Popescu, D.; Marculescu, N.

    2007-01-01

    Full text: As it is known, Cernavoda Unit 2 - Romania, is a delayed nuclear power plant (NPP), started in early '80s, works were frozen in 1990 and resumed in 2003 under a management contract concluded by Nuclearelectrica, the Romanian nuclear utility, with Atomic Energy of Canada Ltd (AECL)-Canada and Ansaldo - Italy. This project has many specificities, including long time stored equipment, some works done 15 to 20 years ago; technology developments during these years; only couple of staff available from those initially involved; and a forthcoming project (Cernavoda Units 3 and 4) in its latest development phase. On top of that, like in other Eastern European countries, Nuclearelectrica is losing people due to salary issue and 'brain drain'. In the actual international situation where the nuclear energy contribution to energy mix is under reconsideration and where the demand for qualified personnel significantly exceeds the offer, it is estimated that maybe the biggest challenge of the forthcoming Cernavoda Units 3 and 4 would be availability of human resources. As Cernavoda Unit 2 Project goes towards a successful completion, all those who put lots of efforts and a difficult to overestimate contribution to overcome all challenges of this special Project will leave one after the other. Special attention is being given by Nuclearelectrica and the main contractors AECL and Ansaldo capturing the knowledge (both explicit and tacit) accumulated in these last almost five years and to leave to those who will continue the forthcoming Unit 3 and 4 Projects and to the nuclear industry in general. The objective on knowledge capture and preservation is to gather all experience and lessons learned during contracting, financing, constructing and commissioning of NPP Cernavoda Unit 2, with a focus on tacit knowledge and to asses potential improvements that might be applied in the forthcoming projects, in order to improve nuclear and economic performance. There are couple of

  9. Sitting Safety Aspects of Second Romanian NPP

    International Nuclear Information System (INIS)

    Mauna, T.

    2010-01-01

    The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units like the Wolsong applied design project for nuclear island. For the BOP parts the ASALDO-GE project was applied with the careful about the interface connection NSP requirements. The new NPP sitting studies began from 1982 in a serious manner as first part on Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. For develop the all package of the studies in concordance with the first IAEA Safety Standards recommendations. Till the 1982 the first mission of design and research multi-branch of specialists team was to adapt the NPP Cernavoda project having a open water cooling circuit to the new parameters of close water cooling circuit. But the team was looking at the other type of NPP for sitting. Also in the same time was studied the possibility of NSP foundation on hard less or soft soil foundation strata in connection with safety aspects. The close circuit of cooling water means others parameters of systems and need very large cooling towers. Also must be reconsidering the safety systems design and performance as new solution. In the south of Transylvania historical region in Romania the Olt River run from west to east having medium multi annual flow around 70 m3/s. The Olt River has a chain of small hydropower in operation and other planned. From geological and geophysical points of view two main faults, along the Olt river valley, one of this having seismically small activities was detected. Site region geotechnical studies show small quantity underground natural gas, salt and peat. The initial nuclear program has imposed 4 NPP units site near Olt River. Taking into account the orogenesis, water cooling needs and other local feature can't be built more than two NPP units on a site. This paper tries to reconsider the old analysis from the last IAEA Safety Standards point of view taking into account the new

  10. Installing the detritiation facility at Cernavoda NPP. Technical solutions and national participation

    International Nuclear Information System (INIS)

    Barariu, Gheorghe

    2002-01-01

    Generation and accumulation almost linear of tritium in the heavy water used as moderator and coolant in CANDU type reactors appears to be a drawback with implication upon the long term operation of the nuclear station. In the CANDU type reactors about 2400 kCi/GW(e) of tritium is generated annually. In case of CANDU-600 reactors as, those operating at Cernavoda NPP, the amount of tritium generated is 1500 kCi/y from which about 95% is found in moderator water what leads to an activity level of about 80-100 Ci/kg. Due to the specific working conditions about 85 Mg/y of D 2 O are eliminated from the circuits of which some 95% is recovered. About 30-50% of the radiation dose to which the operation personnel is exposed is due to the tritium from heavy water, while its contribution to the radioactivity released in the environment is about 20%. Detritiation ensures a radioactivity level due to the tritium contained in the moderator heavy water of about 5 Ci/kg in D 2 O moderator and about 1 Ci/kg in the coolant. Consequently, the radiation dose due to tritium is reduced three times while the tritium amount released in the environment is diminished by about 10 times. At present, the price of tritium is 2-3 USD/Ci what means that the tritium recovered from a CANDU reactor could reach a value of about USD 3 - 4.5 million/y. The detritiation procedures are based on catalyzed chemical exchange, heavy water electrolysis and deuterium distillation. Following experimentations and cost/benefit analyses the Institute for Cryogenics and Isotopic Technologies, ICSI, at Rm. Valcea, adopted for detritiation the procedure LPCE - CD, i.e. Liquid Phase Catalytic Exchange - Cryogenic Distillation. The procedure allows tritium transfer from the heavy water in gaseous deuterium in a column equipped with hydrophobic catalyst and phosphorous bronze packing. In the second stage of the technological process, the tritium is extracted from the gaseous phase by liquid deuterium distillation and

  11. 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

  12. Bases of updating of nuclear safety regulations for NPP in Romania

    International Nuclear Information System (INIS)

    Biro, Lucian; Serbanescu, Dan

    1999-01-01

    The paper presents the basic principles of reviewing and updating process of the regulatory environment pyramid. The main part of this review process refers to Cernavoda NPP Unit 2. However, there is an important impact on Cernavoda NPP Unit 1. The basic principles were defined in 1993/1994 when the licensing process for Unit 1 was resumed in order to be in accordance with the latest developments of Candu 600 worldwide and with the IAEA and NEA latest recommended documents and practices. After the licensing process for the Unit 1 was completed up to operation stage, CNCAN developed new updated regulations on nuclear safety and the regulatory pyramid in the framework of the RAMG PHARE project. CNCAN issued in 1996 the regulatory Policy for Unit 2, self-sustained and independent of future possible revisions of the regulations. The use of the concept of hierarchical systems, systematic review of safety criteria and objectives and margins along with the feedback from international and national experience on this topic ensured issuance of a reference document for future approach of nuclear safety in Romania. (authors)

  13. 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

  14. The role of research programs and commercial contracts for increase of economic competitiveness and development at INR Pitesti

    International Nuclear Information System (INIS)

    Petra, Nicoleta Mihaela; Ionila, Maria; Datcu, Mirela; Balan, Iosif Bogdan; Cretu, Ileana

    2008-01-01

    In the period in which globalization is increasing, one of the strategic objectives of the institute is to focus on those activities which help developing of services, products and technologies, applicable in nuclear industry, environment protection and medicine. One way to sustain INR activity is the technological transfer which ensures availability of research results by carrying out of R and D contracts in priority areas and of contracts with economical agents for the supply of services, products, technologies, such as: - Materials irradiation for medicine, industry and research; - Neutron Activation Analysis (NAA) and prompt gamma spectrometry for Cernavoda NPP - Unit 1; - Control and testing: non-destructive examination, functional tests of samples and equipment from Cernavoda NPP - Unit 1; - Characterization, conditioning and treatment of radioactive wastes for NPP- Cernavoda, Unit 1, Nuclear Fuel Plant (FCN) - Pitesti; - Measurement of isotopes concentration in environmental samples; -Corrosion experiments in static autoclaves and experiments regarding microbial corrosion for NPP Cernavoda Unit 1 and FCN Pitesti; - Nuclear consultancy for Cernavoda NPP - Unit 1 and Unit 2; - Stainless steel casks for radwaste; - Containers for heavy water; - Training and practice for students at the Universities of Pitesti, Bucuresti, Brasov. The paper presents the main areas where the results obtained in R and D programs can be applied, their implementation can be done, and the status of contracts and their importance for INR Pitesti and Romanian society development, as well. (authors)

  15. Degradation tests for C 32/40 concrete used for perimetral wall, reactor base and components of Cernavoda NPP containment, under thermal stress conditions and liner degradation

    International Nuclear Information System (INIS)

    Carlan, P.; Paraschiv, I.; Dinu, A.; Stanciulescu, M.; Olteanu, A. M.; Voica, I.; Stelian, R.; Buc, G.

    2016-01-01

    In order to evaluate the effect of thermal degradation on C 32/40 concrete used in nuclear constructions at Cernavoda NPP, continuous thermal stress tests were performed at 65, 80 and 100°C and cyclic thermal stress tests at 65°C in dry conditions. This paper presents the macroscopic properties of concrete, obtained after these treatments and also the microstructural changes that occur in the cement paste from the concrete composition, which has been tested in the same conditions as the concrete samples. Determinations performed for macroscopic properties of concrete included: compressive strength, loss of density, permeability and modulus of elasticity. Cement paste samples were analysed by XRD (for mineralogical composition) and SEM (for morphology). The obtained results shown an appropriate behaviour of the concrete used in this study; changes are insignificant and follow the normal evolution process of concrete, proving that concrete will preserve its safety functions, as part of the containment structure. (authors)

  16. 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

  17. NPP safety and personnel training. XII International conference. Abstracts. Volume 2

    International Nuclear Information System (INIS)

    2011-01-01

    The XII International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7 2011. The problems of personnel training for nuclear industry are discussed. The innovation nuclear systems and fuel cycle are considered. The much attention has been given to NPP radiation safety and radioecology issues. The recent high-speed computation and simulation methods used in reactor technology are presented [ru

  18. 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

  19. Simulator training and human factor reliability in Kozloduy NPP, Bulgaria

    International Nuclear Information System (INIS)

    Stoychev, Kosta

    2007-01-01

    This is a PowerPoint presentation. Situated in North Bulgaria, in the vicinity of the town of Kozloduy, near the Danube River bank, there is the Bulgarian Kozloduy Nuclear Power plant operating four WWER-440 and two WWER-1000 units. Units 1 and 2 were commissioned in July, 1974 and November, 1975, respectively. These were shut down at the end of 2003. Units 3 and 4 were commissioned in December, 1980 and May, 1982. They were shut down at the end of 2006 as a precondition for Bulgaria's accession to the European Union. The 1000 MW units 5 and 6 of Kozloduy NPP were commissioned in September, 1988 and December, 1993, respectively. Large-scale modernization have been implemented and now the units meet all international safety standards. The paper describes the multifunctional simulator Kozloduy NPP for the operational staff training. The training stages are as follows: - Preparatory; -Theoretical studies; - Training at the Training Centre by means of technical devices; - Preparation and sitting for an exam before a Kozloduy NPP expert commission; - Simulator training ; - Preparation to obtain a permit for a license, corresponding to the position to begin work at the NPP; - Exams before the Nuclear Regulatory Agency (NRA) and licensing; - Shadow training at the working place; - Permission for unaided operation. The following positions are addressed by the simulator training: - Chief Plant Supervisor; - Shift Unit Supervisor; - Senior Reactor Operator; - Simulator Instructor; - Controller physicist; -Senior Turbine Operator; - Senior Operator of Turbine Feedwater Pumps of Kozloduy NPP. Improving of training method led to a reduction of number of significant events while worldwide practice proves that improvement of engineering resulted in an increase in the percentage of events, related to human factor. Analysis of human reliability in 2005 and 2006 in cooperation with representatives from Great Britain and the Technical University in Sofia were worked on the DTI NSP B

  20. Report of the IPERS (International Peer Review Service) review mission for the Cernavoda nuclear power plant probabilistic safety evaluation (CPSE -PHASE B) in Romania 3 to 14 July 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This report presents the results of the IAEA International Peer Review Services review of the internal events Level 1 probabilistic safety assessment (PSA) for the Cernavoda, Unit 1 NPP. The review was based on the PSA documentation available and on intensive communications with the analysis team and representatives from the utility and the plant operator. 7 refs, figs, tabs

  1. Update on Cernavoda

    International Nuclear Information System (INIS)

    Boucher, R.

    1994-01-01

    The Cernavoda project in Romania is for five 700 MWe CANDU units. Construction began in 1980, but because of problems occurring, many of them associated with political, social, and economic changes in Romania, in 1991 the management of construction of Unit 1 was transferred from RENEL (Regia Nationala de Electricitate) to a consortium formed by AECL and Ansaldo. This had been one of the chief recommendations of a pr-operational safety review conducted by the I.A.E.A. By May 1994, Unit 1 was 93.4% complete, but progress was hampered by the need to rework a number of components, mainly piping. A continuous quality assurance program was in place. Ninety-two Romanian operators were trained by New Brunswick Power at Point Lepreau. As of the date of the conference, the target date for grid connection was March 1995, nine months ahead of the contractual target

  2. Cernavoda unit2 recirculated cooling water system transient analysis

    International Nuclear Information System (INIS)

    Nita, I. P.; Pancef, R.

    2015-01-01

    The paper is an approach to calculate the response of Cernavoda NPP Unit 2 RCW System to transient regimes during normal and abnormal regimes. Then one started to analyse the system response to reactor trip on class III and IV of power, LOCA on class IV of power, LOCA on class III power, LOIA on class IV of power, and LOIA on class III power. Moreover, one analysed the system transient due to requirement of changeover of a RCW operating pump, planned and unplanned changeover. This is the first transient approach to this system that took in consideration all building of the system, obtaining a very large system model, with over 900 pipe, 4 pumps, 50 consumers, 21 control valves. The changeover procedure was required to be analysed in order to change the nominal operating mode for Unit 2, from current 2 pumps in operation to 3 pump operations during summer operating mode. (authors)

  3. Contributions to a methodology for periodical verification of the parameters of the control systems at Cernavoda Nuclear plant Unit 1

    International Nuclear Information System (INIS)

    Tapu, Cornel; Anescu, George

    1998-01-01

    A model identification methodology for periodical verification of the regulating system parameters at Cernavoda NPP Unit 1 was developed. As support to this methodology, the computer program MODELIDENT was implemented in the Java programming language. This program is used for off-line evaluation of the real regulating systems characteristic parameters using an identification algorithm which takes as input data the system response collected for different input excitation signals, a structurally similar model of the analyzed regulating system, and some starting guess value of the unknown parameters. The real values of the parameters are determined during MODELIDENT program execution by applying an iterative algorithm and afterwards are retained as nominal reference values. The success of the identification algorithm is strongly dependent on how appropriately the structure of model's transfer function is chosen. By repeating periodically the identification method, using newly collected data from the process, the current value of the parameters are determined. Any deviations of the new values relative to the nominal reference values are interpreted as de-calibration of the control equipment and in this case corrective maintenance actions have to be taken. With the implementation of the presented methodology at Cernavoda NPP Unit 1 we can make the statement that the preventive maintenance activity is gaining a predictive feature, which can lead to the elimination of major degradation possibilities in the performances of the RS equipment and consequently to increase the NPP availability. On the basis of the experience gained in the practical application of the presented methodology we expect that the identification method will also have beneficial effects in the optimal control of the process systems and also in the activity of Full Scope Simulator software maintenance (the reference values of the identified parameters being used for fine tuning of the simulation models

  4. 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)

  5. Organizational aspects of NPP operator training

    International Nuclear Information System (INIS)

    Vel'chinskij, V.I.

    1992-01-01

    The main points of the document regulating the selection, prepation, permission for work and in-service control of NPP personnel developed on the basis of the IAEA requirements are considered. The specialists engaged for work are subjected to qualification, medical, professional, psychological and psychophysiological selections. The scheduled monthly instructive lessons are conducted during the work. The antiaccident and fire-fighting trainings are organized not rarely than twice in three months

  6. Training, education and qualification of NPP operating personnel in the Netherlands

    International Nuclear Information System (INIS)

    de Vrey, G.A.

    1987-01-01

    This paper outlines the organization and the requirements of the training, education and qualification of NPP operating personnel in the Netherlands. It describes the implementation of a formally required scheme of personnel qualification after TMI, and the current practice as developed by the training staff of both Dutch nuclear power plants. Attention is given to the specific circumstances and problems in the Netherlands, and the resulting program. The licensing criteria for control room operating personnel are discussed, including the level of government involvement. Measures are described to improve the approach to training of NPP personnel involved in safety relevant activities. Finally, some ideas are given for strategies to cope with adverse stress situations

  7. Cernavoda nuclear power plant: Modifications in the fire protection measures of the CANDU 6 standard design

    International Nuclear Information System (INIS)

    Covalschi, V.

    1998-01-01

    Having as purpose the improvement of fire safety at the Cernavoda NPP - both in the prevention and the protection aspects in the case of fire - we implemented some modifications in the CANDU 6 standard design. These improvements are inspired, mainly, from two sources: the world-wide achievements in the field of fire protection techniques, introduced in nuclear power plants since the middle of 70's, when the CANDU 6 design was completed; the national practice and experience in fire protection, usually applied in industrial objectives (conventional power plants, in particular). The absence of any incident may be considered as a proof of the efficiency of the implemented fire preventing and protection measures. (author)

  8. Development of NPP personnel training system in Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Tarykin, V. [Operation Personnel Training Department, Khmelnitsky NPP, Training Center, Neteshin 30100, Khmelnitsky region (Ukraine)]. E-mail: tarykinv@ukr.net

    2005-07-01

    Modern personnel training and retraining system is a guarantee of NPPs safe reliable operation. Since the time when independence of Ukraine was proclaimed personnel training system was created directly at NPPs. This system is based on the latest legislation framework, developed subject to IAEA recommendations, gained international experience in the field of personnel training in view of increased demands to personnel qualification. Training Centers, formed at each plant, form one of the main components of NPP personnel training. Personnel training at Training Centers is performed in accordance with standard programmes. Simulator training base was created by joint efforts of specialists from the USA, Russia and Ukraine. Establishing manager training system and replacement reserves for National Nuclear Energy Generating Company 'ENERGOATOM' (NNEGC 'ENERGOATOM') managerial personnel, including training programme and training materials development, teacher selection and training, is under way. (author)

  9. 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

  10. On application of the systematic approach to training in Qinshan NPP

    International Nuclear Information System (INIS)

    Wang Riqing

    1997-01-01

    The author describes the feature of systematic approach to training and introduces the situation about using the approach for training operation and maintenance personnel in Qinshan NPP. The final part of paper shows that there are still some problems worthy of serious consideration in application of the systematic approach to training in nuclear power plant

  11. Students education and training for Slovak NPP

    International Nuclear Information System (INIS)

    Lipka, J.; Slugen, V.; Hascik, J.; Miglierini, M.

    2004-01-01

    Slovak University of Technology is the largest and also the oldest university of technology in Slovakia. Surely more than 50% of high-educated technicians who work nowadays in nuclear industry have graduated from this university. The Department of Nuclear Physics and Technology of the Faculty of Electrical Engineering and Information Technology as a one of seven faculties of this University feels responsibility for proper engineering education and training for Slovak NPP operating staff. The education process is realised via undergraduate (Bc.), graduate (MSc.) and postgraduate (PhD.) study as well as via specialised training courses in a frame of continuous education system. (author)

  12. Cernavoda CANDU severe accident evaluation

    International Nuclear Information System (INIS)

    Negut, G.; Marin, A.

    1997-01-01

    The papers present the activities dedicated to Romania Cernavoda Nuclear Power Plant first CANDU Unit severe accident evaluation. This activity is part of more general PSA assessment activities. CANDU specific safety features are calandria moderator and calandria vault water capabilities to remove the residual heat in the case of severe accidents, when the conventional heat sinks are no more available. Severe accidents evaluation, that is a deterministic thermal hydraulic analysis, assesses the accidents progression and gives the milestones when important events take place. This kind of assessment is important to evaluate to recovery time for the reactor operators that can lead to the accident mitigation. The Cernavoda CANDU unit is modeled for the of all heat sinks accident and results compared with the AECL CANDU 600 assessment. (orig.)

  13. Training in fundamentals of radiological coverage in Laguna Verde NPP

    International Nuclear Information System (INIS)

    Lara H, M. A.

    2014-10-01

    In 2010, the Institute of Nuclear Power Operations (INPO) celebrates the Knowledge Transfer and Retention Workshop, an event where nuclear regulators and operators presented the strategies that various NPP to worldwide were implemented to mitigate the consequences of this generational change and take advantage of it, the trend in the presented works was the same: the generational change occurs in a faster way that the transfer of knowledge, the future was already here and many NPP had not been adequately prepared to train its nuclear technicians and engineers in the tasks demanded by the industry of them, so in addition to preparing these workers to forced marches was necessary to establish strategies to retain at more experienced staff in the industry. The Laguna Verde NPP has not been exempt to this process; the preparation of personnel squares to replace those that reaching retirement age in the Comision Federal de Electricidad (CFE) has become extensive in the last five years, sometimes leading to have personnel covering functions without an alternate to the next lower position, the cause? Not enough staff. In the specific case of radiation protection (Rp) the time required for obtaining the status of Rp technician according to the ANSI/ANS 3.1 standard is 2 years, one of the tasks that most occupies part of these two years is training in radiological coverage, this training requires a mix of knowledge and experience, recently one of the concepts used for training in Rp is the evaluation and management of the radiological risk, topic that is considered in this technical work. (Author)

  14. Experience in development and implementation of Control Room continuing training programme at Ignalina NPP

    International Nuclear Information System (INIS)

    Peradze, K.

    2002-01-01

    Based on the same SAT principles each NPP (or operating organisation) goes by its own way, which is defined by available resources, assistance, NPP operational conditions, including policy, economics and public opinion. There were several groups of factors, which are very important to provide quality of training- Time, Human Resources and material resources. We pay especial attention to simulator training. In different conditions personnel behaviour is defined by knowledge, rule or skills. It is very difficult to develop unknown to personnel scenarios. But sometimes- real events not described in plant procedures take place at Nuclear Power Plants. Therefore during NPP events analysis we pay a especial attention searching for situation when knowledge or rule defines personnel behaviour. To provide analysis and statistics of Control Room Personnel training at INPP simulator we developed 'INPP events computer data base'. (author)

  15. The FMEA Analysis for Fuel Handling System at Cernavoda Unit 2

    International Nuclear Information System (INIS)

    Park, Jin Hee; Kim, Tae Woon; Rhee, Bo Wook; Yoon, Chul; Kim, Hyeong Tae; Cho, In Gil; Kim, Seong Ho

    2006-01-01

    A Nuclear Safety Evaluation was performed by an independent assessor at the request of the regulatory authority CNCAN (Comisia Nationala pentru Controlul Activitatilor Nucleare. National Committee for Nuclear Activities Control in Romania) to provide an independent overview of all the nuclear safety aspects of Cernavoda Unit 2 under construction and an expert opinion whether the completed Cernavoda Unit-2 Nuclear Power Plant would satisfy current Western European nuclear safety objectives and practices. A report was produced (Cernavoda 2 Nuclear Safety Expert Project, 'Task 10 . Safety Evaluation Report', A.F.Parsons, NNC Limited, December 2001) and contains recommendations either mandatory or advisory. The FMEA study, one of the mandatory recommendations, is performing now for fuel handling system and radioactive waste handling system for Cernavoda unit 2 in Romania sponsored by KHNP. In this paper, only the FMEA study for fuel handling system is presented

  16. New EDF approach to the mentification of NPP personnel training needs

    International Nuclear Information System (INIS)

    Hazet, Jean-Christophe

    2003-01-01

    The EDF ambition today is to be among the best electricity producers in the world. To do so, we have to take more responsibilities, to motivate and to give our employees a better level of competence, and to make them more involved in the culture and the success of our company. In order to reach these objectives a deeper analysis of the NPP training needs must be completed. Our answer, named 'Local Competencies Development System' (LCDS) consists in implementing a large decentralisation of the competencies management, done by the EDF Production Department in conjunction with the EDF Training Department. It takes place in a logical approach bound up with the historical development of our nuclear program. In addition to this LCDS a new organization of training centers instructors, in dedicated training teams, has been implemented in order to co-ordinate the different actions directly with the NPP. The purpose of this presentation is to take into account the LCDS on the operation personnel training side, a similar organization has been implemented for the maintenance side

  17. Use of operator training and simulating complexes for development of NPP APCS

    International Nuclear Information System (INIS)

    Malkin, S.D.; Rakitin, I.D.; Sivokon', V.P.

    2002-01-01

    The evolution of NPP educational facilities - from systems of training of personnel to power simulating systems for the development of Automatic Process Control System (APCS) and safety analysis is followed. High efficiency of simulating systems application for the development of NPP APCS including optimization of man-machine system interface was shown by experiments of USA, France, Japan, United Kingdom, conforming examples were given [ru

  18. Introduction of the SAT based training programs at Paks NPP

    International Nuclear Information System (INIS)

    Kiss, I.

    1998-01-01

    An introduction of the SAT based training programs at Paks nuclear power plant is described in detail, including framework of project operation; project implementation; process of SAT applied at Paks NPP and the needs of its introduction

  19. Experience of Hungarian model project: 'Strengthening training for operational safety at Paks NPP'

    International Nuclear Information System (INIS)

    Kiss, I.

    1998-01-01

    Training of Operational Safety at Paks NPP is described including all the features of the project including namely: description of Paks NPP, its properties and performances; reasons for establishing Hungarian Model Project, its main goals, mentioning Hungarian and IAEA experts involved in the Project, its organization, operation, budget, current status together with its short term and long term impact

  20. 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

  1. Students education and training for Slovak NPP

    International Nuclear Information System (INIS)

    Slugen, V.; Lipka, J.; Hascik, J.; Miglierini, M.

    2005-01-01

    Slovak University of Technology is the largest and also the oldest university of technology in Slovakia. It is certain that more than 50% of the highly-educated technicians who are currently working in the nuclear industry have graduated from this university. The Department of Nuclear Physics and Technology of the Faculty of Electrical Engineering and Information Technology as one of the seven faculties of this University feels the responsibility to impart proper engineering education and training for Slovak NPP operating staff. The education process is realised via undergraduate (BSc), graduate (MSc) and postgraduate (PhD) study as well as via specialised training courses within the framework of a continuous education system. (author)

  2. The Cernavoda project - past and future

    International Nuclear Information System (INIS)

    Glodeanu, F.; Campureanu, T.; Chirica, T.; Popescu, D.

    1995-01-01

    The history of the Cernavoda nuclear power station in Romania is traced. It was conceived in 1977 as five unit CANDU-6 station and agreements were concluded on engineering, procurement and financial assistance with Atomic Energy of Canada Ltd (AECL) and Ansaldo of Italy. Delays in construction were created from the first, however, by efforts to manufacture as many components as possible in Romania, unfamiliarity with nuclear project management and the disadvantages of a highly centralised economy. Political changes since December 1989 have led to a new approach to project implementation. The Romanian Electricity Authority (RENEL), signed a new contract with AECL and Ansaldo in August 1991 to perform the project management for the completion of Cernavoda 1. The project has progressed very well and by the beginning of 1995 more than 90% of the plant systems were ready for commissioning and a full operating shift was in place. As a second phase of the nuclear power programme RENEL plans to complete Cernavoda 2, the construction of which was suspended at 30% completion. The three other units will be preserved in their present preliminary stage of construction up to 2000 while finance is sought for their completion. Nuclear power is seen as an environmentally clean means of meeting Romania's growing energy demand as the economy develops. (UK)

  3. Virtual reality in design, planning, operation and training related to the decommissioning of the Chernobyl NPP

    International Nuclear Information System (INIS)

    Mark, N.-K.; Johnsen, T.; Meyer, G.; Owre, F.

    2007-01-01

    Virtual Reality in refueling operation and maintenance training at Leningrad NPP has been recognized by Chernobyl NPP. Institute for Energy Technology's is establishing now the Chernobyl Decommissioning Visualization Centre to be used for planning and training the dismantling procedures in addition to presenting it to the authorities and the public. It will be ready in 2007. The first scenario will be the dismantling of the refueling machines

  4. SAT for NPP personnel training in Spain

    International Nuclear Information System (INIS)

    Gonzalez, M.

    1995-01-01

    The SAT process objectives as applied to Spanish NPPs are: Perform JTA for selected job positions at the NPPs; develop the associated training plans; develop training support media; prepare training instructors as teachers and as task analysts; develop a SAT database. A lesson-learned from the task assessments conducted at Spanish NPPs is that the final task list should be obtained with full participation of workers so that they feel the final training plan has been developed taking into account their own opinion and experience. The breakdown of the tasks into its elements and the concordant job performance measure was presented. The process of determining knowledge and skills associated with the task elements and the structure and use of the taxonomy codes (for component, system, and academic skills and knowledge) was shown and explained. Based on the Spanish experience, the average time devoted to analyze a complete task is 5.33 person-hours per task. This data has permitted training and plant management to allocate the NPP human resources to support the analysis phase of SAT (which can be very time-consuming)

  5. 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

  6. NPP Krsko simulator training for operations personnel

    International Nuclear Information System (INIS)

    Pribozic, F.; Krajnc, J.

    2000-01-01

    Acquisition of a full scope replica simulator represents an important achievement for Nuclear power Plant Krsko. Operating nuclear power plant systems is definitely a set of demanding and complex tasks. The most important element in the goal of assuring capabilities for handling such tasks is efficient training of operations personnel who manipulate controls in the main control room. Use of a simulator during the training process is essential and can not be substituted by other techniques. This article gives an overview of NPP Krsko licensed personnel training historical background, current experience and plans for future training activities. Reactor operator initial training lasts approximately two and a half years. Training is divided into several phases, consisting of theoretical and practical segments, including simulator training. In the past, simulator initial training and annual simulator retraining was contracted, thus operators were trained on non-specific full scope simulators. Use of our own plant specific simulator and associated infrastructure will have a significant effect on the operations personnel training process and, in addition, will also support secondary uses, with the common goal to improve safe and reliable plant operation. A regular annual retraining program has successfully started. Use of the plant specific simulator assures consistent training and good management oversight, enhances conformity of operational practices and supports optimization of operating procedures. (author)

  7. Time depending assessment of low and intermediate radioactive waste characteristics from Cernavoda NPP

    International Nuclear Information System (INIS)

    Mateescu, S.; Pantazi, D.; Stanciu, M.

    2002-01-01

    Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Power Plant must be well known from the point of view of contained radionuclide activity, during all steps of their processing, storage and transport, to ensure the nuclear safety of radioactive waste management. As in intermediate storage stage, the waste activity changes by radioactive decay and nuclear transmutation, the evolution in time of these sources is necessary to be assessed, for the purpose of biological shielding determination at any time. On the other hand, during the transport of waste package at the repository, the external dose rates must meet the national and international requirements concerning radioactive materials transportation on public roads. In this paper, a calculation methodology for waste characterization based on external exposure rate measurement and on sample analysis results is presented. The time evolution of waste activity, as well as the corresponding shielding at different moments of management process, have been performed using MICROSHIELD-5 code. The spent resins proceeded from clean-up and purification systems and solutions from decontamination have been analyzed. The proposed methodology helps us to assess radiation protection during the handling of low and intermediate - level radioactive waste drums, ensuring safety conditions for the public and environment.(author)

  8. The main steps of the Romanian nuclear power program development - Accumulated experience

    International Nuclear Information System (INIS)

    Chirica, T.; Popescu, D.; Condu, M.; Vatamanu, M.

    1998-01-01

    The paper presents a historical summary of the Romanian Nuclear Power Program development, providing details for the main criteria and principles the Program was based upon, the contracts signed with the foreign partners to implement it, and the national participation (site contractors, suppliers and design organizations). The effect of the equipment assimilation program on the NPP Cernavoda (5x700 MWe) and especially on Unit 1 schedule and performance is analyzed. Further on the impact of the transition from centralized to a market economy over the Romanian Nuclear Power Program development is analyzed, providing information's on its actual status and perspectives for the next 20 years. A description of the NPP Cernavoda Unit 1 actual progress and of the main steps performed by RENEL to get finance to complete NPP Cernavoda Unit 2 is included. Finally there is summarized the accumulated experience, and its feed back on RENEL strategy to complete NPP Cernavoda Unit 2. (author)

  9. Example of an application of systematic approach to training. Paks NPP Ltd

    International Nuclear Information System (INIS)

    Bajor, L.

    1998-01-01

    In order to show a practical example of how Hungarian Maintenance program works implementation of SAT based training of primary circuit field operator is described in detail as implemented at Paks NPP

  10. Example of an application of systematic approach to training. Paks NPP Ltd

    International Nuclear Information System (INIS)

    Szabo, Z.

    1998-01-01

    In order to show a practical example of how Hungarian Maintenance program works implementation of SAT based training of primary circuit valve maintenance senior mechanic is described and explained in detail as done at Paks NPP

  11. Classification and optimization of training tools for NPP simulator

    International Nuclear Information System (INIS)

    Billoen, G. van

    1994-01-01

    The training cycle of nuclear power plant (NPP) operators has evolved during the last decade in parallel with the evolution of the training tools. The phases of the training cycle can be summarized as follows: (1) basic principle learning, (2) specific functional training, (3) full operating range training, and (4) detailed accident analyses. The progress in simulation technology and man/machine interface (MMI) gives the training centers new opportunities to improve their training methods and effectiveness in the transfer of knowledge. To take advantage of these new opportunities a significant investment in simulation tools may be required. It is therefore important to propose an optimized approach when dealing with the overall equipment program for these training centers. An overall look of tools proposed on the international simulation market shows that there is a need for systematic approach in this field. Classification of the different training tools needed for each training cycle is the basis for an optimized approach in terms of hardware configuration and software specifications of the equipment to install in training centers. The 'Multi-Function Simulator' is one of the approaches. (orig.) (3 tabs.)

  12. The dependence level analysis between the human actions in NPP Operation

    International Nuclear Information System (INIS)

    Farcasiu, M.; Nitoi, M.; Apostol, M.; Florescu, G.; Prisecaru, Ilie

    2009-01-01

    The Human Reliability Analysis (HRA) is an important method in Probabilistic Safety Assessment (PSA) studies and offers desirability for concrete improvement of the man - machine - organization interfaces, reliability and safety. An important step in HRA is the dependence level analysis between the human actions performed by the same person or between the actions performed by different persons, step in quantitative analysis of the human errors probabilities. The purpose of this paper is to develop a model to analyze the dependence level between human actions for Nuclear Power Plant (NPP) operation. The model estimates the conditional human error probabilities (CHEP) and joint human error probabilities (JHEP). The achieved sensitivity analyses determine human performance sensibility to systematic variations for dependence level between human actions. The human error probabilities estimated in this paper are adequate values for integration both in HRA and in PSA realized for NPP. This type of analysis helps in finding and analyzing the ways of reducing the likelihood of human errors, so that the impact of human factor to systems availability, reliability and safety can be realistically estimated. In order to demonstrate the usability of this model an analysis is performed upon the dependences between the necessary human actions in mitigating the consequences of LOCA events, particularly for the case of Cernavoda NPP. (authors)

  13. Manufacturer's part in NPP personnel training in the FRG

    International Nuclear Information System (INIS)

    Martin, H.D.

    1987-01-01

    This paper describes the regulatory guidelines and the training and retraining procedures and programs for NPP personnel in the Federal Republic of Germany. Reference is also made to the three years dual workshop/factory and classroom education of skilled workers in Germany. KWU as a turnkey manufacturer of Nuclear Power Plants holds the nuclear operating license towards the authority after first fuel loading of a new plant. In this respect it has extensive overall training obligations not only towards its customers but also with regards to its own shift personnel during nuclear power operation up to commercial operation and hand over of the plant. KWU's philosophy of training, its infrastructure, its various obligations and services are described for new plants as well as with regards to retraining for older plants

  14. Future needs in radiation protection training for NPP workers of Slovenia

    International Nuclear Information System (INIS)

    Kozelj, M.; Bogovic, T.

    1999-01-01

    Short review of history of radiation protection training for NPP workers in Slovenia and legal requirements regarding this field are presented. Courses developed in co-operation between Milan Copic Nuclear Training Centre and Krsko Nuclear Power Plant are briefly described and their implementation presented. Using available data we have predicted probable number of courses and participants in forthcoming years. Some results from inquiry on courses for regularly exposed workers are presented, enabling us to modify courses according to participants' needs.(author)

  15. Approach to development and use of PSA Level 2 analysis for the Cernavoda nuclear power plant

    International Nuclear Information System (INIS)

    Turcu, I.; Deaconu, R.; Radu, G.

    1998-01-01

    This paper first describes the status of PSA activities for the Cernavoda NPP and the extension of the PSA work to include Level 2 PSA. Important characteristics of this reactor type for Level 2 PSA are outlined. Due to the specific layout of the CANDU reactor the evolution of severe accidents is considerably different to vessel type LWRs. Accidents can be roughly categorized into three categories, ''''severe accidents'''' which lead to the loss of core structural integrity, delayed loss of core structural integrity as a consequence of the loss of heat sinks, and fuel channel failures. The current work for modelling accident progression in the core region is described. The elements for the Level 2 PSA including definition of PDSs, probabilistic containment logic and source term calculation are outlined. It is pointed out that uncertainties have to be considered which are contained in the models to bridge knowledge gaps. For this purpose sensitivity studies will be carried out for key modelling assumptions. (author)

  16. On-the-job training and qualification of nuclear power plant personnel. OJT at the Loviisa NPP

    International Nuclear Information System (INIS)

    1996-01-01

    On-the-job training and qualification process of nuclear power plant personnel is described, including the following issues: educational system of technical studies in Finland; training methods at the Loviisa NPP; on-the-job training of control room operators,field operators, maintenance personnel, other groups of the plant; qualifying examinations for different jobs

  17. Prediction of Axial and Radial Creep in CANDU 6 Pressure Tubes

    International Nuclear Information System (INIS)

    Radu, Vasile S.

    2013-01-01

    Status and proposals: 1. A review of literature concerning on the in-reactor deformation of PTs has been carried ouţ. 2. A model based on MFNN has been proposed to assess the radial and axial creep of CANDU 6 PTs. 3. Preliminary discussion with Cernavoda NPP (Romania) has been lunched, and now the preparation of official documents (collaboration in providing the inspection data from fuel channel in Unit 1 and 2) are in progress. 4. Further activities: • Improvement MFNN to accommodate complex data base (eventually with many variables) for radial and axial in-reactor deformation PT, and to satisfy the requirements from NPP Cernavoda and hopefully from present CRP database; • To build-up a database by running the creep equations (if the creep constants are provided by AECL); training of MFNN on them and to qualify it as a tool for PT in-reactor deformation prediction

  18. 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

  19. Maintenance philosophy and program at Cernavoda NPP

    International Nuclear Information System (INIS)

    Bobos, M.; Enciu, G.

    1994-01-01

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

  20. Financing arrangements for nuclear power projects - past and present experience and future expectations

    International Nuclear Information System (INIS)

    Ispas, G.

    2004-01-01

    The intent of the author of the present paper is to demonstrate, in a practical manner, the role of the past experience and the new approaches of the nuclear projects financing, especially as nuclear generation financing in developing countries involves complex issues that need to be fully understood and dealt with by all the parties involved, namely: high investment costs, generally long construction periods, a high degree of uncertainty with respect to costs and schedule and to public acceptance, particularly because of safety, waste disposal and non-proliferation issues. Moreover, as many associations whose activities consist of ensuring and facilitating at different levels the exchange of knowledge between generations, i.e.: European Nuclear Society (ENS) Young Generation, North American Young Generation in Nuclear (NA-YGN), the goal of the paper is also to outline the importance of the education in nuclear field, i.e. training a young team of specialists to be ready to take over the movement and responsibility in continuing the further development of nuclear program in Romania, mainly with view to the Financing Arrangements for Nuclear Power Projects. The first part of the paper is referring to general financing procedures, while the second part is focusing on a case study related to the: past experience the financing scheme of Cernavoda NPP Unit 1, present or actual experience ongoing financing issues for Cernavoda NPP Unit 2 and potential future shared contribution to the financing of the next Cernavoda NPP units.(author)

  1. Evaluating external costs of human health and environmental impacts using IAEA model SIMPACTS

    International Nuclear Information System (INIS)

    Bobric, Elena; Jelev, Adrian

    2005-01-01

    SIMPACTS (Simplified Approach for Estimating Impacts and External Costs of Electricity Generation) model developed at the International Atomic Energy Agency is a powerful and convenient tool for evaluating external costs induced by different energy sources. The model was developed for industrial countries and for developing countries as well where studies of alternatives of sustainable energy policies are conducted. The SIMPACTS allow the decision making factors involved in energy policy to have reasonable estimates of environment impacts and relating costs appealing to a rather low number of input parameters. The paper aims at analyzing by means of SIMPACTS the environmental impact produced by Cernavoda NPP operation in two cases: a) the impact of the Cernavoda NPP itself; b) the impact of an hypothetical coal based power plant of the same power level and located on the Cernavoda NPP site. The SIMPACTS modules AIRPACTS and NUCPACTS were applied to assess the impacts on human health, agricultural crops and building materials from exposure to routine atmospheric emissions and as well to quantify and value the adverse effects on human health due to routine atmospheric release of radionuclides from the NPP, via radioactive waste ground disposal or resulting from accidents in nuclear facility, respectively. The conclusion of this study based on SIMPACTS model application to assess the health effects and damage cost per year is that the Cernavoda NPP presents the lower health effects and damage cost comparing with power plants of other types

  2. Comparison of Domestic Safety Review and European Union(EU) Stress Test After Nuclear Accident in Fukushima Daiichi NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Hwa Sung; Kim, Jin Weon [Chosun University, Gwangju (Korea, Republic of)

    2016-05-15

    The European Union(EU) nuclear regulators group established stress test criteria and procedures, and utilities performed a self-review in accordance with those criteria and procedures. For Wolsung nuclear unit-1,the stress test was additionally conducted for deciding the continued operation of NPP, even though the safety review had been conducted after Fukushima NPP accident. Thus, this study is to compares the process, criteria, and results of the safety review performed in domestic NPPs and EU stress test performed in Cernavoda NPP. From the comparisons, the effectiveness and necessity of the stress test to decide the continued operation of NPPs is discussed. and the improvement items for safety enhancement are derived. The comparison showed that the process and review criteria of EU stress test was more systematic and specific than those used in domestic NPPs. But it was indicated that the improvement items resulted from the safety review performed in domestic NPPs are more comprehensive and powerful than EU stress tests (Cernavoda NPP) results. EU stress test for Cernavoda NPP evaluated in 3 fieldsand derived 13 design change items. The 50 improvement items derived from domestic safety review were including the contents of these 13 items.

  3. Compex system for teaching and training operators for TPP and NPP power units

    International Nuclear Information System (INIS)

    Tsiptsyura, R.D.

    1985-01-01

    Requirements, taken as a principle for constructing the system for operator teaching and training (OTT), have been formulated on the basis of investigation of operators' work at TPP and NPP power units. Functional structure and a structural block-diagram for OTT are built. As a criterion, which determines the structure of any trainers, being a part of OTT a requirement has been chosen satisfying the correspondence beetween habits developed with the help of trainers and habits of real operators' work. Results of analysis permit to confirm that refusal or under statement of the role of any stage of operator training leads to reduction of quality of his training

  4. The settlement Cernavoda III culture on the site Bubanj near Niš

    Directory of Open Access Journals (Sweden)

    Milanović Dragan

    2011-01-01

    Full Text Available Archaeological investigations carried out between 2008 and 2010 in the east sector of site Bubanj near Niš (Plan 1; Figs. 1-3 confirmed the existence of horizon of the Cernavoda III culture. In features 22, 23 and 31, which are the remains of settlement buildings, have been found archaeological material mostly pottery vessels, which according to style of decoration, technological and morphological characteristics could be ascribed to the initial period of late Eneolithic. Also, the dwelling structures of Krivodol-Salcuþa-Bubanj cultural complex have been recorded in the layer of brown soil with the remains of above mentioned Cernavoda III buildings. In the vertical stratigraphy of trench I (Fig. 4 the mentioned layer was encountered immediately under the layer of whitish/gray ashy soil and thin layer of compact soil of gray color (Fig. 5, which date from the advanced phases of the late Eneolithic and above the early Eneolithic layers. The settlement features recorded during 2009 excavations are parts of the structures from the settlement of Cernavoda III culture (Fig. 6; T. I-III. Feature 22 is section of devastated probably aboveground building, feature 23 is shallow pit and feature 31 is most probably the rubbish pit. Very similar stratigraphy of the site had been recorded by investigations of M. Garašanin in 1954. In the layer of brown soil, the material of Cernavoda III culture was discovered in level III, and in level IV both Cernavoda III and the material of the earlier Krivodol-Salcuþa-Bubanj cultural complex was recorded. These building horizons are at different depths within approximately same area of the trench and have been identified on the basis of considerable amount of daub and stone, two floor levels, wooden building material and fragmented pottery vessels (T. IV-VI. Despite the lack of technical field documentation remains of one above ground structure could be identified at level III according to descriptions from field

  5. Leningrad NPP full scope simulator - new generation tool for training and analysis

    International Nuclear Information System (INIS)

    Malkin, S.D.; Shalia, V.V.; Rakitin, I.D.; Khoudiakov, M.M.

    1999-01-01

    Recent developments of Russian Research Center 'Kurchatov Institute' are aimed at the soonest and minimum expenditure's creation of modern high-performance means for personnel's training and regular restraining and also at the development of means of modeling, safety analysis and operators' support with severe accidents to be included. In this view, the most elaborated one is the Training Support Center (TSC) created at the Leningrad NPP, Sosnovy Bor, Russia. To be applied in this center, GSE Systems of USA and RRC 'Kurchatov Institute' have jointly developed the Total Training System that incorporates full-scope simulator; analytical full-scope simulator, expert system, interactive system, psycho-physiological system; and training support programs. Mathematical models creating and special software development were the responsibility of RRC 'Kurchatov Institute', the hardware and general purpose software were the responsibility of GSE Systems. (author)

  6. 'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Bilegan, C. Iosif

    2001-01-01

    Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

  7. 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)

  8. Programmes design for Bohunice NPP personnel other than control room operators

    International Nuclear Information System (INIS)

    Kalincik, L.

    2002-01-01

    This paper deals with project development of training programmes for non-licenced NPP personnel-masters, field operators, maintenance and technical supporting personnel. The programme development focuses on the part stage and on the job training at NPP. Bohunice NPP belongs to plants with higher specific number of personnel per installed power capacity. This factor also influenced the choice of programmes design. Undermentioned procedure is one of various approaches to SAT exploitation for training programmes design. (author)

  9. ALARA tools and performance indicators at Cernavoda NPP

    International Nuclear Information System (INIS)

    Chitu, C.; Popescu, V.; Simionov, V.

    2009-01-01

    Work efficiency is an area of high concern to nuclear power plant operators. Job planning has to be done so that there will be enough time for ALARA actions to be implemented. The control of the activities involving radiological risk is part of ALARA Process. An effective control supposes the implementation of a process to systematically identify the activities performed in radiological areas. Plant Performance Indicators related to ionizing radiation exposure have been established to improve station safe performance. They are assessed and reported periodically to reflect the safe operation objectives. If target values are exceeded 'abnormal condition reports' are generated. Corrective and preventive actions aim at work planning, technical aspects, and human performance. All the staff is informed about these events and corrective actions described through the training program are implemented. (authors)

  10. 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

  11. Spent fuel interim storage

    International Nuclear Information System (INIS)

    Bilegan, Iosif C.

    2003-01-01

    The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

  12. A dose assessment for final low level waste disposal located at Cernavoda

    International Nuclear Information System (INIS)

    Moldoveanu, E.

    1995-01-01

    This paper presents the first step in the radiological effect evaluation of the low radioactive wastes disposal which will be located in Cernavoda's area. The calculations are done with some approximations based on pessimistic hypotheses. In this sense, the primary step of the accident scenario is a total failure of the wastes disposal and a total emission of radioactive wastes in the environment. The results are estimated versus the time in which radioisotopes migrate through geological formations until they arrive at the underground water. It is considered that for Cernavoda, a town situated in the vicinity of the disposal, the water is contaminated with all radioisotopes arising in this way, and people ingest this water (2 l/day). The results are presented in tables and figures. (author)

  13. Training system enhancement for nuclear safety at PAKS NPP

    International Nuclear Information System (INIS)

    KIss, I.

    2000-01-01

    Paks Nuclear Power Plant is the only commercial nuclear facility in Hungary, which has been operational since 1982. The over 15 years operation of the plant can from all aspects be considered as a success, to which the well qualified, competent staff significantly contributes. Like other N-plants, Paks NPP is also exposed to major challenges due to plant ageing and changes in circumstances that affect the operation. The management focusing on maintaining nuclear safety launched an overall programme to upgrade quality of personnel training and to improve its infrastructure. Though this programme has successfully finished with visible proofs, further actions to develop a reconsidered human resource policy is needed so that the plant would successfully stand against the challenges of the 21. century. (author)

  14. Update from Cernavoda

    International Nuclear Information System (INIS)

    Sommerville, J.D.

    1996-01-01

    On April 16 1995 Cernavoda Unit 1 achieved criticality. This event marked the culmination of roughly 17 years of effort and one of the most troubled histories experienced by any nuclear construction project worldwide. It was also a major milestone in the program begun by AAC (AECL-ANSALDO CONSORTIUM) in 1991 and due to end in June 1997 with the hand-over to RENEL (The Romanian National Electric Utility) of a fully operational CANDU 600 Power Plant. This paper briefly outlines the history of the project, the organisational structure in place and the funding schemes used to ensure its completion. Most attention is given to the present status of the project and those areas and/or issues which have been or continue to be significant problem areas. The future program for the achievement of 100% power and hand-over of the station to RENEL is outlined and potential future problem areas are discussed. (author). 9 appendices

  15. The performance shaping factors influence analysis on the human reliability for NPP operation

    International Nuclear Information System (INIS)

    Farcasiu, M.; Nitoi, M.; Apostol, M.; Florescu, G.

    2008-01-01

    The Human Reliability Analysis (HRA) is an important step in Probabilistic Safety Assessment (PSA) studies and offers an advisability for concrete improvement of the man - machine - organization interfaces, reliability and safety. The goals of this analysis are to obtain sufficient details in order to understand and document all-important factors that affect human performance. The purpose of this paper is to estimate the human errors probabilities in view of the negative or positive effect of the human performance shaping factors (PSFs) for the mitigation of the initiating events which could occur in Nuclear Power Plant (NPP). Using THERP and SPAR-H methods, an analysis model of PSFs influence on the human reliability is performed. This model is applied to more important activities, that are necessary to mitigate 'one steam generator tube failure' event at Cernavoda NPP. The results are joint human error probabilities (JHEP) values estimated for the following situations: without regarding to PSFs influence; with PSFs in specific conditions; with PSFs which could have only positive influence and with PSFs which could have only negative influence. In addition, PSFs with negative influence were identified and using the DOE method, the necessary activities for changing negative influence were assigned. (authors)

  16. Achievements and future directions in the reactors physics and nuclear safety research

    International Nuclear Information System (INIS)

    Dumitrache, Ion

    2001-01-01

    A historical overlook is presented with respect to inception and development of reactor physics research and on the job training in Romania. First these activities were carried out at the Institute for Atomic Physics and Institute for Power Reactors (IRNE) in Bucharest and afterward at the Institute for Nuclear Technologies, later on transformed in the Institute of Nuclear Research at Pitesti. CYBER Computer installed at Pitesti allowed formation in as early as 1971 reactor specialists who worked out computer programs for neutron physics calculations. These specialists were able to assimilate the characteristic of CANDU 6 type reactor as well as the AECL methodology of simulating processes of CANDU reactor physics. At present four programs are under way. These are: 1. The nuclear reactor physics; 2. The nuclear facility safety; 3. Safety analyses for the transport and radioactive waste disposal; 4. Analyses for radiation shielding and biological protection. There are presented results of the work associated to the CANDU type reactor: 1. Adapting and improving the code system for neutron and thermohydraulic calculation for CANDU type reactor, as supplied by AECL; 2. The IRNE manual for CANDU reactor neutron designing; 3. Final sizing of shim rods of Cernavoda NPP Unit 2; 4. Tests and measurements of reactor physics at the Cernavoda NPP Unit 1 commissioning; 5. Simulation and independent analysis of thermosiphoning carried out at Cernavoda NPP Unit 1 commissioning; 6. Static and dynamical response of the detectors in the CANDU reactor core and their time evolution following the burnup in the neutron flux and their ageing effects; 7. PSA studies at Unit 1; 8. Safety analyses for the radioactive waste disposal at Saligny repository. Also, reported are the results of the work associated to the TRIGA reactor, as follows: 1. Flux measurements and neutron computations necessary in the reactor commissioning; 2. Cleaning up controversial issues relating to neutron flux

  17. 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 '

  18. Training in fundamentals of radiological coverage in Laguna Verde NPP; Entrenamiento de fundamentos de coberturas radiologicas en la CLV

    Energy Technology Data Exchange (ETDEWEB)

    Lara H, M. A., E-mail: marcolarah@gmail.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    In 2010, the Institute of Nuclear Power Operations (INPO) celebrates the Knowledge Transfer and Retention Workshop, an event where nuclear regulators and operators presented the strategies that various NPP to worldwide were implemented to mitigate the consequences of this generational change and take advantage of it, the trend in the presented works was the same: the generational change occurs in a faster way that the transfer of knowledge, the future was already here and many NPP had not been adequately prepared to train its nuclear technicians and engineers in the tasks demanded by the industry of them, so in addition to preparing these workers to forced marches was necessary to establish strategies to retain at more experienced staff in the industry. The Laguna Verde NPP has not been exempt to this process; the preparation of personnel squares to replace those that reaching retirement age in the Comision Federal de Electricidad (CFE) has become extensive in the last five years, sometimes leading to have personnel covering functions without an alternate to the next lower position, the cause? Not enough staff. In the specific case of radiation protection (Rp) the time required for obtaining the status of Rp technician according to the ANSI/ANS 3.1 standard is 2 years, one of the tasks that most occupies part of these two years is training in radiological coverage, this training requires a mix of knowledge and experience, recently one of the concepts used for training in Rp is the evaluation and management of the radiological risk, topic that is considered in this technical work. (Author)

  19. RAAN Conference. Support of Nuclear Power. Opening talk

    International Nuclear Information System (INIS)

    Valeca, Serban

    2002-01-01

    Nuclear power in Romania was initiated on the basis of CANDU reactor type technology, an option found to fulfill the requirements for a sustainable economic development, to support the electric energy demand of the country and to ensure the population and environment protection. The construction of the Cernavoda NPP was heavily based on the Romanian industry participation and basic and applied nuclear research national resources. The experience acquired from Cernavoda NPP Unit 1 will be fructified in the construction of Units 2-5 to be built. The Romanian Ministry of Education and Research implemented a nuclear national program for research and development taking into account the European Union requirements and recommendations, the cooperation with the IAEA - Vienna and the Romanian government policy on short and medium terms in the nuclear field. The research-development program targeted: the reactor physics and nuclear fuel management; the operation safety of Cernavoda NPP Unit 1; improvement of technological solutions for Cernavoda NPP; improvement of nuclear fuel cycle technology; risk assesment and evaluation of the radiological impact upon the environment; behavior of the materials submitted to operational conditions in the reactor and nuclear facilities; radiation safeguards; application of nuclear technologies and methods in industry, agriculture, health and other sectors of social life. The author highlights also relating topics concerning legislation, financing and international cooperation. He stresses the important role of the Romanian Agency for nuclear activities, R.A.A.N. through the Institute of Nuclear Research at Pitesti, the Center for Technological Engineering for Nuclear Objectives at Bucharest and the Heavy Water Plant at Drobeta Turnu Severin

  20. On psichological problem of NPP operation and control

    International Nuclear Information System (INIS)

    Mashin, V.A.

    1994-01-01

    The role of psichological factor as a reserve for increasing NPP safety connected with human factor is discussed. It is emphasized that the process of NPP personnel professional training should not be restricted by formation of a certain set of knowledge, skills and experience. It is necessary to initiate ability for constant self-developing. Control for assurance of effective interaction of the whole NPP personnel is an important problem

  1. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)

    2008-07-01

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  2. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)

    2008-07-01

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  3. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    International Nuclear Information System (INIS)

    Urjan, Daniel

    2008-01-01

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  4. Nuclearelectrica - a player on the Romanian energy market

    International Nuclear Information System (INIS)

    Chirica, T.; Metes, M.; Havris, A.

    2001-01-01

    Nuclearelectrica operates at Cernavoda NPP a CANDU 6 unit. The production performances and some technical indicators are presented. The paper introduces the players of the new-born Romanian energy market, where Nuclearelectrica acts as a significant producer, and. gives a short description of the current market mechanisms. The specific features of a producer operating a single nuclear unit, related to both technical and economical terms, are itemized; they are considered in the market rules issued by the Romanian Electricity Regulatory Authority - ANRE. Following these rules, Nuclearelectrica concluded with Electrica, the main energy supplier to final consumers, a long-term energy wholesale contract for all the generated by Cernavoda 1 electricity, based on the so-called Power Purchase Agreement model, where a large part of the risk related to the power sales is borne by the buyer. On the same time, the existing conditions on the Romanian market proved the competitiveness of Cernavoda unit as an energy producer; hence, the above-mentioned contract provides a futile over-protection to the NPP facing the market risks. The paper presents also the critical issue of the collection of revenues for the sold electricity and the company's approach in allotting this limited revenues. In light of the completion of Unit 2 of the Cernavoda NPP, the company's strategy considers new possible contracts, with eligible customers and energy exports.(author)

  5. National report from Romania

    International Nuclear Information System (INIS)

    Bengulescu, D.

    1995-01-01

    Review of objectives and activities in the area of creation operator support systems(OSS) in nuclear power plants in Romania is presented. Task 4.4.3. ''Develop requirements for techniques and tools for developing OSS and document existing ones'' is described. The following subjects are also discussed: development of computerised OSS for CANDU NPP; Cernavoda probabilistic safety evaluation project; rule-based and neural network-based expert systems in the Romanian safety research; an OSS for PHWR spent fuel bay; studies on an OSS in CANDU-6 NPP; Cernavoda probabilistic safety evaluation and utilization of results to improve nuclear power plant safety. 51 refs

  6. Utilization of NPP Krsko plant specific simulator

    International Nuclear Information System (INIS)

    Fifnja, I.; Pribozic, F.; Krajnc, J.

    2002-01-01

    NPP Krsko started with licensed operator training using its own plant-specific full scope simulator in April 2000. Today, two years after simulator was completed, the benefits of simulator use are visible in various fields. The simulator was effectively used to conduct licensed operator continuing training and practical examinations. Two-year continuous training program was designed to help maintain and improve operator performance. The simulator was also used to provide just-in-time training prior to plant evolutions. Together with licensed operators the non-licensed operators are also included into simulator training to provide affective team training opportunity and to foster good communication and increase scenario realism. Now, the first group of initial licensed operator training using plant-specific simulator is also almost completed. It is the first time that NPP Krsko training department conducted complete initial training and this will represent the great experience for future training. Besides training, the simulator was also utilized for procedure development and validation, operating standards development, testing of plant modifications and other activities, like emergency preparedness procedures validation and training exercises.(author)

  7. 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

  8. 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

  9. Operational experiences feedback in Bohunice NPP

    Energy Technology Data Exchange (ETDEWEB)

    Betak, A [NPP Bohunice (Slovakia)

    1997-10-01

    The presentation reviews the following issues: OEF team in Bohunice NPP - structure; training and qualification: ASSET seminars on Prevention of incidents - INES manual handling, NRA-NRC the training on event investigation methods, NU - the training on HPES; legislation - documentation prepared in the frame of QA programme; results of OEF team activities; ASSET mission Dukovany - Experiences; the perspective activities.

  10. The experience in the Cernavoda Unit 1 operation - a stimulating argument for future nuclear power development in Romania

    International Nuclear Information System (INIS)

    Rotaru, I.; Bucur, I.; Galeriu, A.C.; Budan, O.

    1999-01-01

    The Romanian nuclear program has been developed based on the option for CANDU type reactors. At the beginning, this program was unrealistically conceived and its management was inappropriate. The program was reconsidered in 1990 and the management policy and organization structure were also adapted accordingly. The paper presents, in the first part, the actual organization structure, adapted for the execution of the current and future activities, related to the nuclear power program. The performance achieved by Cernavoda Unit 1 constitutes the main part of the paper. The performances described demonstrate that the Cernavoda Unit 1 is a success and the Romania's electricity needs are satisfied in a proportion of about 12% by the nuclear power. The paper also presents a general view on Cernavoda Unit 2 perspectives. The essential conclusion of the paper is that the continuation of the nuclear program appears to be a logical option, generally accepted in Romania, limited only by financial restraints. (author)

  11. Optimal test intervals for shutdown systems for the Cernavoda nuclear power station

    International Nuclear Information System (INIS)

    Negut, Gh.; Laslau, F.

    1993-01-01

    Cernavoda nuclear power station required a complete PSA study. As a part of this study, an important goal to enhance the effectiveness of the plant operation is to establish optimal test intervals for the important engineering safety systems. The paper presents, briefly, the current methods to optimize the test intervals. For this reason it was used Vesely methods to establish optimal test intervals and Frantic code to survey the influence of the test intervals on system availability. The applications were done on the Shutdown System no. 1, a shutdown system provided whit solid rods and on Shutdown System no. 2 provided with injecting poison. The shutdown systems receive nine total independent scram signals that dictate the test interval. Fault trees for the both safety systems were developed. For the fault tree solutions an original code developed in our Institute was used. The results, intended to be implemented in the technical specifications for test and operation of Cernavoda NPS are presented

  12. Presentation on development of safety assessment reports in Romania

    International Nuclear Information System (INIS)

    Goicea, L.

    2002-01-01

    This presentation shows whole steps of Cernavoda 2 NPP licensing and accident management relevant changes considered. There are description of CANDU Safety principles and design criteria, as well as FSAR structured according to NRC Regulatory Guide 1.70, format of presentation of accident analyses, applicable acceptant criteria to analyses and Design Codes, Safety standards and Safety Guides used. The main features of CANDU reactors are presented, including of base design characteristics and describing of structures of CANDU reactors. During the licensing Cernavoda 2 are passed through Site approval, Construction permits of NPP system (1980-1993), Final construction license (1993) and Commissioning license (1995). In the May 1998 the First operating license is issued, based on FSAR Phase 1, Full power probationary report and carried out the requirements related to revising the FSAR and initiating of the Modernization program. To achieve the defense in depth concept are used and implemented the norms and quality standards during all plant stages, as well as selecting the high quality materials. During all plant stages is keeps strictly accomplishment of the quality requirements, and ensures a high level of reliability by using of operating principle and fabrication. In NPP operation is established using of the approved operating concept permitting only the safe condition for reactor operation. In the process of Cernavoda NPP licensing and operating the CSA and CGSB Canadian Standards, ASME and ANSI American Standards, Romanian Norms are implemented. Another useful Codes and Standards are implemented too, as ACI, ASTM, ANSI, AWS and others. In accident analysis for Safety Analysis Report for Cernavoda Unit 1 are involved 37 computer codes, in such areas as Reactor physics, Thermal-hydraulics, Fuel behavior, Fuel channel, Containment, and Fission product release and dose calculation

  13. Ukrainian Nuclear Society International Conference 'Modernization of the NPP with VVER reactor' (abstracts)

    International Nuclear Information System (INIS)

    Bar'yakhtar, V.G.

    1999-01-01

    Abstracts of the papers presented at International conference of the Ukrainian Nuclear Society 'Modernization of the NPP with VVER reactor'. The following problems are considered: improving the NPP's safety and reliability; reactor modernization, the lifetime prolongation; increasing of the reactor operating characteristics; methods of capacity factor increasing: refueling control, maintenance control; technical and economical aspects of NPP modernization; modernization of the automated control system of the fuel process at the NPP's; technical features and methods for the continued radiation and technology control at the NPP's; training, increasing the staff qualification and NPP modernization

  14. 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

  15. 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%

  16. Quantitative analysis of psychological personality for NPP operators

    International Nuclear Information System (INIS)

    Gao Jia; Huang Xiangrui

    1998-01-01

    The author introduces the relevant personality quantitative psychological research work carried out by 'Prognoz' Laboratory and Taiwan, and presents the primary results of the research for Chinese Nuclear Power Plant (NPP) operator's psychological personality assessment, which based on the survey of MMPI, and presents the main contents for the personality quantitative psychological research in NPP of China. And emphasizes the need to carry out psychological selection and training in nuclear industry

  17. Treatment, conditioning and packaging for final disposal of low and intermediate level waste from Cernavoda: a techno-economic assessment

    Energy Technology Data Exchange (ETDEWEB)

    Suryanarayan, S.; Husain, A. [Kinectrics Inc., Toronto, ON (Canada); Fellingham, L.; Nesbitt, V. [Nuvia Ltd., Didcot, Oxfordshire (United Kingdom); Toro, L. [Mate-fin, Bucharest (Romania); Simionov, V.; Dumitrescu, D. [Cernavoda Nuclear Power Plant, Cernavoda (Romania)

    2011-07-01

    National Nuclearelectrica Society (SNN) owns and operates two CANDU-6 plants at Cernavoda in Romania. Two additional units are expected to be built on the site in the future. Low and intermediate level short-lived radioactive wastes from Cernavoda are planned to be disposed off in a near-surface repository to be built at Saligny. The principal waste streams are IX resins, filters, compactable wastes, non-compactables, organic liquids and oil-solid mixtures. Their volumetric generation rates per reactor unit are estimated to be: IX resins (6 m{sup 3}/y), filters (2 m{sup 3}/y), compactables (23 m{sup 3}/y) and non-compactables (15 m{sup 3}/y). A techno-economic assessment of the available options for a facility to treat and condition Cernavoda's wastes for disposal was carried out in 2009 based on projected waste volumes from all four units. A large number of processes were first screened to identify viable options. They were further considered to develop overall processing options for each waste stream. These were then consolidated to obtain options for the entire plant by minimizing the number of unit operations required to process the various waste streams. A total of 9 plant options were developed for which detailed costing was undertaken. Based on a techno-economic assessment, two top ranking plant options were identified. Several scenarios were considered for implementing these options. Amongst them, a contractor run operation of a facility located on the Cernavoda site was considered to be more cost effective than operating the facility using SNN personnel. (author)

  18. 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)

  19. 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

  20. Off reactor testings. Technological engineering applicative research

    International Nuclear Information System (INIS)

    Doca, Cezar

    2001-01-01

    By the end of year 2000 over 400 nuclear electro-power units were operating world wide, summing up a 350,000 MW total capacity, with a total production of 2,300 TWh, representing 16% of the world's electricity production. Other 36 units, totalizing 28,000 MW, were in construction, while a manifest orientation towards nuclear power development was observed in principal Asian countries like China, India, Japan and Korea. In the same world's trend one find also Romania, the Cernavoda NPP Unit 1 generating electrical energy into the national system beginning with 2 December 1996. Recently, the commercial contract was completed for finishing the Cernavoda NPP Unit 2 and launching it into operation by the end of year 2004. An important role in developing the activity of research and technological engineering, as technical support for manufacturing the CANDU type nuclear fuel and supplying with equipment the Cernavoda units, was played by the Division 7 TAR of the INR Pitesti. Qualification testings were conducted for: - off-reactor CANDU type nuclear fuel; - FARE tools, pressure regulators, explosion proof panels; channel shutting, as well as functional testing for spare pushing facility as a first step in the frame of the qualification tests for the charging/discharging machine (MID) 4 and 5 endings. Testing facilities are described, as well as high pressure hot/cool loops, measuring chains, all of them fulfilling the requirements of quality assurance. The nuclear fuel off-reactor tests were carried out to determine: strength; endurance; impact, pressure fall and wear resistance. For Cernavoda NPP equipment testings were carried out for: the explosion proof panels, pressure regulators, behaviour to vibration and wear of the steam generation tubings, effects of vibration upon different electronic component, channel shutting (for Cernavoda Unit 2), MID operating at 300 and 500 cycles. A number of R and D programs were conducted in the frame of division 7 TAR of INR

  1. The principles, terms and responsibilities contained in the Romanian legislation related to coverage of risk in nuclear activities developed by Societatea Nationala Nuclearelectrica SA

    International Nuclear Information System (INIS)

    Vatamanu, Mariana

    2005-01-01

    Societatea Nationala ''NUCLEARELECTRICA'' (SNN) SA, a Romanian state owned stock company, established in July 1998, following the restructuring of RENEL, the former centralized Romanian Utility is the Owner of the Cernavoda Nuclear Power Plant and has three main branches: ''CNE Prod'', operating Unit 1 Cernavoda NPP; 'CNE Invest'', including Units no.2 to 5, actually in charge with the completion of Unit 2; ''FCN - Pitesti'', the nuclear fuel factory. Cernavoda NPP project is based technology transfer process from Canada, Italy and United States for CANDU 6 reactor type. The transfer of technology covers mainly nuclear island, secondary cycle and turbo - generator. Romania has a well developed nuclear infrastructure. Heavy water plant (ROMAG). Fuel fabrication facility (FCN). Technically qualified CANDU experienced staff. Nuclear R and D program. This places Romania in an excellent position to optimize their resources and nuclear infrastructure with the construction and the operation of Cernavoda 2 and 3. Romania is part of Non Proliferation Treaty, Third Part Liability Convention, Nuclear Safety Convention, etc.. The Romanian nuclear regulations are in line with the European Community legislation. In accordance with general international practices of Nuclear Operators and with the International and National specific Legislation regulating the nuclear activities in Romania, Nuclear All Risk - Material Damage and Nuclear Liability insurance policies and placed by SOCIETATEA NATIONALA NUCLEARELECTRICA to the international nuclear ''pools'' from February 1995. Regarding the environmental protection, each unit of Cernavoda NPP can accommodate spent fuel for ten years of full operation. Furthermore, Romania is developing radioactive waste management programs and adopting concepts recognized worldwide (interim dry storage, near surface repository for low and medium level waste). The final repository of the nuclear spent fuel is subject to future decision. Based on the

  2. Periodic and in-service inspection programs

    International Nuclear Information System (INIS)

    Dinu, M.

    2000-01-01

    Periodic and in-service inspection programs for Cernavoda NPP consists of periodic inspections of CANDU NPP components CSAN N-285.4 and CSAN N-285.4, in-service inspections and repair and modifications general inspection. Periodic inspection program document (PIPD) determines the systems and components subject to inspection, the category of the inspection, techniques, areas and other details.The current status of the inspection programs is presented, including containment , erosion/corrosion, pressure vessel support and snubbers, main steam lines inspection programs. Qualification program in Cernavoda NPP involves equipment qualification in the on-site laboratory, yearly certification, special equipment qualification in the National Institute of Metrology. All procedures are approved by the ISCIR (regulatory body for pressure vessel and lifting equipment) and CNCAN (National Commission on Nuclear Activities Control). Qualification of the personnel is performed according to the ISCIR Technical prescription CR 11/82 for up to 3 year period. Final qualification and licensing is performed by CNCAN

  3. Romania country report

    Energy Technology Data Exchange (ETDEWEB)

    Stiopol, Mihaela [Nuclearelectrica SA, 65 Polona Street, 010494 Bucharest (Romania)

    2008-07-01

    and Particle Physics, Field Theory, Mathematical and Computational Physics, Atomic Physics of Condensed matter, Life and Environmental Physics. Facilities: Tandem Accelerator, Cyclotron, IRAS, Test nuclear reactor - Institute for Nuclear Research Pitesti - 18 programs. Facilities: TRIGA Research Reactor, Post-Irradiation Examination Laboratory, Out-of-Pile Testing, Radioactive Waste Treatment Plant. WIN Romania members are involved in activities related to: personnel training, knowledge transfer through IAEA fellowships, workshops, courses, etc. They have an active professional implication as leaders of research and engineering programs, managers of national/international projects, key experts in the European Commission Framework Programs. Cooperation activities with Joint Research Center and with IAEA - Vienna. WIN Romania members were the main promoters of most of the visits to Cernavoda NPP for pupils and teachers. were deeply involved in organizing the 'International Symposium on Nuclear Energy - SIEN 2007' and the contest and the exhibition of children drawings involving the children of the town. WIN - Romania Organised WiN Workshop on 17 October, during SIEN 2007, and WIN meeting on 14 December 2007.

  4. Establishing a relationship with media

    International Nuclear Information System (INIS)

    Mesaru, Dana

    2000-01-01

    The Cernavoda NPP site is in Constanta County in the Dobrogea region. Within a 30-km radius of the Cernavoda NPP site there are several historical monuments and archaeologically significant ruins, some of which date to Greek and Roman times. There are also four natural reserves. None of these features are sufficiently close to the NPP to be disturbed by its operation The start of the nuclear program in Romania, about 20 years ago, was a high-level government decision based on economical and political considerations, but without any commitment or acceptance of the people. Unit 1 delivers to the national grid 20% of the national electricity demand, in 1998 the gross capacity factor was 86.19%. Cernavoda is the only nuclear station operating in the country. The plant has been in commercial operation a little more than three years, so the Public Relations Department is a fledgling one. The site PR group was first formed during the latter stages of the construction. The PR group has to deal with the changing of the access to the information, still going on in Romania. First, the PR group had the public who used to view the information with apathy and scepticism, as the information was coming from a single controlled source. The same public today views the information with the scepticism and apathy, confused by the unrestricted access to the information. First, the information was unbelievable, and now it is bewildering. The PR group is in the middle of this change. We must convince the public that the messages we put out are factual and that this is an honest exchange. The challenge before is to build a bridge of understanding and trust between the NPP and the public. The PR group has the necessary foundation on the NPP side and the full commitment from the management. What are needed are a formation of a group of public sufficiently interested in the affairs of the NPP and the influence of the NPP on the life of community

  5. Waste Minimization Policy at the Romanian Nuclear Power Plant

    International Nuclear Information System (INIS)

    Andrei, V.; Daian, I.

    2002-01-01

    The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP

  6. Brief history of the reactor physics activities at ICN Pitesti

    International Nuclear Information System (INIS)

    Dumitrache, I.

    2004-01-01

    The Institute was established 33 years ago, in April 1971. Several specialists from the Institute for Atomic Physics - Bucharest came at the new research entity and the reactor physics activities had a successful start. One can identify three distinct periods: 1971-1980, the Bucharest years, 1980-1996, solving critical problems years and 1977-present (2004), technical support years. The first period is usually seen as a training one. This is only partially true. Most of the physicists came from University in 1971 and 1972 years. A significant number of them were trained abroad, in France, Germany, Italy, USA, Canada etc., usually under IAEA Vienna fellowships. The work was really pleasant and the progress was exciting. Unfortunately, the main task (to design a thermal reactor and a fast reactor, both for research activities) was, probably, much too difficult from the technical point of view and, in addition, required an unrealistic economic effort. In the Fall of the 1976 year, most of the reactor physicists were removed from Bucharest to Pitesti. One year later, all the remaining specialists were concentrated in Pitesti. The dual core TRIGA reactors were commissioned in the last months of the 1979 year. The CYBER 720 mainframe computer was available in December 1980. Between 1980 and 1992 years, practically all the Romanian activities related to reactor physics were performed in Pitesti, Mioveni compound. The details related to critical problems will be presented in the paper. We mention here four of the problems that have a significant impact even today, namely: -Final dimensioning of the adjuster rods for the Cernavoda NPP, Unit 2. The rods were manufactured in USA and Canada, using the AECL design and the final dimensions have been specified by ICN Pitesti; -Use of the LEU fuel in TRIGA-SSR Reactor, instead of the original HEU fuel; -Design of the irradiation experiments in TRIGA cores, in order to provide the required conditions during the test, according to

  7. Customization of RODOS 5.0 system for the assesment of a CANDU Cernavoda NPP nuclear accident scenario

    International Nuclear Information System (INIS)

    Mateescu, Gh.; Galeriu, D.; Slavnicu, D.; Vamanu, D.; Craciunescu, T.; Turcanu, C.; Melintescu, C.A.; Gheorghiu, D.; Gheorghiu, A.

    2003-01-01

    The RODOS expert system is designed to be run in real time and on-line for multiuser operation in local, regional and national nuclear emergency centers responsible for off-site nuclear emergency management. RODOS provides continuously updated, consistent, comprehensive and timely information as an input for making decisions at local, national and European scale, in early or late phase of an accident, for all types of actions and countermeasures in an emergency situation. For testing the customization of RODOS in prototype version 5.0 to Romanian conditions an accident scenario for CANDU reactor was considered. This accident scenario is the early reactor core disruption with hydrogen burning. For customization a more detailed geographic database was created and was updated according to the radioecological database for our country. The goal of testing is to assess the accident consequences in early phase and also the banning, processing and disposal of agricultural products. One figure presents the evacuation zone and a second one shows the iodine tablet intake (for children). Another application was the estimation of HTO concentration and OBT (organic bound tritium) in cow's milk and also the tritium ingestion dose, having in view that CANDU reactor is an important source of tritium in the case of an accidental release. Other important estimations regard the assessment of concentration of important radionuclides as Cs-137, I-131 and Sr-90 which has an important impact on organs like muscles, thyroid and bones. In case of countermeasures for long term it is very important to estimate the number of persons to be relocated as well as the relocation lapse. The system provides economic estimations corresponding to different countermeasure strategies regarding the costs of food consumption and decontamination activities of radioactively contaminated regions. RODOS is adapted to evaluate accident or incident consequences for all nuclear risk zones in Romania (Cernavoda

  8. NPP Krsko full scope simulator verification and qualification

    International Nuclear Information System (INIS)

    Krajnc, B.; Glaser, B.; Novsak, M.; Spiler, J.

    1998-01-01

    NPP Krsko (NEK) will, as a part of the Modernization plan, obtain also Krsko Full Scope Simulator (KFSS). Contract has been awarded to CAE Electronics for the design, construction and integration. KFSS will support in real time, the training for the complete range of operation, which can be performed from the main control room and some selected plant areas (remote shutdown panels, etc). Based on the lessons learned on development of NPP Krsko Basic Principle Simulator we decided for active approach. That means that NPP Krsko personnel will be heavily involved into all phases of KFSS development and testing. Since NPP Krsko is going to replace the existing steam generators, raise the nominal power and perform necessary modifications to support the power uprate, it was decided that the development of the KFSS will be conducted in two steps: 1. Development of the models as well as all the hardware interface in the MCR for the existing plant Cycle 15 and then, 2. Models and hardware will be modified, added or replaced as needed to take into account the steam generator replacement and plant uprate projects. In spite of the fact that the simulator will be used for the training of the plant operators for the uprated conditions and with new steam generators, the upper described approach was selected since we want to be sure that the models will at the beginning adequately simulate the existing plant. For the existing conditions we have available reference data for different plant conditions, as well as data for different plant transients. By verifying that simulator will be able adequately simulate the existing conditions the level of confidence for the uprated simulator will be much higher. This is of special importance since it will support initial training for modernized plant conditions. In this paper the plan for verification and qualification of KFSS as well as the amount of the work needed on NPP Krsko side to develop the test acceptance criteria will be presented.(author)

  9. Regulatory approach to NPP ageing in Romania

    International Nuclear Information System (INIS)

    Benescu, C.G.; Hossu, A.

    2000-01-01

    In this paper the Romanian requirements for ageing management of systems and components important to safety of Cernavoda nuclear power plant (one Candu type reactor, heavy water moderated power reactor) are presented

  10. Training of personnel

    International Nuclear Information System (INIS)

    1997-01-01

    Selected staffs (in the area of NPPs) are examined by the State Examining Committee established by Nuclear Regulatory Authority of the Slovak Republic (NRA SR's) chairman. The committee consists of representatives of NRA SR , Bohunice NPPs, Mochovce NPP, Research Institute of Nuclear Energy and experts from the Faculty of Electrical Engineering and Information Technology of the Slovak Technical University. The review of selected personnel of NPP V-1, V-2 and Mochovce NPP which passed exams in 1996 is given. NRA SR paid attention to the upgrading training process of individual categories of staff for V-1, V-2 and Mochovce NPPs, simulator training and training with computerized simulation system according to the United criteria of nuclear installation personnel training that started in 1992. During the year, an inspection was performed focused on examination of technical equipment of the simulator of Mochovce NPP, professional eligibility and overall preparation of simulator training including simulator software. Throughout the year launching works continued at the simulator with the deadline of commissioning to trial use operation in the first half of 1997

  11. Methodology transfer for the preparation of NPP decommissioning for leading personnel of the Ignalina NPP and for the representatives of Lithuanian authorities

    International Nuclear Information System (INIS)

    Ackermann, L.; Baecker, A.

    2004-01-01

    At request of the Lithuanian government to receive support for the preparation of the decommissioning of Ignalina NPP, a bilateral project was financed by the German federal government to transfer experience from the decommissioning of the Greifswald and Rheinsberg NPPs to the management staff of the Ignalina NPP and to the representatives of the Lithuanian authorities in charge of the decommissioning. The methodology transfer project was prepared and carried out under the leadership of the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. The practical implementation was within the responsibility of Energiewerke Nord GmbH (EWN) in cooperation with other German subcontractors. The methodology transfer comprised the task fields of project management, project planning, licensing procedure and waste management as well as social aspects of the further development of the industrial site. Five intensive one-week seminars were conducted mainly at the Greifswald NPP site and the knowledge gained was then consolidated in two evaluation seminars at the Ignalina NPP. As the basis for the training realised in 2002 and 2003, EWN provided about 2000 power-point illustrations, more than 200 transparencies and four video films. The training handouts produced by EWN were delivered to the seminar participants in Russian and English language and documented in the database ''Technische Dokumentation Ost'' (DOKU OST) of GRS. (orig.)

  12. Strategic maintenance plan for Cernavoda steam generators

    International Nuclear Information System (INIS)

    Cicerone, T.; Dhar, D.; VandenBerg, J.P.

    2002-01-01

    Steam generators are among the most important pieces of equipment in a nuclear power plant. They are required full time during the plant operation and obviously no redundancy exists. Past experience has shown that those utilities which implemented comprehensive steam generator inspection and maintenance programs and strict water chemistry controls, have had good steam generator performance that supports good overall plant performance. The purpose of this paper is to discuss a strategic Life Management and Operational-monitoring program for the Cernavoda steam generators. The program is first of all to develop a base of expertise for the management of the steam generator condition; and that is to be supported by a program of actions to be accomplished over time to assess their condition, to take measures to avoid degradation and to provide for inspections, cleaning and modifications as necessary. (author)

  13. Impact of nuclear information on the public acceptance. Case study for young people in Cernavoda and Pitesti towns

    International Nuclear Information System (INIS)

    Constantin, Marin; Diaconu, Daniela

    2007-01-01

    The general objective of this work was to investigate the impact of nuclear information on young people's knowledge and attitudes by using different Methods/Participatory Tools in an Educational Programme. The investigation started with a baseline survey of six groups of youngsters, three each from Pitesti and Cernavoda, which was completed early in 2005. After analysing the results an Educational Programme was proposed and developed following the FP6- COWAM2 Annual Seminar at Ljubljana. The Programme was produced by November 2005 and three methods were selected: classical methods usually used for school teaching, the discovery method, and a method involving simulation of a Local Committee. Three groups from Pitesti and four from Cernavoda attended the Programme, which was followed by a new questionnaire-based measurement (May 2006). (authors)

  14. Chapter No.8. Personnel qualification and training

    International Nuclear Information System (INIS)

    2002-01-01

    The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

  15. Report of the IPERS (International Peer Review Service) pre-review mission for the Cernavoda nuclear power plant probabilistic safety evaluation (CPSE - PHASE B) in Romania 31 October to 3 November 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This report presents the results of the IAEA international peer review services pre-review mission which reviewed the status of the present version of the Cernavoda probabilistic safety evaluation, a Level 1 internal events Probabilistic Safety Assessment for the Cernavoda, Unit 1, nuclear power plant. 2 refs

  16. EOPs at NPP Temelin: Analytical support for EOPs verification

    International Nuclear Information System (INIS)

    Bica, M.

    1999-01-01

    The process of implementation of symptom-based emergency operating procedures (EOPs) started at the NPP Temelin in 1993. The process has the following phases: development of symptom-based EOPs; EOPs verification; EOPs validation; operating personnel training; EOPs control and experience feedback. The development of Temelin specific EOPs was based on technology and know-how transfer using the Emergency Response Guidelines Methodology developed by the Westinghouse Owner Group. In this lecture the implementation of symptom-based EOPs in the the NPP Temelin is described

  17. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2001-01-01

    The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

  18. Beyond designed functional margins in CANDU type NPP. Radioactive nuclei assessment in an LOCA type accident

    Directory of Open Access Journals (Sweden)

    Budu Andrei Razvan

    2015-01-01

    Full Text Available European Union's energy roadmap up to year 2050 states that in order to have an efficient and sustainable economy, with minimum or decreasing greenhouse gas emissions, along with use of renewable resources, each constituent state has the option for nuclear energy production as one desirable option. Every scenario considered for tackling climate change issues, along with security of supply positions the nuclear energy as a recommended option, an option that is highly competitive with respect to others. Nuclear energy, along with other renewable power sources are considered to be the main pillars in the energy sector for greenhouse gas emission mitigation at European level. European Union considers that nuclear energy must be treated as a highly recommended option since it can contribute to security of energy supply. Romania showed excellent track-records in operating in a safe and economically sound manner of Cernavoda NPP Units 1&2. Both Units are in top 10 worldwide in terms of capacity factor. Due to Romania's need to ensure the security of electricity supply, to meet the environmental targets and to move to low carbon generation technologies, Cernavoda Units 3&4 Project appears as a must. This Project was started in 2010 and it is expected to have the Units running by 2025. Cost effective and safety operation of a Nuclear Power Plant is made taking into consideration functional limits of its equipment. As common practice, every nuclear reactor type (technology used is tested according to the worse credible accident or equipment failure that can occur. For CANDU type reactor, this is a Loss of Cooling Accident (LOCA. In a LOCA type accident in a CANDU NPP, using RELAP/SCDAP code for fuel bundle damage assessment the radioactive nuclei are to be quantified. Recently, CANDU type NPP accidents are studied using the RELAP/SCDAP code only. The code formerly developed for PWR type reactors was adapted for the CANDU geometry and can assess the

  19. Romanian nuclear fuel cycle development

    International Nuclear Information System (INIS)

    Rapeanu, S.N.; Comsa, Olivia

    1998-01-01

    Romanian decision to introduce nuclear power was based on the evaluation of electricity demand and supply as well as a domestic resources assessment. The option was the introduction of CANDU-PHWR through a license agreement with AECL Canada. The major factors in this choice have been the need of diversifying the energy resources, the improvement the national industry and the independence of foreign suppliers. Romanian Nuclear Power Program envisaged a large national participation in Cernavoda NPP completion, in the development of nuclear fuel cycle facilities and horizontal industry, in R and D and human resources. As consequence, important support was being given to development of industries involved in Nuclear Fuel Cycle and manufacturing of equipment and nuclear materials based on technology transfer, implementation of advanced design execution standards, QA procedures and current nuclear safety requirements at international level. Unit 1 of the first Romanian nuclear power plant, Cernavoda NPP with a final profile 5x700 Mw e, is now in operation and its production represents 10% of all national electricity production. There were also developed all stages of FRONT END of Nuclear Fuel Cycle as well as programs for spent fuel and waste management. Industrial facilities for uranian production, U 3 O 8 concentrate, UO 2 powder and CANDU fuel bundles, as well as heavy water plant, supply the required fuel and heavy water for Cernavoda NPP. The paper presents the Romanian activities in Nuclear Fuel Cycle and waste management fields. (authors)

  20. Third RAAN conference: RAAN as Support of Nuclear Power

    International Nuclear Information System (INIS)

    Popescu, Camillo

    2004-01-01

    The proceedings of the third RAAN conference, titled 'RAAN as Support of Nuclear Power', held in Drobeta Turnu-Severin, Romania on 6-7 Nov 2003, are structured on three sections covering the following issues: - Section 1. Energy and Environment (19 papers); - Section 2. Isotopic products (3 papers); - Section 3. Prospects of Nuclear Power development in Romania (17 papers). Nuclear power in Romania was initiated on the basis of CANDU reactor type technology, an option found able to fulfill the requirements for a sustainable economic development, to support the electric energy demand of the country and to ensure the population and environment protection. The construction of the Cernavoda NPP was heavily based on the Romanian industry participation and basic and applied nuclear research national resources. The experience acquired from Cernavoda NPP Unit 1 will be fruitfully used in construction of the Units 2-5 to be built. Lately Romania's economy recorded a significant grow what entailed a net increase in the energy demand. Analyses presented in this conference that take into account the classical energy resources of the country, on one hand, and the natural uranium deposits, the existing facilities as for instance those ensuring from domestic industry both heavy water and the nuclear fuel, on the other hand, argue that the sole viable alternative ensuring the sustainable economic development appears to be the nuclear power based on the experience already acquired through Cernavoda NPP operation

  1. Application and the importance of aging management within the PLiM/PLEx programs

    International Nuclear Information System (INIS)

    Cojan, Mihai

    2004-01-01

    The PLiM/PLEx Program applied to the Cernavoda NPP has the goal of ensuring the lifetime target of the plant and its extension in conditions of a continuous, secure and reliable operation by fulfilling at the same time the general licensing requirements as established by the regulation authority CNCAN. The aging management is, according to the organization model, a systematic process implying the following activities specific to the operation: - Planning: Coordination of the aging management activities; - Exploitation: Controlling the aging mechanisms; - Testing: Detection and evaluation of the aging effects; - Maintenance: Controlling the aging effects. All these are interdependent with specific activities in INR Pitesti, related to the research and development which are key elements for controlling effectively the aging process. The model of organizing the aging management developed in this work is applied to the Cernavoda NPP Unit 1

  2. Training Nuclear Power Specialists

    International Nuclear Information System (INIS)

    Paulikas, V.

    2003-01-01

    Situation of preparation of nuclear energy specialists in Lithuania is presented. Nuclear engineers are being prepared at Kaunas University of Technology. In view with decision to decommission Unit 1, the Ignalina NPP is limiting the number of new personnel to fill in vacancies. The main attention is given to the training courses for improvement skills of existing Ignalina NPP, VATESI personnel. Main topics of the training courses are listed. Comparison with previous years on personnel hired and dismissed in Ignalina NPP is made

  3. Status of the Romanian nuclear power program and the strategy related to the public information

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Chirica, Teodor

    1999-01-01

    The year 1997 represented for the Romanian nuclear power sector the year of the performances and capabilities proved Cernavoda NPP s unit operation, after one year of successful operation. Good performances of this unit could represent a positive impact on further development of nuclear power in Romania, considering first the completion of Unit 2 and for National Heavy Water Reactor Program. On the other hand, 'The years of 1997 and 1998 marked for the Romanian Electricity Authority a new and completely different perception of the Romanian power sector'. Recently, the first step of the restructuring of power sector has been accomplished. The Romanian Government approved the creation of the National Power Grid Company and the moving-out of the nuclear activities. The present Nuclear Power Group from RENEL was transformed in a separate entity, the National 'Nuclear Ellectrica' Company, including three subsidiaries, no legal persons, one for nuclear power production CNE-PROD (Cernavoda Unit 1), one for nuclear power development CNE-INVEST (Cernavoda Unit 2 to 5) and one for nuclear fuel fabrication FCN (Pitesti Nuclear Fuel Plant). The other Units from Nuclear Power Group, such as the Heavy Water Plant - ROMAG, Center of Technology and Engineering for Nuclear Projects - CTON and the Institute for Nuclear Research-Pitesti - ICN have been transformed in a state owned company for nuclear activities. To better understand the aspects related to the nuclear power in Romania and the necessity of the continuation and development of a public information strategy based on the new look of the nuclear power sector, please, allow me to present you a few things with regard the Romanian nuclear program. The main targets of Public Information Program Strategy considered when assessing the strategy related to the public information were: education and built-up of a credibility on the construction of a nuclear power plant in general, and of the Cernavoda NPP, in particular; and once

  4. Training on radiation protection in Information Center of Vandellos 1 NPP

    International Nuclear Information System (INIS)

    Preciado, L.; Lopera, A.

    2007-01-01

    The beginning of the Vandellos 1 NPP decommissioning set the starting point of an ambitious communication programme addressed to the different kinds of stake holders which composed the social environment of the site. The National Radioactive Wastes company (ENRESA), as the project performed and the legal responsible for the site, designed a communication plan with a clear formative drive and aimed at total transparency in a event which had not taken place before in Spain. All aspects of Safety became strategic values for the project and, therefore, for its communication activities. This was especially the case with regards to public information and Radiological Protection (RP) training. The seminars for the media, the presentations for the interested organizations and environmental collectives and the informative meetings with the political authorities were accompanied by a discourse and several formative initiatives addressed to the general public, and especially to student visitors. those activities have been developing alongside the decommissioning process, from the organization of visits which made possible an in situ view of the RP procedures to the current offer of a specific RP workshop. (Author)

  5. How e-learning contributes to corporation competitiveness

    International Nuclear Information System (INIS)

    Ceclan, Mihai; Ionescu, Tudor Basarab; Ceclan, Rodica Elena

    2006-01-01

    This paper aims at presenting an original Computer Based Training (CBT) System (or e- Learning system) and the way to use CBT technology to increase corporate competitiveness. Our solution is called CBTCenter and it is a complete software platform which offers a variety of teaching and learning services to its users. CBT or e-Learning mean two things: a software platform and content authoring. Ideally, a software platform should be able to import any type of flat documentation and integrate it into a structured database which keeps track of pedagogically meaningful information (test and quiz results, etc.). CBT technology was successfully implemented at the Training Department of NPP Cernavoda. CBT technology has brought several advantages: - the technology improves overall communication between all individuals which are part of the educational process - students can access training materials from their own desk using the NPP intranet - the logistics problem decreased, while more and more classic disciplines (courses) will be converted to CBT objects. On the other hand the paper is focused on using CBT technology (e-Learning) as a tool for corporate competitiveness increasing. This comes a reality by ICT (Information and Communication Technology) integration in corporate learning environment

  6. 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)

  7. Evaluation of specific tritium transfer parameters in equilibrium conditions for Cernavoda area

    International Nuclear Information System (INIS)

    Paunescu, N.; Galeriu, D.; Mocanu, N.; Margineanu, R.

    1998-01-01

    In Romania, a CANDU nuclear power plant with five reactors of 600 MWe is under construction. The first unit reached its criticality on April 1996 and became operational at full power on December 1996. The nuclear power plant is placed in Cernavoda area, in the S-E of Romania, between the Danube River and the Danube-Black Sea Canal. The prevalent local climate is continental and agricultural activity in the neighbourhood of the nuclear power plant is of intensive type. The routine atmospheric tritium release from the 3 GWe nuclear power plant is expected to be about 460 TBq/year and the aqueous release is expected to be 350 TBq/year. The aim of this study was to evaluate the environmental tritium reference level before commissioning the nuclear power plant. Representative samples for Cernavoda area were analysed: air humidity; water from Danube River, Danube-Black Sea Canal, lakes; drinking and ground water, rain (snow) water; soil at different depths; tissue free water tritium in vegetal and animal foodstuff relevant for human diet: cereals (wheat, maize, barley), vegetables (potato, tomato, cabbage, onion, bean), fruits, grapes, wine and milk; organically bound tritium in wheat and maize grains. The equipment and methods used were: Liquid scintillation analyzer of type TRICARB 1900 TR; scintillation cocktails of Instagel and Pico Fluor LLT type; sampling system for trapping the atmospheric tritium on molecular sieves; furnace; vacuum line and freeze trap (-60 deg. C); equipment for simple, fractionating and azeotropic distillation. The background level of tritium concentration was determined in environmental samples in Cernavoda area, in preoperational stage of nuclear power plant. The mean values determined during 1994-early 1996 are : (7.4±5.5) Bq/L in air humidity, (3.1±1.0) Bq/L in water, (3.53±0.4) Bq/L in tissue water from vegetable and (4.9±1.7) Bq/L in tissue water from cereals (grains). The values of tritium concentration in air, water, soil and

  8. Nuclear power plant personnel training and its evaluation. A guidebook

    International Nuclear Information System (INIS)

    1996-01-01

    The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs, tabs

  9. Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Scott Hower [Zetec Inc. (Romania); Luiza Vladu; Adrian Nichisov; Mihai Cretu [COMPCONTROL ING. (Romania)

    2006-07-01

    Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

  10. Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

    International Nuclear Information System (INIS)

    Scott Hower; Luiza Vladu; Adrian Nichisov; Mihai Cretu

    2006-01-01

    Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

  11. Engineering geological and hydrogeological invstigations for storage of medium and low-activity nuclear waste at Cernavoda, Romania. Soil stabilisation using the CONSOLID system; Ingenieurgeologische und hydrogeologische Untersuchungen zur Lagerung mittel- und schwachradioaktiver Abfaelle in Cernavoda Rumaenien. Baugrundstabilisierung mit dem CONSOLID-System

    Energy Technology Data Exchange (ETDEWEB)

    Giurgea, V.; Merkler, G.P.; Hoetzl, H.; Hannich, D. [Karlsruhe Univ. (T.H.) (Germany). Lehrstuhl fuer Angewandte Geologie

    1998-12-31

    In Cernavoda/Romania investigations and planning from a low and middle radioactive waste disposal site have been carried out. A multitude of hydrogeological, geological, engineering geological criteria`s and constructional security measures were examined with respect to the strict regulations for such a waste site. This studies and measures are shortly analyzed and discussed in this paper. In accordance with the selection criteria for such a hazardous waste site, several laboratory and `in situ` tests, soil-mechanic studies, numerical modeling and foundation tests for soil stabilization with the CONSOLID-System are presented. (orig.) [Deutsch] Zur Einhaltung der strengen Vorgaben, die bei einem Deponiestandort fuer mittel- und schwachradioaktive Abfaelle gestellt werden, sind in Cernavoda/Rumaenien eine Vielzahl von hydrogeologischen und ingenieurgeologischen Untersuchungen sowie bautechnischen Sicherungsmassnahmen vorgesehen, die im Rahmen dieser Publikation kurz analysiert und diskutiert werden. Im Zusammenhang mit den geologischen und hydrogeologischen Auswahlkriterien des Standortes werden eine Reihe von Labor- und `in situ` Untersuchungen, Modellrechnungen sowie Baugrundstabilisierungsmassnahmen mit dem CONSOLID-System vorgestellt. (orig.)

  12. 'Nuclearelectrica' and restructuring the electric power sector in Romania

    International Nuclear Information System (INIS)

    Metes, Mircea

    2001-01-01

    The paper presents the first steps of the energy market development in Romania and the impact of this process on 'Nuclearelectrica' company which operates the Cernavoda NPP. The main directions of the power sector liberalization in the European Union are being implemented in Romania. 'Nuclearelectrica' attempts to comply with both economic and safety requirements for nuclear plant operation. So far, the evolution of power market proved the competitiveness of Cernavoda Unit 1 with the existing power producers in Romania. It is stressed that although the 'Hydroelectrica' company sells the MWh at a lower price it cannot cope with top demands higher than 2400 MW. Economical aspects are analyzed and the conclusion is drawn that the situation of 'Nuclearelectrica' company will be significantly changed after the commissioning of Cernavoda Unit 2. (author)

  13. ROMATOM- the Romanian Atomic Forum, a Romanian voice in the choir of the European nuclear industry

    International Nuclear Information System (INIS)

    Pall, Stefan; Stiopol, Mihaela

    2001-01-01

    The Romanian Atomic Forum-ROMATOM is the national representative of the Romanian nuclear industry in the European forum. The paper presents the scope, objectives and the involvement of the organization in the completion and commissioning of the Cernavoda NPP Unit 2. The recent activities of ROMATOM are related to actions of lobby, some of cooperation with other organizations (AGIR, AREN, SRRp) in favor of nuclear power development in Romania and development of national nuclear equipment industry. Also, ROMATOM representatives attended the FORATOM working groups dealing with AQ and energy supply security as well as to the organizing committee of European Nuclear Society which held its 4th European Conference in October 2002 at Lile, France. The paper presents a schedule of ROMATOM activities for 2001-2003. Particularly, actions for boosting Cernavoda NPP Unit 2 completion as well as Romanian nuclear industry are mentioned. (authors)

  14. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2000-01-01

    In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

  15. Power sale. An activity of increasing importance in S.N Nuclearelectrica S.A

    International Nuclear Information System (INIS)

    Metes, Mircea

    2006-01-01

    The paper discusses the main characteristics of the power market in Romania. S. N. Nuclearelectrica S.A., the operator of Cernavoda nuclear power plant, is a new power supplier on this market. The price formation of the power sold by S. N. Nuclearelectrica S. A., its participation to the power market as well as the structure of the production costs at Cernavoda NPP are presented. The paper has the following contents: The electricity companies; - From service supplier to wholesale dealer; - Regulated contracts vs. free market; - The shock from 1 July 2005; - The last but not the final challenge. At the above noted date two events with an direct impact upon the power sale by Nuclearelectrica S.A. in Romania took place: 1.The new Trade Code of the power gross market became operative; 2. The opening degree of the free market raised steeply from 55% to over 83% of the energy demand, all the industrial consumers having the right of having the statute of 'eligible consumer'. The conclusion of the paper is that the reduced production cost in the nuclear unit as compared with those of classical stations, as well as a correct planning of the production are favorable premises to a successful transaction and sale of power produced at Cernavoda NPP

  16. Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

    Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

  17. Tritium and radon risks for humans

    International Nuclear Information System (INIS)

    Mauna, Traian; Mauna, Andriesica

    2008-01-01

    Full text: The gaseous and liquid releases into environment from the two CANDU type units of Cernavoda NPP now in operation has more tritium contents than other kind of western power reactors. CANDU type reactor uses heavy water as moderator and primary circuit heat transfer agent. In normal operation deuterium go to tritium by neutron capture, the molecule of tritiated heavy water can escape from nuclear systems in very small amounts and so it is released into environment. After release the tritium follows the way of water into environment. One year ago the antinuclear NGO led a hard attack against Units 3 and 4 during the procedure of public acceptance request. This attack tried to demonstrate the great risk for humans of the tritium released by Cernavoda NPP. Obviously this risk is very low as demonstrated by many years reactor operation. SNN as owner of Cernavoda NPP ensures by all kind of information channels about the radioactive potential risk for humans. By the other hand, ironically, the antinuclear NGO makes nothing to inform the people about radon risk magnitude in some areas. This is a well-known fact but the radon concentration in dwellings can be decreased by some improved building procedures. The radon is the first natural cause of lung cancer. The environmental NGO and Romanian authorities do not have an information service about radon hazard data neither in dwellings or in uranium mining areas. The paper compares the properties and risks for tritium and radon. (authors)

  18. 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)

  19. Task to Training Matrix Design for Decommissioning Engineer on the basis of Systematic Approach to Training Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Kwak, Jeong Keun [KHNP, Ulsan (Korea, Republic of)

    2016-10-15

    In nuclear history, before Chernobyl Accident, Three Mile Island (TMI) Accident was the severest accident. For this reason, to resolve the disclosed or potential possibilities of nuclear accident, more than one hundred countermeasures were proposed by United States Nuclear Regulatory Commission (USNRC). Among various recommendations by USNRC, one suggestion was related to training aspect. It was Systematic Approach to Training (SAT) and this event was the initiation of SAT methodology in the world. In Korea, upcoming June 2017, Kori Unit-1 NPP is scheduled to be shut down and it will experience NPP decommissioning for the first time. Present study aims to establish concrete training foundation for NPP decommissioning engineers based on Systematic Approach to Training (SAT) methodology, in particular, Task to Training Matrix (TTM). The objective of this paper is to organize TTM on the basis of SAT for NPP decommissioning engineer. For this reason, eighteen tasks are yielded through Job and Task Analysis (JTA) process. After that, for the settlement of Task to Training Matrix (TTM), various data are determined such as element, condition, standard, knowledge and skill, learning objective and training setting. When it comes to training in nuclear industry, SAT methodology has been the unwavering principle in Korea since NPPs export to UAE.

  20. Nuclear power plant personnel training and its evaluation. A guidebook. Executive summary

    International Nuclear Information System (INIS)

    1997-05-01

    The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs

  1. Planning, conduct and principal features of NPP emergency exercises in Switzerland

    International Nuclear Information System (INIS)

    Baggenstos, M.

    1993-01-01

    Emergency exercises for each NPP are required on a regular basis by the Swiss Nuclear Safety Inspectorate. The purpose of such exercises is to train the NPP staff and the on-site emergency organization in the application of the emergency procedures and the cooperation with off-site emergency teams and public authorities. The paper discusses the purpose of the emergency exercises and experiences made especially with bilateral exercises. The responsibilities for the preparation and execution of the different emergency exercises in Switzerland are explained

  2. 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

  3. Qualitative and quantitative methods for human factor analysis and assessment in NPP. Investigations and results

    International Nuclear Information System (INIS)

    Hristova, R.; Kalchev, B.; Atanasov, D.

    2005-01-01

    A description of the most frequently used approaches for human reliability assesment is given. The relation between different human factor causes for human induced events in Kozloduy NPP during the period 2000 - 2003 is discussed. A comparison between the contribution of the casual factors for events occurrences in Kozloduy NPP and an Japanese NPP is presented. It can be concluded that for both NPPs the most important casual factors are: 1) written procedures and documents; 2) man-machine interface; 3) environmental working conditions; 4) working practice; 5) training and qualification; 6) supervising methods

  4. 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.

  5. SAT for instructor training. An experience in implementation

    International Nuclear Information System (INIS)

    Ioujakov, A.Yu.

    2002-01-01

    In this paper, the main approaches for Instructor Training are presented been verified and approved by practice within Russian NPP Training organisations during last 5 years. The instructor selection, recruitment and followed training activities are an essential strategy plan for any NPP training organisation if the latter wants to provide effective training of NPP personnel. The strategy how to reach and maintain the competencies of instructors (or trainers) is explained; key points of instructor training programmes, both initial and continuing, are also discussed. The approaches concerned Instructor Training Programs being in compliance with the best of the Russian and international practice are defined and presented; these approaches in the field of instructor training. Initial and continuous training parts of whole program are discussed including specific modules/parts and principles to be used. Some examples extracted from verified and implemented training courses are presented and discussed. (author)

  6. The simulator Neck-Mfgs and its training status

    International Nuclear Information System (INIS)

    Setnikar, T.; Pribozic, F.; Srebotnjak, E.; Gortnar, O.; Kovacic, J.; Stritar, A.

    1998-01-01

    This paper presents the status and training possibilities on Krsko NPP Multi-Functional Simulator (NEK-MFS). Since spring 1997 it serves as a training facility in Nuclear Training Center. During first year of operation the simulator NEK-MFS was found to be a very useful Krsko NPP specific tool which is capable to support both the initial operator training program and licensed operator retraining activities.(author)

  7. Prospects of nuclear power development in Romania

    International Nuclear Information System (INIS)

    Valeca, Serban Constantin; Popescu, Dan

    2003-01-01

    Nuclear Power Development in Romania of a series of projects and national programs among which the Research Development and Innovation National Plan, Rainless, Infrastructure and Standardization, Infra, Quality and Standardization, Castle, Agriculture and Food, Aural, Environment Power and Energy Resources, Territory Remedy and Transportation, Aminotris, Life and Health, Vitasan, Stimulation of Patent Applications, Invent, Information based Society, Infancies, Bio technologies, Biotech, New Materials, Micro-Nano Technologies Machinate, Aeronautical and Space Technologies, Basic Research of Socioeconomic and Cultural Significance, Cereus, International Cooperation and Partnership, Coring, Also discussed are the nuclear national organizations implication in connection with numerous international on-going programs and projects such as U E Frame Program 6, IAEA Technical Cooperation Programs, Jr Research Programs, Technical Cooperation with DOE-USA (LANL), JINR Research Programs, CERN Research Programs and the programs of other international organizations working in the field of nuclear regulations, radiation protection, radioactive waste and spent fuel management, nuclear safety at Cernavoda NPP and improvement of radiotherapy services, The paper presents the major issues of the peaceful uses of nuclear energy worldwide and in Romania as well as the objectives and strategies of the National Nuclear Plan. The objective of covering 40% of the energy demand from nuclear sources will be reached under strict compliance with the principles of sustainable socio-economic development, in a competitive market environment and strict observance of nuclear safety assurance within the international standard provisions. Finally, the paper addresses issues relating to personnel education and training, public information and acceptance, legislative aspects, the great advantages of nuclear power (small cost, implication of domestic industry in the nuclear effort, environment friendly, earth

  8. Cernavoda NPP integration in the Romanian grid

    International Nuclear Information System (INIS)

    Prodan, R.C.

    2000-01-01

    The intention of this material is to present our point of view about some specific matters that arise from having a relatively large power production unit (706 MW) connected to a National Grid in which the second largest units are only 330 MW. The material consists in three major parts. In the first section is presented the 'big picture' of the Romanian National Grid. The second section covers the role played by CNPP in the grid power balance and frequency/voltage adjustment. CNPP is located at the base of the daily load curve and thus not normally participating at frequency adjustment. CNPP also has a contribution in increasing the dynamic stability of the National Grid. The third section is a more detailed presentation of CNPP behavior during grid upsets, with reference to the reactor and turbine control systems, and also the types of transients that our plant could induce to the grid due to internal malfunctions. The over-all unit control is based on the 'reactor power constant' policy, all the fluctuations in the power output to the grid being compensated by the Boiler Pressure Control System. Some features of the Turbine Electro-Hydraulic Control System and how it interacts with the Boiler Pressure Control Sys. will also be presented. The types of transients that CNPP could experience are reactor power setbacks (automatic ramped power reductions), reactor power step-backs (fast controlled power reduction) and unit trips, which are the most severe. There are two ways from the grid point of view to deal with such transients; to compensate the power loss by increasing the production and to disconnect unimportant power consumers. These actions are taken both automatically and manually (some details will be presented). (author)

  9. Contribution of Nuclear Training Centre in Ljubljana to Training and Information in the Area of Nuclear Technology

    International Nuclear Information System (INIS)

    Stritar, A.

    1998-01-01

    Nuclear Training Centre in Ljubljana ia a part of the Jozef Stefan Institute. The paper presents its main activities, which consist of training for NPP Krsko staff, training in the area of radiation protection, organization of international training courses and public information. NPP Krsko personnel obtains initial technical training at our training centre. We are also offering training courses and licensing for people working with radioactive substances in medicine, industry and science. We are internationally recognized training centre for organization of regional and interregional courses and meeting. Our fourth activity is public information. We are visited by around 7000 students per year and answer to every question about nuclear energy. (author)

  10. 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)

  11. TEAMproTM: The complete training evaluation, analysis, and management system, professional edition

    International Nuclear Information System (INIS)

    Bruno, Ronald J.; Armistead, Michael W.; Fish, James R. . Web sites: www. exitech. com; www. exitech.net

    2003-01-01

    The Systematic Approach to Training (SAT) has become the internationally accepted standard of identification, organization, development, and delivery of performance-based training. Through use of the SAT process the industry is provided with a consistent methodology to determine the level of knowledge and skills that are required to perform job related tasks at a nuclear power plant (NPP). However, due to the complexity of each NPP job position an enormous volume of data is required to develop, deliver, and maintain a performance based training program. The burden of managing this data has fallen upon the NPP training department. Proficient information management is essential to ensure all aspects of job performance are incorporated into the individual training programs. In addition, training program effectiveness can be increased through the relational tracking of analysis materials, which result in an efficient training setting delivery of learning objectives. The desire to increase training effectiveness and decrease the data management burden has driven NPP training department personnel to seek a SAT based information management system, in the form of a relational database. The desired database product will act as a tool to track and manage all aspects of the material used during development and conduct of training. There are several third party training management database products available in today's marketplace. Each provides solutions to specific needs in specialized training environments such as training of NPP Licensed Operators, and technical vocational training of electricians, mechanics, and crane operators. Each training area has its own unique training requirements, whether dictated by regulatory agencies, or mandated by in-house management decisions. This paper will offer a single relational database solution that is intended to support all aspects of NPP training requirements. This product is TEAMSpro TM . (author)

  12. Khmelnitsky NPP personnel training system improvement

    International Nuclear Information System (INIS)

    Sapronov, V.G.; Issupov, V.I.

    1996-01-01

    Khmelnitsky nuclear power plant personnel training system improvement is described, including creation of Training center, development of training courses based on SAT methodology, development of training hardware

  13. Improvement of NPP training to ensure a transfer of critical knowledge

    International Nuclear Information System (INIS)

    Vaisnys, P.; Bieth, M.; Kosilov, A.; Lipar, M.

    2007-01-01

    found in several OSART missions that at some nuclear utilities human related factors including knowledge transfer are not properly addressed. The following deficiencies are the typical representatives of the shortcomings in training programmes which may lead to critical knowledge losses and not adequate competence of NPP staff: Lack of systematic job and task analysis as a basis for specifying the content of training programmes and assessment criteria; The refresher training is not based on the job specific needs and knowledge gap analysis; Insufficient details (e.g., description of training content, learning objectives, assessment criteria) of the training programme; Inadequate incorporation of lessons learned from external operational experience; Insufficient training in safety awareness and safety culture. Many NPPs have well equipped Maintenance Training Centres with mock-ups of reactor, steam generator, reactor cooling pump, all types of valves (e.g. to train packing), control rod drives, rotating machines). This allows conducting effective training of maintenance personnel, however in some NPPs such equipment is missing. Main deficiencies in the maintenance training are that the maintenance training does not include lessons learned from experienced workers, from industry events, changes in plant maintenance programmes and approaches. Despite that the on-job training, which is the basis for the acquiring the adequate competence for some maintenance position, is not provided with job specific training in a facility workshops and does not ensure a transfer of knowledge. The weak point of the training management is the assessment of the training results and acquiring knowledge. The lack of assessment of training effectiveness does not ensure that it will meet the quality standards for ongoing and perspective staff performance needs. In some cases the evaluation of training programmes focuses mainly on the numerical indicators (number of attendees, training events

  14. Changing NPP consumption patterns in the Holocene: from Megafauna "liberated" NPP to "ecological bankruptcy"

    Science.gov (United States)

    Doughty, C.

    2015-12-01

    There have been vast changes in how net primary production (NPP) is consumed by humans and animals during the Holocene beginning with a potential increase in availability following the Pleistocene megafauna extinctions. This was followed by the development of agriculture which began to gradually restrict availability of NPP for wild animals. Finally, humans entered the industrial era using non-plant based energies to power societies. Here I ask the following questions about these three energy transitions: 1. How much NPP energy may have become available following the megafauna extinctions? 2. When did humans, through agriculture and domestic animals, consume more NPP than wild mammals in each country? 3. When did humans and wild mammals use more energy than was available in total NPP in each country? To answer this last question I calculate NPP consumed by wild animals, crops, livestock, and energy use (all converted to units of MJ) and compare this with the total potential NPP (also in MJ) for each country. We develop the term "ecological bankruptcy" to refer to the level of consumption where not all energy needs can be met by the country's NPP. Currently, 82 countries and a net population of 5.4 billion are in the state of ecologically bankruptcy, crossing this threshold at various times over the past 40 years. By contrast, only 52 countries with a net population of 1.2 billion remain ecologically solvent. Overall, the Holocene has seen remarkable changes in consumption patterns of NPP, passing through three distinct phases. Humans began in a world where there was 1.6-4.1% unclaimed NPP to consume. From 1700-1850, humans began to consume more than wild animals (globally averaged). At present, >82% of people live in countries where not even all available plant matter could satisfy our energy demands.

  15. A systematic approach to human performance improvement in nuclear power plants: Training solutions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance with respect to development, implementation and evaluation of training programmes for all NPP personnel. The IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared that provided further details concerning the training of NPP personnel on non-technical or soft skills. This report has been prepared in response to that recommendation. In the past, much of the focus of formal NPP training and development programmes was on the technical skills of NPP personnel, particularly those of control room operators. The environment in which NPPs operate is continually changing, placing new demands on NPP personnel to work more efficiently and effectively while continuing to maintain the high levels of safety required of NPPs. In this report, an integrated approach that considers training along with other ways to achieve desired levels of human performance is suggested.

  16. A systematic approach to human performance improvement in nuclear power plants: Training solutions

    International Nuclear Information System (INIS)

    2001-03-01

    In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance with respect to development, implementation and evaluation of training programmes for all NPP personnel. The IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared that provided further details concerning the training of NPP personnel on non-technical or soft skills. This report has been prepared in response to that recommendation. In the past, much of the focus of formal NPP training and development programmes was on the technical skills of NPP personnel, particularly those of control room operators. The environment in which NPPs operate is continually changing, placing new demands on NPP personnel to work more efficiently and effectively while continuing to maintain the high levels of safety required of NPPs. In this report, an integrated approach that considers training along with other ways to achieve desired levels of human performance is suggested

  17. Training scientist from developing countries

    International Nuclear Information System (INIS)

    Schultze-Kraft, P.

    1987-01-01

    The system of the training of specialists at the IAEA training courses, which are organized on interregional, regional and national basis, is presented. The necessity in the training of specialists in the given field, which is expressed by the states asking for assistance, is the main criterion for choosing subjects at the training courses. The IAEA has concentrated its attention on the courses in the following three directions: courses on the planning (expansion of power systems, prediction of needs in electric power); courses on the supervision (project realization, safety and reliability of NPP operation, radiation protection); courses for NPP construction inspectors, site selection, safety assessment. Training of teachers for national personnel is one of the new directions

  18. 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.

  19. IAEA Project UKR/4/003, Ukraine: Training for safe operation and management of nuclear power plants

    International Nuclear Information System (INIS)

    Kossilov, A.; Ivanytskyy, V.

    1998-01-01

    The IAEA Project UKR/4/003 was established with the aim to develop and upgrade Ukrainian NPP personnel training system in order to enhance the NPP operational safety and improve NPP management, through development of the SAT concept for personnel training

  20. Customization of RODOS expert system for use in Romania

    International Nuclear Information System (INIS)

    Mateescu, G.; Galeriu, D.; Slavnicu, D.; Berinde, A.; Craciunescu, T.; Margineanu, R.; Gheorghiu, A.; Gheorghiu, D.; Niculae, C.; Mocanu, N.

    1998-01-01

    In the frames of the PECO-FI4P - CT95 - 0007 and INCO COPERNICUS IC15 - CT96 - 0318 contracts the following research activities are developed: 1. The developing a geographic data base RoGIS, concerning the zones of nuclear interest for Romania (Cernavoda, Pitesti, Bechet). In this frame an information service concerning dwelling and industrial areas, land-use, traffic net-works, administrative boarder lines, hydrological data for Cernavoda area has been put in operation. 2. The coupling of IFIN-HH meteorological tower and RODOS system has been done, based on a dedicated software to adapt the meteorological information to the requirements of RODOS system. 3. The RODOS Data Base of Countermeasure and Emergency Management Data has been developed. It implied collecting of data for long term countermeasure application and the definition of five radiological data for Romania. From the study of five severe accident scenarios at CANDU-NPP, early countermeasures were obtained for the area around city of Cernavoda regarding: the intake of iodine tablets; - evacuation of population; - sheltering; - relocation based on simulated meteorological conditions. 4. The assessment of doses and dose rates in a neighbourhood of CANDU NPP in case of core disassembly. Based on accident scenarios and using Complementary Cumulative Frequency Distribution Technique (CCFD) dose rates for I-131, Cs-137 and H-3 and effective potential doses were obtained. In the case of an Early Core Disassembly the following data were obtained: - a lower limit dose rate of 4 x 10 -4 Sv/h for I-131 deposition and 10 -4 Sv/h for Cs-137; - a lower limit potential week dose of 7 Sv and a lower limit 50 year inhalation dose of 3 x 10 -1 Sv. The above estimations refer to a 2 - 8 Km zone around CANDU-NPP using 340 meteorological sequences. (authors)

  1. Radioactive waste management at nuclear power plant Cernavoda

    International Nuclear Information System (INIS)

    Raducea, D.

    2002-01-01

    Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. 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, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

  2. Nuclear public information in practice

    International Nuclear Information System (INIS)

    Mesaru, Daniela

    2001-01-01

    This presentation describes the site of Cernavoda-1 NPP, its history, decision making to build it, major public concerns related to NPP operation, fuel fabrication, Interim storage of spent fuel and spent fuel disposal, Transport of radioactive material,Emergency preparedness, Nuclear or radiological accidents. Within this scope the key messages to be communicated to the public are recommended. The public relation groups should communicate all the time with public - trying to send the main message: 'Nobody Wants To Hide Anything. We Are Always Open. Your Good Health Means We Can Still Produce Nuclear Power'

  3. Assessment of the cryogenic distillation system in Cernavoda tritium removal facility

    International Nuclear Information System (INIS)

    Pasca, Gheorghe; Draghia, Mirela; Porcariu, Florina; Ana, George

    2010-01-01

    Full text: This paper aims at presenting an assessment of the Cryogenic Distillation system (CD) in the Cernavoda Tritium Removal Facility (CTRF). The cryogenic distillation system is one of the key components of the CTRF which comprises other systems as: the liquid phase catalytic exchange system, designed to transfer tritium from heavy water to a deuterium stream to be fed into the CD system; the atmosphere detritiation system; the tritium recovery system; the tritium/hydrogen monitoring system; the central interlocking system; the tritium extraction and storage system. Thus, the need to build a tritium separation and recovery system results from economic opportunities offered both by heavy water reuse and tritium production, but, at the same time, it offers an alternative for the storage of tritiated heavy water as radioactive waste. (authors)

  4. Pioneer robot testing and training status

    International Nuclear Information System (INIS)

    Herndon, J.; Nosovsky, A.; Garin, E.; Goncharov, B.; Neretin, Y.

    2001-01-01

    The U. S. Department of Energy developed the Pioneer Robot and provided it to the Chornobyl Nuclear Power Plant (ChNPP) within the framework of international technical assistance. At the Pioneer Robot has been transferred to ChNPP ownership for broad use in ChNPP activities related to decommissioning and emergency response, as well as in Unit Shelter. Oak Ridge National Laboratory is working with ChNPP and SLIRT to test the Pioneer Robot operation in a broader scope, and to provide additional operational training

  5. Seismic assessment of a site using the time series method

    International Nuclear Information System (INIS)

    Krutzik, N.J.; Rotaru, I.; Bobei, M.; Mingiuc, C.; Serban, V.; Androne, M.

    1997-01-01

    To increase the safety of a NPP located on a seismic site, the seismic acceleration level to which the NPP should be qualified must be as representative as possible for that site, with a conservative degree of safety but not too exaggerated. The consideration of the seismic events affecting the site as independent events and the use of statistic methods to define some safety levels with very low annual occurrence probability (10 -4 ) may lead to some exaggerations of the seismic safety level. The use of some very high value for the seismic acceleration imposed by the seismic safety levels required by the hazard analysis may lead to very costly technical solutions that can make the plant operation more difficult and increase maintenance costs. The considerations of seismic events as a time series with dependence among the events produced, may lead to a more representative assessment of a NPP site seismic activity and consequently to a prognosis on the seismic level values to which the NPP would be ensured throughout its life-span. That prognosis should consider the actual seismic activity (including small earthquakes in real time) of the focuses that affect the plant site. The paper proposes the applications of Autoregressive Time Series to issue a prognosis on the seismic activity of a focus and presents the analysis on Vrancea focus that affects NPP Cernavoda site, by this method. The paper also presents the manner to analyse the focus activity as per the new approach and it assesses the maximum seismic acceleration that may affect NPP Cernavoda throughout its life-span (∼ 30 years). Development and applications of new mathematical analysis method, both for long - and short - time intervals, may lead to important contributions in the process of foretelling the seismic events in the future. (authors)

  6. Identification of NPP accidents using support vector classification

    Energy Technology Data Exchange (ETDEWEB)

    Back, Ju Hyun; Yoo, Kwae Hwan; Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

    2016-10-15

    In case of the accidents that happens in a nuclear power plants (NPPs), it is very important to identify its accidents for the operator. Therefore, in order to effectively manage the accidents, the initial short time trends of major parameters have to be observed and NPP accidents have to accurately be identified to provide its information to operators and technicians. In this regard, the objective of this study is to identify the accidents when the accidents happen in NPPs. In this study, we applied the support vector classification (SVC) model to classify the initiating events of critical accidents such as loss of coolant accidents (LOCA), total loss of feedwater (TLOFW), station blackout (SBO), and steam generator tube rupture (SGTR). Input variables were used as the initial integral value of the signal measured in the reactor coolant system (RCS), steam generator, and containment vessel after reactor trip. The proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. In this study, the proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. We used an initial integral value of the simulated sensor signals to identify the NPP accidents. The training data was used to train the SVC model. And, the trained model was confirmed using the test data. As a result, it was known that it can accurately classify five events.

  7. The Hungarian model project: Strengthening training for operational safety at Paks nuclear power plant

    International Nuclear Information System (INIS)

    Mautner Markhof, F.

    1998-01-01

    The Hungarian Model project (HMP) reflects the commitment to constant increase of safety and reliability of the NPP Paks, the Government of Hungary and the IAEA. It includes some of the most important nuclear power objectives of Paks NPP, namely the strengthening of NPP personnel training and competence through the application of international best practice, the systematic approach to training (SAT), for training operation and maintenance personnel; setting up a state of-the-art maintenance training center (MTC) at Paks and enhancing safety culture at Paks NPP. The IAEA supported implementation of the HMP through fellowships and scientific visits, expert missions, provision of hardware and software for SAT application, and supply od major new uncontaminated items of actual WWER equipment for the MTC

  8. Simulator experiments: effects of NPP operator experience on performance

    International Nuclear Information System (INIS)

    Beare, A.N.; Gray, L.H.

    1985-01-01

    Experiments are being conducted on nuclear power plant (NPP) control room training simulators by the Oak Ridge National Laboratory, its subcontractor, General Physics Corporation, and participating utilities. The experiments are sponsored by the Nuclear Regulatory Commission's (NRC) Human Factors and Safeguards Branch, Division of Risk Analysis and Operations, and are a continuation of prior research using simulators, supported by field data collection, to provide a technical basis for NRC human factors regulatory issues concerned with the operational safety of nuclear power plants. During the FY83 research, a simulator experiment was conducted at the control room simulator for a GE boiling water reactor (BWR) NPP. The research subjects were licensed operators undergoing requalification training and shift technical advisors (STAs). This experiment was designed to investigate the effects of (a) senior reactor operator (SRO) experience, (b) operating crew augmentation with an STA and (c) practice, as a crew, upon crew and individual operator performance, in response to anticipated plant transients. The FY84 experiments are a partial replication and extension of the FY83 experiment, but with PWR operators and simulator. Methodology and results to date are reported

  9. Romanian nuclear higher education towards a network of excellency

    International Nuclear Information System (INIS)

    Ghitescu, Petre

    2006-01-01

    RONEN - Romanian Nuclear Education Network - aims at becoming the future network of excellency for nuclear higher education in Romania. University Politehnica of Bucharest participated in ENEN and NEPTUNO FP-5 and FP-6 programs, being a founding member of ENEN Association. The experience gained by ENEN as well as the present European trends show that realization of associations and networks endow with more power the educational national capacities and makes easier the European cooperation. The objective of this project is to develop an efficient, flexible and modern system in the nuclear education field, able to comply with the requirements of final users (NPP operators, regulations organisms, subcontractors, decommissioning operators, radiation protection, personnel, radioactive waste disposal managers), complying at the same time with the common European perspectives of education and research (FP-6, FP-7, EUROATOM). This system is the proposed network of excellency, gathering all the Romanian institutions (universities, research-development centers, training centers, etc) implied in the nuclear education field and using the existent experience of BNEN (Belgian Network of Nuclear Education) and ENEN. The participants in RONEN are the Universities of Bucharest, Pitesti, Babes-Bolyai in Cluj-Napoca, the Vocational Training Center of National Institute for R and D in Physics and Nuclear Engineering Bucharest, the Training Center of Cernavoda NPP, and the Institute for Nuclear Research in Pitesti

  10. 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

  11. Potential role of the Romanian research and industry on the small and medium reactors market

    International Nuclear Information System (INIS)

    Rapeanu, S.N.; Bujor, A.; Comsa, O.

    1998-01-01

    The need of diversifying the energy sources, independence from foreign supplies and modernization of economy have constituted the major factors in implementation of nuclear energy in Romania. The choice of the heavy water reactor CANDU-600 was made on grounds of advanced safety features, proven efficient economic operation as well as on the technologic feasibility for manufacturing of components, equipment, instrumentation, heavy water and natural uranium fuel in Romania. Unlike turn-key acquisition approaches, the Romanian option provided an active national participation in construction the Cernavoda NPP. As consequence, important support was being given to development of the industries involved in the nuclear fuel cycle, manufacturing of equipment and nuclear materials, construction-montage, engineering, consulting, services, etc. This was done based on technology transfer, implementation of advanced design and execution standards, quality assurance procedures and modern nuclear safety requirements at international level. The efforts materialized in an important national participation in the construction of the Cernavoda NPP and all related programs are successful. Now, Romanian firms are also involved in supplying components, equipment and services to NPP's in other eastern and central Europeans countries. The paper presents the achievements of the Romanian economy in this field and the effort of the Romanian companies on the small and medium power reactors market. Lists with main R and D institutes, nuclear fuel cycle facilities as well as potential equipment suppliers are attached. (author)

  12. 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

  13. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    International Nuclear Information System (INIS)

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2009-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  14. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    International Nuclear Information System (INIS)

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2008-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  15. Nuclear power plant personnel entry level qualifications and training

    International Nuclear Information System (INIS)

    Jorgensen, C.C.; Haas, P.M.; Selby, D.L.; Lowry, J.C.

    1983-01-01

    This paper summarizes the early results and current status of a research program at ORNL which is intended to provide the methods and technical basis for NRC to initiate the use of the Systems Approach to Training (SAT) in the evaluation of training programs and entry level qualifications for NPP control room personnel. The program is an outgrowth of previous studies of simulator hardware and simulator training requirements under the Safety Related Operator Actions Program which recommended adaptation of a systems methodology to development and evaluation of NPP training programs

  16. Training centres - organization and management

    International Nuclear Information System (INIS)

    Kovar, P.

    1986-01-01

    In the lecture 'Training centres - organization and management' some principles and requirements which influence the organization, management and activity pattern of nuclear training centres, are briefly introduced. It is demonstrated, step by step, how these general principles are implemented in the development of the Czechoslovak nuclear power programme, it means, how the training of the NPP personnel proceeds in Czechoslovak nuclear training centres. General principles which are selected: a connection between the capacity of the training centre and the scope and needs of the nuclear power programme, a position of the training center within the institutional set-up, a structure and organization of the training system which complies with the system of NPP construction, reflect the pattern and the activity of the nuclear training centre and nuclear power technical level, a research group of workers in the nuclear training centre, main tasks and technical facilities, management of the training process and a transfer of knowledge and research results into the training process. The lecture is supplemented by pictures and slides. (orig.)

  17. Cernavoda NPP - Boiler and steam cycle chemistry control

    International Nuclear Information System (INIS)

    Zotica, D.

    2001-01-01

    Steam generators protection against corrosion and fouling is an ongoing issue for nuclear power plants. The true effectiveness of the secondary chemistry control program is best judged by the absence of secondary side corrosion related tube degradation particularly that leads to tube plugging or sleeving or tube support degradation. To continue striving for excellence in chemical control, the following issues should be considered: Continuous evaluation of the effectiveness of the chemistry control program in mitigating SG damage; Evaluation of plant compliance with the program; Laboratory quality assurance program to assure that laboratory analyses are accurate and reproductibile; Quality assurance program for on-line monitoring equipment to assure that results from this equipment are accurate. (R.P.)

  18. Qinshan 300Mwe NPP full scope simulator upgrade

    International Nuclear Information System (INIS)

    Qi Kelin; Li Qing; Liu Wei, Lai Shengyuan

    2006-01-01

    On April 28,2004, RINPO was awarded the project for Qinshan 300Mwe NPP full scope simulator upgrade, the SAT (site acceptance test) was completed on June 30 2005 and the simulator put into operator training again. Scope of upgrade includes: computer system (DGI server and workstations) all replaced by microcomputers; G2 I/O controllers all replaced by RTP EIOBC; Unix-based simulation support environment replaced by RINPO's PC-based simulation environment RINSIMTM, Instructor software replaced by RINPO's PC-based instructor software with function and diagram redesigned; DEH, Feed-water control and some other digital control systems redeveloped to follow NPP modifications; desk-top simulator with soft panel control room developed as byproduct; most of the models not changed but it is planned the reactor core and PPC model will be upgraded in near future. SAT of upgrade demonstrates that the performance of the simulator much improved after the upgrade. (author)

  19. Aspects regarding the lifetime of a fuel channel in a CANDU nuclear power plant

    International Nuclear Information System (INIS)

    Calinescu, A.

    1998-01-01

    The paper presents the analysis of factors influencing upon the time life of a fuel channel of CANDU reactors built in Romania. Fuel channels are made of Zr-2.5%Nb alloy. Means and methodology to detect cracking of fuel channels are described, as well as improvements to increase life time of Cernavoda NPP fuel channels and national programme in this area. (author)

  20. Failure mode and effect analysis experimental reliability determination for the CANDU reactor equipment

    International Nuclear Information System (INIS)

    Vieru, G.

    1996-01-01

    This paper describes the experimental tests performed in order to prove the reliability parameters for certain equipment manufactured in INR Pitesti, for NPP Cernavoda. The tests were provided by Technical Specifications and test procedures. A comparison, referring to the reliability parameters, between Canadian equipment and INR manufactured equipment ones is also given. The results of tests and conclusions are shown. (author)

  1. Mochovce NPP experience in the certification and the use of full scope simulator

    International Nuclear Information System (INIS)

    Krenicky, L.

    1999-01-01

    The paper presents some of the Mochovce NPP experience in the full-scope simulator certification process, simulator training programs development, implementation and evaluation, the use of simulator in the all-plant emergency exercises as well as the experience in validation of plant operational procedures.(author)

  2. Lowering the risk at Chernobyl NPP by ventilation stack reparation: a success full international project

    International Nuclear Information System (INIS)

    Lazarev, S.V.

    1999-01-01

    Problems of NPP personnel professional adaptation, health protection and psychological stress are discussed. For main tainting good working capability in extemal situations a professional selection, special training and other psychological and psychotherapeutic actions are proposed

  3. International inventory of training facilities in nuclear power and its fuel cycle 1978

    International Nuclear Information System (INIS)

    1979-01-01

    The revised inventory is arranged according to the following subject areas: nuclear power plant (NPP) engineering, nuclear safety, quality assurance, NPP operation and maintenance, NPP instrumentation and control, nuclear fuel management, nuclear materials control. Training in each subject area is classified into five groups depending on the type of organization offering the training courses. Each course is briefly described by its name or purpose, institution and location, duration, frequency, language, and content

  4. 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

  5. IAEA activities in nuclear power plant personnel training and qualification

    International Nuclear Information System (INIS)

    Mautner-Markhof, F.

    1993-01-01

    Training to achieve and maintain the qualification and competence of nuclear power personnel is essential for safe and economic nuclear power. Technical Cooperation Meeting on Training-Related Activities for Nuclear Power Plant (NPP) Personnel in the countries of Central and Eastern Europe (CEEC) and of the former Soviet Union (FSU) has as its main objective the identification, through information exchange and discussion, of possible Technical Cooperation (TC) projects to assist Member States in meeting NPP personnel training needs and priorities, including the enhancing of training capabilities

  6. Vibration reduction at the engine-pumps assembly of the main moderator system

    International Nuclear Information System (INIS)

    Holostencu, Adriana; Dinu, Marius

    2005-01-01

    Problem of decreasing vibrations in the main moderator motor at Cernavoda NPP - Unit 1 is presented. The moderator pumps are of centrifugal, vertical, single stage and double suction type. Each pump is provided with a main motor (690 Kw, 50 Hz, 6 KV) capable of full rotative speed and a secondary motor, also known as 'pony motor' (15 Kw, 50 Hz, 380 V) capable of a quarter of the full speed. At starting-commissioning stage of Cernavoda NPP, the vibration level in the moderator pump - motor assembly had an average value of 6 mm/s with spurious peaks up to 8 mm/s. It has to be mentioned that operation with a high vibration level may lead to: - a premature wear of the motor bearings; - extra stresses and fatigue in the material of pump and associated pipes. In order to maintain vibration speed to the design limit, the NPP personnel have started investigations since 1997. The main activities were: - verification of the vibration measuring loops; - checking the torque of the bolts that hold the motor's case; - measuring the start-up and nominal currents of the motors in order to determine any phase unbalance; - adjusting the spring hangers from the pumps discharge with simultaneous monitoring of the motor vibration level; - installation of rubber pads in the gap between the motor lugs and the existing seismic supports. None of these actions revealed deviations from the installation requirements or operating parameters. In 1999, a contract with EUROTEST S. A and Stevenson was signed, in order to find a solution to reduce the vibration level. The EUROTEST/ Stevenson action plan contains de following main activities: 1. Creating a calculus model of the moderator system, based on the design drawings provided by Cernavoda NPP; 2. Preparing and performing the vibration measurements in various points of the system; 3. Analyzing the measurements results; 4. Calibrating the calculus model created in step 1, according with the field measurements; 5. Propose a solution to reduce

  7. The specific aspects for the ASSET methodology implementation in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Serbanescu, D [National Commission for Nuclear Activities Control of Romania (Romania)

    1997-10-01

    The main aspects of the implementation of a root cause analysis methodology are as follows: The Test Operating Licence requires that a systematical root cause analysis method for the event analysis to clarify the three questions from the ASSET methodology has to be implemented; A Training seminar on the ASSET methodology for the plant staff was performed at Cernavoda 1 NPP in April 1997, with the IAEA support; The self assessment process for the events which occurred during commissioning phases has to be performed by the plant up to the end of this year; An ASSET Peer Review of the Plant Self Assessment is planned in 1998; The Regulatory Authority has the task to evaluated independently the plant conclusions on various events. The tool used by CNCAN is the ASSET methodology.

  8. The specific aspects for the ASSET methodology implementation in Romania

    International Nuclear Information System (INIS)

    Serbanescu, D.

    1997-01-01

    The main aspects of the implementation of a root cause analysis methodology are as follows: The Test Operating Licence requires that a systematical root cause analysis method for the event analysis to clarify the three questions from the ASSET methodology has to be implemented; A Training seminar on the ASSET methodology for the plant staff was performed at Cernavoda 1 NPP in April 1997, with the IAEA support; The self assessment process for the events which occurred during commissioning phases has to be performed by the plant up to the end of this year; An ASSET Peer Review of the Plant Self Assessment is planned in 1998; The Regulatory Authority has the task to evaluated independently the plant conclusions on various events. The tool used by CNCAN is the ASSET methodology

  9. 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)

  10. Does climate directly influence NPP globally?

    Science.gov (United States)

    Chu, Chengjin; Bartlett, Megan; Wang, Youshi; He, Fangliang; Weiner, Jacob; Chave, Jérôme; Sack, Lawren

    2016-01-01

    The need for rigorous analyses of climate impacts has never been more crucial. Current textbooks state that climate directly influences ecosystem annual net primary productivity (NPP), emphasizing the urgent need to monitor the impacts of climate change. A recent paper challenged this consensus, arguing, based on an analysis of NPP for 1247 woody plant communities across global climate gradients, that temperature and precipitation have negligible direct effects on NPP and only perhaps have indirect effects by constraining total stand biomass (Mtot ) and stand age (a). The authors of that study concluded that the length of the growing season (lgs ) might have a minor influence on NPP, an effect they considered not to be directly related to climate. In this article, we describe flaws that affected that study's conclusions and present novel analyses to disentangle the effects of stand variables and climate in determining NPP. We re-analyzed the same database to partition the direct and indirect effects of climate on NPP, using three approaches: maximum-likelihood model selection, independent-effects analysis, and structural equation modeling. These new analyses showed that about half of the global variation in NPP could be explained by Mtot combined with climate variables and supported strong and direct influences of climate independently of Mtot , both for NPP and for net biomass change averaged across the known lifetime of the stands (ABC = average biomass change). We show that lgs is an important climate variable, intrinsically correlated with, and contributing to mean annual temperature and precipitation (Tann and Pann ), all important climatic drivers of NPP. Our analyses provide guidance for statistical and mechanistic analyses of climate drivers of ecosystem processes for predictive modeling and provide novel evidence supporting the strong, direct role of climate in determining vegetation productivity at the global scale. © 2015 John Wiley & Sons Ltd.

  11. 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)

  12. Ignalina NPP: living and working conditions

    International Nuclear Information System (INIS)

    Chiuzhas, A.

    1998-01-01

    The conference was devoted to discuss the social problems related with the operation of Ignalina NPP. The main topics are the following: analysis of public opinion of surrounding region of Ignalina NPP including neighbouring Daugavpils district in Latvia, environment impact evaluation of Daugavpils district, assessment of the influence of Ignalina NPP operation to the development of business in the region, investigation of problems of Visaginas town - residence of Ignalina NPP personnel. The specificity of Visaginas (former Sniechkus) is defined by the majority of non-native Lithuanians living there. Cultural transformation and political organization of the region were surveyed as well

  13. Nuclear Business Acumen Training for Executives

    International Nuclear Information System (INIS)

    Blomgren, Jan

    2014-01-01

    The presentation is structured as follows: Failure in large technology projects; Simulations in industry; Training in reactor simulators; Business simulation; NPP business simulation Nuclear Inc.; Knowledge retention; Boosting the effect of training; Contact

  14. Current status of the near surface repository in Romania

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.; Rotaru, I.

    2000-01-01

    The radioactive waste management at the Cernavoda NPP is based on collection, pretreatment and storage of all solid wastes. The disposal of operational and decommissioning wastes has been evaluated, based on the results of a research and development programme. A near surface disposal facility was selected and a siting process was implemented. The status of this project and its prospective are discussed in the paper. (author)

  15. A methodology of selection of exercises for operator training on a control room simulator and its application to the data bank of exercises at the Dukovany NPP

    International Nuclear Information System (INIS)

    Holy, J.

    2005-07-01

    The report describes the preparation of methodology for the selection of scenarios to be used during operator training on a full-scope simulator. The scenarios are selected from a data bank of scenarios, which is under preparation based on feedback from the operational history and theoretical analyses. The new methodology takes into account 3 basic attributes defining the priority for use within the training programme: frequency of occurrence, safety-related significance, and difficulty. The attributes are scored and based on a joint score, the importance of inclusion of the scenario in the training programme is also scored. The methodology was applied to the data bank of scenarios for simulation of abnormal states and incidents trained on the up-to-date simulator of the Dukovany NPP, and the results of this pilot application were made available to Dukovany operator training staff as a tool for the preparation of training plans for the years to come. The results of a PSA study are used for a non-trivial selection of the scenarios

  16. Personnel education and training at Bohunice NPP

    International Nuclear Information System (INIS)

    Malovec, J.

    1998-01-01

    Procedure for education and training of all the personnel employed at Bohunice Nuclear power plant is presented in detail describing the training system structure, kinds of training, staff members qualification development, short term and long term tasks needed to assure attaining the training objectives. The proposed Staff Members Lifetime education implementation project contains basic starting points, measures to be implemented by 1998. It was prepared on the basis of a primary analysis which confirmed the existing need for implementing the lifetime education system

  17. IAEA activities on safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    Pachner, J.

    1998-01-01

    A review of IAEA activities concerned with safety aspects of nuclear power plants ageing is given for the period from 1995 to 1998 with the prospects till year 2000. Coordinated Research programs were conducted on Management Ageing of Concrete Containment Buildings; Management of Ageing of In-Containment I and C cables. TECDOCs were published on Assessment and Management of Ageing of Major NPP Components Important for Safety of CANDU, PWR and BWR NPPs. Technical Committee Meetings and Interregional training courses concerned with the same subjects were held

  18. Periodical safety review of units 1 and 2 of PAKS NPP. Examples from summary report

    International Nuclear Information System (INIS)

    Hammar, K.

    1998-01-01

    On the basis of American practice of qualification and relevant IAEA recommendations detailed guidelines of the qualification procedure were developed and executed on the Units 1 and 2 of the Paks NPP. Periodic safety supervision will be performed by evaluation of the following reports to be submitted by NPP: real technical conditions of the facility; existing practice and proposals for equipment qualification; evaluation of the existing safety reports estimating their validity up to the plant lifetime; ageing and ageing management; procedures of operation, maintenance, supervision; organisation and administration; safety impact of human factor, training, education, qualification of personnel

  19. 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)

  20. Financing arrangements for nuclear power projects - Past and present experience, future expectations

    International Nuclear Information System (INIS)

    Troncuta, Mariana; Vatamanu, Maria; Ispas, Gheorghe

    2003-01-01

    Nuclear energy is a clean, safe, and economical industrial electricity source, with many environmental benefits. It does not emit greenhouse gases that contribute to climate change, or combustion by-products and acid gases that cause air, water resource and land pollution. Nuclear energy has also many benefits in the areas of medicine, industry, agriculture, and research. Moreover, the results are revealing. Over the past 12 years, from 1900 to 2002, the global 'energy availability factor' - representing the percentage of time that nuclear power plants worldwide were up and running - increased from 72.9% to 83.4%. At the same time, based on statistics gathered by the World Association of Nuclear Operators - WANO, the number of industrial accidents has gone down, radiation exposure has dropped sharply and the annual volume of radioactive waste produced has been reduced substantially. In other words, the safety, performance and economic competitiveness of the nuclear industry are at an all time high, reflecting a mature and vibrant enterprise. These are several reasons why a prospective host nation and other nations around the world may be attracted by nuclear power generation. Nuclear power can be and has been financed by world capital markets. The crucial question is whether host governments and interested utilities are willing to take the steps required to attract investment with reasonable assurance of success, and whether the nuclear industry is willing and able to become competitive in increasingly deregulated financial and electricity markets. The present paper will have the following structure: the first part will refer to general financing guidelines, and the second part will present a case study. The latter will treat the past experience as provided by the financing scheme of Cernavoda NPP Unit 1, the present experience, i.e. ongoing financing issues for Cernavoda NPP Unit 2 and potential future shared contribution to financing Cernavoda NPP Unit 3, 4 and 5

  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. Methods and means for improving the man-machine systems for NPP control

    International Nuclear Information System (INIS)

    Konstantinov, L.V.; Rakitin, I.D.

    1984-01-01

    Consideration is being given to the role of ''human factors'' and the ways of improving the man-machine interaction in NPP control and safety systems (CSS). Simulators and tAaining equipment on the basis of dynamic power unit models used for training and improving skill of NPP operatoAs, as well as for mastering collective actions of personnel under accidental conditions are considered in detail. The most perfect program complexes for fast NPP diagnostics and theiA pealization in the Federal Republic of Germany, Japan, Canada, the USA and other countries are described. A special attention is paid to the means and methods of videoterminal dialogue operator interaction with an object both in normal and extreme situations. It is noted that the problems of the man-machine interaction have become the subject of study only in the end of 70s after analyzing the causes of the Three-Mile-Island accident (USA). Publications dealing with the development of perspective control rooms for NPP were analyzed. It was concluded that radical changes both in equipment and principles of organizing the personnel activity will take place in the nearest future. They will be based on the progress in creating dialogue means and computers of the fourth and fifth generations as well as on engineering and psychological and technical aspects of designing

  3. A brief overview of Ignalina NPP safety issues

    International Nuclear Information System (INIS)

    Almenas, K.; Ushpuras, E.

    1998-01-01

    A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

  4. Potential role of the Romanian research and industry on the small and medium reactors market

    Energy Technology Data Exchange (ETDEWEB)

    Rapeanu, S N; Bujor, A [National Agency for Atomic Energy, Bucharest (Romania); Comsa, O [Center of Technology and Engineering for Nuclear Projects, Bucharest (Romania)

    1998-02-01

    The need of diversifying the energy sources, independence from foreign supplies and modernization of economy have constituted the major factors in implementation of nuclear energy in Romania. The choice of the heavy water reactor CANDU-600 was made on grounds of advanced safety features, proven efficient economic operation as well as on the technologic feasibility for manufacturing of components, equipment, instrumentation, heavy water and natural uranium fuel in Romania. Unlike turn-key acquisition approaches, the Romanian option provided an active national participation in construction the Cernavoda NPP. As consequence, important support was being given to development of the industries involved in the nuclear fuel cycle, manufacturing of equipment and nuclear materials, construction-montage, engineering, consulting, services, etc. This was done based on technology transfer, implementation of advanced design and execution standards, quality assurance procedures and modern nuclear safety requirements at international level. The efforts materialized in an important national participation in the construction of the Cernavoda NPP and all related programs are successful. Now, Romanian firms are also involved in supplying components, equipment and services to NPP`s in other eastern and central Europeans countries. The paper presents the achievements of the Romanian economy in this field and the effort of the Romanian companies on the small and medium power reactors market. Lists with main R and D institutes, nuclear fuel cycle facilities as well as potential equipment suppliers are attached. (author). 9 refs, 3 figs.

  5. 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.)

  6. Nuclear education, training and support

    International Nuclear Information System (INIS)

    Vityazev, Vsevolod; Ushakov Artem

    2016-01-01

    The structure and key elements of the ROSATOM education and training system are presented. Educational and training services and technical support are provided during the NPP lifetime, including nuclear Infrastructure, nuclear power plant personnel training, equipment and post-warranty spare parts, nuclear power plant operation support, maintenance and repair, modernization and lifetime extension

  7. Danube quality water assessment from the microbiological point of view in Cernavoda nuclear plant area

    International Nuclear Information System (INIS)

    Sundri, Mirela Iuliana

    2003-01-01

    Herein are analysed the following microbiological parameters: total viable count, total coliforms and faecal coliforms, which represent a standard indicator for water quality. The study has been done during 1998-2002 upon the water in the Danube River and in the channels for cooling water used by Cernavoda Nuclear Power Plant condensers. In this area, based on these values of evaluated parameters, the water feature is placed in the quality classes II and III (moderate and critical pollution), in conformity with European Community Directives. Bacterial communities, component part of aquatic biocenoses, are very important for matter and energy flux. Their contribution to self-purification processes of rivers is of great interest related to the water quality assessment. Microorganisms are ideal sensors, because they respond fast to the fluctuation of environmental conditions by specific changes, detectable physiologically and metabolically. The temperature is a major factor, which directly affects the intensity of all microbial processes. Because the microorganisms are interconnected with the other living organisms, the qualitative or quantitative changes of their activity will affect the functions of the whole ecosystem. Bacterial indicators such as total viable count (colony count), total coliforms or faecal coliforms (thermo-tolerant coliforms) are widely applied to the assessment of water quality. Because of their mostly allochthonus origin, these are used as indicators of changes in the natural water conditions; they point out an organic matter or faecal water pollution. Although the water quality can be considered acceptable from the chemical or biological point of view, the bacteriological parameters might be detected in critical concentration. The objectives of this microbiological assessment are analysis of the variation of bacteriological indicators in some sampling points of Cernavoda aquatic ecosystems area, and monitoring the manner of using the water by

  8. Experience in exchanging pipes in NPP containments

    International Nuclear Information System (INIS)

    Russell, D.J.

    1987-01-01

    Very careful planning and scheduling of NPP retrofit projects involving replacement of piping, valves, pumps and steam generators is essential. To meet the schedule, the approved design engineering documents must be prepared in good time. A viable electronic data processing program must be adopted to track progress and feedback on-site, and care must be exercised during the last phase of the project, i.e. in preparation of the documentation packages. In addition, there must be training of a sufficient number of skilled and responsible personnel, and all necessary job positions must be manned adequately, with close attention paid to health physics

  9. 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)

  10. 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)

  11. Training for vigilance: using predictive power to evaluate feedback effectiveness.

    Science.gov (United States)

    Szalma, James L; Hancock, Peter A; Warm, Joel S; Dember, William N; Parsons, Kelley S

    2006-01-01

    We examined the effects of knowledge of results (KR) on vigilance accuracy and report the first use of positive and negative predictive power (PPP and NPP) to assess vigilance training effectiveness. Training individuals to detect infrequent signals among a plethora of nonsignals is critical to success in many failure-intolerant monitoring technologies. KR has been widely used for vigilance training, but the effect of the schedule of KR presentation on accuracy has been neglected. Previous research on training for vigilance has used signal detection metrics or hits and false alarms. In this study diagnosticity measures were applied to augment traditional analytic methods. We examined the effects of continuous KR and a partial-KR regimen versus a no-KR control on decision diagnosticity. Signal detection theory (SDT) analysis indicated that KR induced conservatism in responding but did not enhance sensitivity. However, KR in both forms equally enhanced PPP while selectively impairing NPP. There is a trade-off in the effectiveness of KR in reducing false alarms and misses. Together, SDT and PPP/NPP measures provide a more complete portrait of performance effects. PPP and NPP together provide another assessment technique for vigilance performance, and as additional diagnostic tools, these measures are potentially useful to the human factors community.

  12. Instructor training

    International Nuclear Information System (INIS)

    Yuzhakov, A.Yu.

    1995-01-01

    A SAT-based Instructor Training Course was developed and implemented at NVTC. The duration of the initial course is 3 weeks and 2 weeks for annual refresher course. NVTC has had much experience with this Instructor Training Course generating the following lessons-learned: SAT implementation needs to be supported by plant management; age of instructors; developments of training materials and conducting training at the same time; knowledge and use of the PC; English language skills; social transitioning from the NPP to the TC; motivation; workplace environment and conditions

  13. 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)

  14. NTC operator training program viewed from SAT-based training process

    International Nuclear Information System (INIS)

    Matsumoto, Yoshio

    1996-01-01

    The Nuclear Power Training Center Ltd. (NTC) was established in June 1972 to train PWR plant operators. Operator training was started in Apr. 1974. Presently we have three full-scope, control-room simulators. Recently IAEA recommended that its Systematic Approach to Training (SAT) be used for the training of NPP personnel. We thoroughly examined the SAT-based process and compared it against the NTC training program. As a result, we have recognized that the NTC training program satisfies the SAT-based training process. We now intend to improve the feedback step of the NTC training system. Our efforts continue to produce a relevant program at the forefront of our profession. (author)

  15. Trillo NPP full scope replica simulator project: The last great NPP simulation challenge in Spain

    International Nuclear Information System (INIS)

    Rivero, N.; Abascal, A.

    2006-01-01

    In the year 2000, Trillo NPP (Spanish PWR-KWU design nuclear power plant) and Tecnatom came to the agreement of developing a Trillo plant specific simulator, having as scope all the plant systems operated either from the main control room or from the emergency panels. The simulator operation should be carried out both through a control room replica and graphical user interface, this latter based on plant schematics and softpanels concept. Trillo simulator is to be primarily utilized as a pedagogical tool for the Trillo operational staff training. Because the engineering grade of the mathematical models, it will also have additional uses, such as: - Operation engineering (POE's validation, New Computerized Operator Support Systems Validation, etc).; - Emergency drills; -Plant design modifications assessment. This project has become the largest simulation task Tecnatom has ever undertaken, being structured in three different subprojects, namely: - Simulator manufacture, Simulator acceptance and Training material production. Most relevant technological innovations the project brings are: Highest accuracy in the Nuclear Island models, Advanced Configuration Management System, Open Software architecture, Human machine interface new design, Latest design I/O system and an Instructor Station with extended functionality. The Trillo simulator 'Ready for Training' event is due on September 2003, having started the Factory Acceptance Tests in Autumn 2002. (author)

  16. Radiation ecological monitoring in NPP region

    International Nuclear Information System (INIS)

    Egorov, Yu.A.; Kazakov, S.V.

    1985-01-01

    The known principle of sanitary-hygienic regulation of NPP radiation effect on man and environment is analyzed. An ecological approach is required to optimize NPP relations with the environment and to regulate radioactivity of the NPP - environment system. The ecological approach envisages the development of standards of permissible concentrations of radioactive and chemical substances (as well as heat) in natural environment, taking into account their synergism, corresponding to ecologically permissible response reactions of biota to their effect. The ecological approach also comprises the sanitary-hygienic principle of radiation protection of man. Attention is paid to ecological monitoring in NPP region, comprising consideration of factors, affecting the environment, evaluation of the actual state of the environment, prediction of the environmental state, evaluation of the expected environmental state

  17. Environmental impact of the NPP Krsko

    International Nuclear Information System (INIS)

    Novosel, N.

    1996-01-01

    The Ministry of Economic Affairs has for six years now been monitoring the operation of the Krsko NPP (NEK) and its impact on the environment. A bulletin titled 'NEK - Energy and Environment' is being issued every three months. It contains information on operation of the Krsko NPP for the previous three months, a graph of duration of temperature increase of water in the Sava river (delta T) in that period, an assessment of the radiological impact of Krsko NPP on the environment through an equivalent dose cumulatively throughout the calendar year, and a short current text related to Krsko NPP. The Ministry of Economic Affairs organizes a press conference on every issue of the bulletin, as an attempt of introducing this subject to the media and to the public. This paper contains a review of information given in the NEK bulletin from 1990 to 1995 with a special emphasis on the contribution of the Krsko NPP to the artificially caused radiation on the border between the Republic of croatia and the Republic of Slovenia. (author)

  18. Some thoughts for 'Energia Nucleara'

    International Nuclear Information System (INIS)

    Harris, David S.

    2002-01-01

    This is a report of an interview between the 'Energia Nucleara' reporter and Mr David S. Harris, the AECL project director for Cernavoda NPP Unit 2. The following items were addressed during the interview: the status of the Cernavoda NPP Unit 2 project; the differences in the project between Unit 1 and Unit 2; the Romanian infrastructure and industrial contributions to the Unit 2 project; the cooperation with Romanian design team; the Canadian authorities support to Unit 2 completion; Unit 3 project and AECL possible involvement. Following the Romanian Government's decision to complete Cernavoda Unit 2 in late 2002 work was recommenced in the key areas of engineering, procurement of equipment and materials signing of major supply contracts and construction, such that the total project is now 52% complete. actual construction activities are now 41% complete, and the number of key milestones have recently been achieved, such as: Closure of the Reactor Building 'B' Opening; commencement of rolling in of 45,000 main turbine condenser tubes; commencement of post-tensioning works on the Reactor Building structure and the completion of various infrastructure civil works. Structures and equipment already delivered, and installed or stored are in good conditions and ready for construction continuation. The following changes were implemented in Unit 2 as compared to Unit 1: design changes to meet new regulations and provide increases in the margin of safety; changes due to development of nuclear technology, particularly those improving performance and reliability of operation; design changes to replace equipment affected by obsolescence to allow purchasing of spare parts in the future. Concerning the future, AECL is willing to cooperate with the Romanian SNN on the Unit 3 completion process

  19. The Safety Assessment Education and Training Programme (SAET). Education and Training in the Area of Safety Assessment

    International Nuclear Information System (INIS)

    Mellinger-Deroy, M.

    2014-01-01

    • The SAET Programme provides a systematic approach for training regulatory, operational and technical support staff in the skills needed for informed decision-making and technical review of NPP safety case documentation. • The objective of the Programme is to support the IAEA Member States in developing the knowledge and skills necessary for making the right decisions in NPP design, licensing and operation. (author)

  20. Basis scheme of personnel training system

    International Nuclear Information System (INIS)

    Rerucha, F.; Odehnal, J.

    1998-01-01

    Basic scheme of the training system for NPP personnel of CEZ-EDU personnel training system is described in detail. This includes: specific training both basic and periodic, and professional training meaning specialized and continuous training. The following schemes are shown: licence acquisition and authorisation for PWR-440 Control Room Personnel; upgrade training for job positions of Control Room personnel; maintaining and refresh training; module training for certificate acquisition of servicing shift and operating personnel

  1. 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)

  2. Seismic characterization of the NPP Krsko site

    International Nuclear Information System (INIS)

    Obreza, J.

    2000-01-01

    The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

  3. The development of NPP operational safety training courses

    International Nuclear Information System (INIS)

    Lee, Chang Kun; Lee, Duk Sun; Lee, Byung Sun; Lee, Won Koo; Juhn, Heng Run; Moon, Byung Soo; Cho, Min Sik; Lee, Han Young; Moon, Hak Won; Seo, Yeon Ho

    1987-12-01

    The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

  4. Regulatory evaluation of nuclear power plant on-the-job training programmes

    International Nuclear Information System (INIS)

    Wilkinson, J.

    1996-01-01

    It is now well recognized internationally in the nuclear industry that a Systematic Approach to Training (SAT), as described in IAEA-TECDOC-525, represents the currently most effective method of providing effective, efficient training to Nuclear Power Plant (NPP) personnel. For this reason the Canadian regulator, the Atomic Energy Control Board (AECB), has made SAT a requirement for the training of NPP personnel whose job activities could affect plant or public safety. In this respect the AECB recognizes that the SAT process will dictate on-the-job-training (OJT) and the prudent use of Job Performance Measures (JPMs) as the most effective method of providing parts of the required training to some work groups. The AECB has adopted a process of training program evaluation for NPP operations personnel which comprises methods to evaluate all types of training including OJT. This paper describes some variations which have been identified in the conduct of OJT at Canadian utilities. It then presents the three step process established by the AECB to effectively evaluate training programs expertise is required. The concept of utility self-evaluations is introduced. Finally, the importance of consistency on the part of the regulator in following a systematic approach to evaluation through the application of a viable standard is addressed. (author). 2 figs

  5. Fuel leak testing performance at NPP Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Slugen, V.; Krnac, S.; Smiesko, I.

    1995-01-01

    The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR's. 1 tab., 2 figs., 3 refs

  6. Fuel leak testing performance at NPP Jaslovske Bohunice

    Energy Technology Data Exchange (ETDEWEB)

    Slugen, V; Krnac, S [Slovak Technical Univ., Bratislava (Slovakia); Smiesko, I [Nuclear Powr Plant EBO, Jaslovske Bohuce (Slovakia)

    1996-12-31

    The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR`s. 1 tab., 2 figs., 3 refs.

  7. 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

  8. Use of the deterministic safety analyses in support to the NPP Krsko modification

    International Nuclear Information System (INIS)

    Feretic, D.; Cavlina, N.; Debrecin, N.; Grgic, D.; Bajs, T.; Spalj, S.

    2004-01-01

    The ultimate goal of the safety analysis is to verify that Nuclear Power Plant (NPP) meets safety and operational requirements. To this aim it is necessary to demonstrate that plant safety has not been deteriorated in the case of the modifications to the plant Systems, Structures and Components (SSC) or changes to the plant procedures. In addition, safety analyses are needed in the case of reassessment of an existing plant. The reasons for reassessment may be different, e.g. due to the changes in the methodology and assumptions used in the original design, if the original design basis or acceptance criteria may no longer be adequate, if the safety analysis tools used may have been superseded by more sophisticated methods or if the original design basis may no longer be met. The operation of the NPP Krsko has experienced numerous changes from the original design for the majority of the reasons that have been mentioned before. On the other side, the application of the large best-estimate thermalhydraulic codes has evolved to the wide spread support in the operation of the NPP: compliance with the regulatory goals, support to the PSA studies, analysis of the operational transients, plant modifications studies, equipment qualification, training of the operators, preparation of the operating procedures, etc. This trend has been followed at the Faculty of Electrical Engineering Zagreb (FER) and applied to the on-going needs due to the modifications and changes at NPP Krsko. In this paper, an overview of the deterministic safety analyses performed at FER in the support to the NPP Krsko modifications and changes is presented.(author)

  9. Testing a CANDU-fueling machine at the Institute for Nuclear Research Pitesti

    International Nuclear Information System (INIS)

    Cojocaru, Virgil

    2006-01-01

    In 2003, as a national and European premiere, the Fueling Machine Head no. 4 (F/M) for the Nuclear Power Plant Cernavoda Unit 2 (NPP) was successfully tested at the Institute for Nuclear Research Pitesti (INR). In 2005, the second Fueling Machine (no. 5) has tested for the Nuclear Power Plant Cernavoda Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate the CANDU technology in Romania. To perform the tests of these machines at INR Pitesti, a special testing rig has built being available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing activity. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any CANDU Reactor owner

  10. Krsko NPP Periodic Safety Review program

    International Nuclear Information System (INIS)

    Basic, I.; Spiler, J.; Novsak, M.

    2001-01-01

    The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

  11. Adapting the notion of natural (geological) barrier for final disposal of low- and intermediate-level radioactive wastes in Romania

    International Nuclear Information System (INIS)

    Durdun, I.; Marunteanu, C.; Andrei, V.

    2001-01-01

    According to the Minimum Disturbances Design (MDD) notion by Carl-Olof Morfeldt of Mineconsult, Sweden, any site selection, design and construction of low- and intermediate-level radioactive waste repository should be based on a thorough knowledge of the geological environmental so that the implantation of the disposal facility induce no significant harmful consequences. This work presents the way in which the Romanian program of radioactive waste management was implemented for disposal of low- and intermediate-level radioactive wastes from Cernavoda NPP. Based on geological criteria of selection of lithologic, petrographic, tectonic, seismologic, hydrologic and geo-technic nature, 37 sites were analyzed from which 2 were retained and finally one, Saligny site, was chosen, as the most close to Cernavoda NPP. Also, public acceptance and transport connections were taken into consideration. SUTRA, SWMS-2D and CHAIN-2D codes were applied to analyze the safety and the geological barrier effects. The barrier consists in red clay, a smectitic mineralogic compound. The computation showed that in Saligny vault the maximal tritium extension is kept inside due to the red clay barrier. Geo-technical engineering works were conducted to improve the properties of the loess upper layer which resulted in lowering its sensitivity to moistening and erosion

  12. ALARA and radiation protection optimization status of Cernavoda NPP

    International Nuclear Information System (INIS)

    Hau, D.I.

    2001-01-01

    ALARA (As Low As Reasonably Achievable) in Radiation Protection is specifically applied as a tool in lowering the risk of exposure when performing necessary activities, leading to a reduction of individual and collective doses of workers as much and as reasonable possible. (authors)

  13. Digital control computer upgrade at the Cernavoda NPP simulator

    International Nuclear Information System (INIS)

    Ionescu, T.

    2006-01-01

    The Plant Process Computer equips some Nuclear Power Plants, like CANDU-600, with Centralized Control performed by an assembly of two computers known as Digital Control Computers (DCC) and working in parallel for safely driving of the plan at steady state and during normal maneuvers but also during abnormal transients when the plant is automatically steered to a safe state. The Centralized Control means both hardware and software with obligatory presence in the frame of the Full Scope Simulator and subject to changing its configuration with specific requirements during the plant and simulator life and covered by this subsection

  14. Cernavoda NPP - A competitive energy source for sustainable development

    International Nuclear Information System (INIS)

    Rotaru, Ioan; Bilegan, I.C.; Jelev, Adrian

    2004-01-01

    At present a trend manifests world wide toward promoting nuclear power, for increasing its performances, toward maintaining competitiveness and sustaining the programs of development and application of advanced nuclear technologies. These objectives will be achieved by improving: operation performances; management of life-cycle, quality management; technical infrastructure; human resource performances; international cooperation for developing innovative nuclear technologies; technologies and applications of advanced reactors. Fostering the Romanian nuclear power on the basis of CANDU 6 type rectors, the developing in Romania of an advanced industrial infrastructure, the economical, environmental and social aspects and their interplay with nuclear power development are the main subjects presented in this work

  15. Financial and organizational models of NPP construction projects

    International Nuclear Information System (INIS)

    Ivanov, Timur

    2010-01-01

    The recent evolution of financial and organizational models of NPP projects can be truly reputed to open a new page of the world market of NPP construction. The definition of the concrete model is based mostly on specific cooperation backgrounds and current terms and conditions under which the particular NPP project is being evolved. In this article the most commonly known strategies and schemes of financing structuring for export NPP construction projects are scrutinized. Special attention is paid to the analysis of BOO/BOT models which are based on the public-private partnership. Most BOO/BOT projects in the power sector has Power Purchase Agreements (PPA) as an integral part of them. The PPA key principles are studied here as well. The flexibility and adaptability of the public-private partnership models for financing and organization of the NPP projects contributes substantially to the competitiveness of the NPP projects especially under current economic conditions. (orig.)

  16. External flood probabilistic safety analysis of a coastal NPP

    International Nuclear Information System (INIS)

    Pisharady, Ajai S.; Chakraborty, M.K.; Acharya, Sourav; Roshan, A.D.; Bishnoi, L.R.

    2015-01-01

    External events pose a definitive challenge to safety of NPP, solely due to their ability to induce common cause failures. Flooding incidents at Le Blayais NPP, France, Fort Calhoun NPP, USA and Fukushima Daiichi have pointed to the importance of external flooding as an important contributor to NPP risk. A methodology developed for external flood PSA of a coastal NPP vulnerable to flooding due to tsunami, cyclonic storm and intense local precipitation is presented in this paper. Different tasks for EFPSA has been identified along with general approach for completing each task

  17. 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

  18. Predisposal of Radioactive Waste from NPP 1000 MWe

    International Nuclear Information System (INIS)

    Suryantoro

    2007-01-01

    Predisposal of radioactive waste from NPP 1000 MW which was planned to be operated in 2016 has been conducted. In this study NPP applying PWR type was assumed. This assessment comprises all aspects of radioactive waste coming from NPP. One through cycle was chosen consequently no reprocessing step will be conducted. The assessment shows that technologically all radioactive waste treatment process rising from NPP operation has similarities to the existing radioactive waste process conducted by RWI which has lower scale of waste amount. (author)

  19. Treatment of NPP wastes using vitrification

    International Nuclear Information System (INIS)

    Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

    1998-01-01

    Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10 -5 -10 -6 g/(cm 2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

  20. NPP electrical price and tariff in the world

    International Nuclear Information System (INIS)

    Mochamad Nasrullah and Sriyana

    2010-01-01

    Construction of a Nuclear Power Plant (NPP) is always become a controversial issue. Nuclear utility and other party which support the NPP present a calculation of NPP electricity cost too optimistic. However for utility and other party that contra to nuclear present a calculation of NPP electricity cost too pessimistic. This study present to reduce the controversy of nuclear cost. In this study, capital cost (Engineering Procurement Construction, EPC) was taken from Asian, America and Europe, operating and maintenance cost uses experience data of PLN, and nuclear fuel cost uses data year of 2008 with high price, low price and average price scenario. The methodological tools used to compare electricity generation cost was LEGECOST, a program developed by IAEA (International Atomic Energy Agency), while for electricity tariff- price calculation using a program developed by PLN research and development center. With the discount rate 10%, the result shows that the cheapest electricity generation cost of NPP is less than 40 mills/kWh, and average electricity tariff was 55 mills/kWh. In the Europe countries the electricity tariff more expensive than NPP in Asia. However generating cost and electricity tariff of NPP in United Stated of America (USA) less competitive because investment cost more expensive. Generating cost and electricity tariff was different at each country depend on salary, labor wage, materials price, construction specification, regulation related to NPP and environment aspect. (author)

  1. 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

  2. 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)

  3. 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

  4. Probabilistic assessment of NPP safety under aircraft impact

    International Nuclear Information System (INIS)

    Birbraer, A.N.; Roleder, A.J.; Arhipov, S.B.

    1999-01-01

    Methodology of probabilistic assessment of NPP safety under aircraft impact is described below. The assessment is made taking into account not only the fact of aircraft fall onto the NPP building, but another casual parameters too, namely an aircraft class, velocity and mass, as well as point and angle of its impact with the building structure. This analysis can permit to justify the decrease of the required structure strength and dynamic loads on the NPP equipment. It can also be especially useful when assessing the safety of existing NPP. (author)

  5. RIAR training center, Dimitrovgrad, Russia

    International Nuclear Information System (INIS)

    Makin, R.

    1998-01-01

    The presentation describes activities and history of the training Center for NPP personnel at the Research Institute of Atomic Reactors (RIAR) in Dimitrovgrad, Russian Federation since its beginnings in 1993. The courses held for training instructors and specialists as well as Russian NPPs were organised in cooperation with American and German organisations

  6. NPP Bohunice experience with ASSET services

    Energy Technology Data Exchange (ETDEWEB)

    Klimo, J [Bohunice NPP (Slovakia)

    1997-12-31

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author).

  7. NPP Bohunice experience with ASSET services

    International Nuclear Information System (INIS)

    Klimo, J.

    1996-01-01

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author)

  8. The Preparation of regulatory resources to control the NPP in Indonesia

    International Nuclear Information System (INIS)

    Aris Sanyoto; Eko Legowo

    2012-01-01

    There are many responses of public in line with the planning to develop nuclear power plant (NPP) in Indonesia; one of them is rejecting it. One of the reasons is worry on the resources as well as the competency of human resources who will operate it. To overcome this situation, therefore it is necessary presence of regulatory authority with capabilities to ensure all requirements to operate the NPP safety and securely. According to the IAEA Safety Guide No GS-G-1.1, in order to have capabilities as regulatory authority, BAPETEN shall have independence resources covering some aspects, such as political, legislative, financial, public information, international, and competency. The independence from the political aspects can be observed from the Act number 10 Year on Nuclear energy, where BAPETEN's organization is directly responsible to President of Republic of Indonesia, meanwhile the independence from legislative aspect where some function such as regulation and guide development, review and assessment , licensing, inspection, research & development, emergency response preparedness and international communication has been covered in its organization structure. Moreover, in order to do its function appropriately BAPETEN shall own technical expertise as recommended by IAEA Tecdoc 1254. Identification of training syllabus, most of the competency has been addressed in the BAPETEN's training program. However, to assess the competency level of every BAPETEN's personnel, especially those 262 with technical education background, it is necessary to do a training need assessment (TNA) process. The result of the process will figure out the gap between the required and existing competency. (author)

  9. Akkuyu NPP – the first Turkish NPP. The new history of the project

    International Nuclear Information System (INIS)

    Tzocheva, V.

    2012-01-01

    An overview is given to the Turkish energy sector and nuclear power plans. The project for the construction of the first NPP in Turkey is presented. The general parameters of the Project are: CAPEX: $ 20 bln; Project design: NPP-2006; (VVER- 1200); Number of units: 4; Total capacity: 4 800 MW; Construction period: 2014 – 2023; PPA period; 15 years, fixed price terms. An account of the activities during 2011, the Worley Parsons participation are presented and a tentative project schedule is given

  10. Inspection Qualification Centre in NPP 'Kozloduy'

    International Nuclear Information System (INIS)

    Mikhovski, M.

    2000-01-01

    In May 1999 according to the working plan of the IAEA project RER 4/020 and the decision of the NPP the Inspection Qualification Centre (IQC) has been established in order to provide examination services in the NPP. During year 1999 IVC (AEA Technology) in the framework of the DTI project provides consulting and technical assistance to the NPP, IQC, Bulgarian Academy of Sciences and Regulatory Authorities in setting up the IQC infrastructure. Now IQC work as an independent inspection body B type. The IQC activities for the period 1999-2000 are presented and further tasks are outlined

  11. Metamorphosis of NPP A1, V1, V2

    International Nuclear Information System (INIS)

    Dobak, D.; Moncekova, M.

    2005-01-01

    In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

  12. NPP A-1 decommissioning - Phase I

    International Nuclear Information System (INIS)

    Krstenik, A.; Blazek, J.

    2000-01-01

    Nuclear power plant A-1 with output 150 MW e , with metallic natural uranium fuelled, CO 2 cooled and heavy water moderated reactor had been prematurely finally shut down in 1977. It is necessary to mention that neither operator nor regulatory and other authorities have been prepared for the solution of such situation. During next two consecutive years after shutdown main effort of operator focused on technical and administrative activities which are described in the previous paper together with approach, condition and constraints for NPP A-1 decommissioning as well as the work and research carried out up to the development and approval of the Project for NPP A-1 decommissioning - I. phase. Subject of this paper is description of: (1) An approach to NPP A -1 decommissioning; (2) An approach to development of the project for NPP A-1 decommissioning; (3) Project - tasks, scope, objectives; (4) Mode of the Project realisation; (5) Progress achieved up to the 1999 year. (authors)

  13. ALARA radiation protection applications at NPP A1 decommissioning using VISPLAN planning tool

    International Nuclear Information System (INIS)

    Slavik, O.; Kucharova, D.; Listjak, M.

    2005-01-01

    The SCK.CEN developed during the BR3 reactor decommissioning a graphical interfaced 3D dose assessment tool aimed at the above mentioned dose optimization problems. The tool was improved further and commercialized under the name VISIPLAN 3D ALARA planning tool. The use of VISIPLAN tool at NPP A1 decommissioning was advised by EDF within the IAEA TCP SLR/4008 project missions as a component of a 3D technological chain ensuring acquisition and evaluation of digitized information leading to ALARA optimisation of the developed decommissioning working procedures (see Fig. 1). VISIPLAN license was purchased by IAEA and granted to VUJE and NPP A1 within the IAEA TCP project SLR/4008, covering also the necessary basic and advanced training (at NPP A1 real decommissioning environment), and is currently used by VUJE analysts at NPP A1 decommissioning as an ALARA tool for intervention planning and optimisation. The VISIPLAN allows a fast dose assessment for work planned in a radioactive environment. The calculations are based on a 3D model of the work place. This PC-based tool is user friendly and calculates a detailed dose account for different work scenarios defined by the ALARA analyst, taking into account worker position, work duration and subsequent geometry and source distribution changes. The VISIPLAN methodology is described. The VISIPLAN tool was applied to several ALARA studies carried out by the VUJE within development and analysis of various Work Programs for NPP Al decommissioning tasks. The applications ranged from simpler to complex ALARA planning tasks covering simple shielding applications to selection of the most suitable order of complex working procedures. Removal of inner liners from underground reservoirs 6/1 and 6/2 as well as Dismantling of pipes and components from a (hostile) 60 m corridor are described. (authors)

  14. Monitoring program of surrounding of the NPP SE-EBO

    International Nuclear Information System (INIS)

    Dobis, L.; Kostial, J.

    1997-01-01

    The paper dealt with monitoring program of radiation control of surrounding of the NPP Bohunice, which has the aim: (1) to ensure the control of influence of work of the NPP Bohunice on the environment in their surrounding; (2) to ensure the back-ground for regular brief of control and supervisory organs about condition of the environment in surrounding of the NPP Bohunice; (3) to maintain the expected technical level of control of the NPP Bohunice and to exploit optimally the technical means; (4) to solicit permanently the data about the radioactivity of environment in surrounding of the NPP Bohunice for forming of files of the data; (5) to exploit purposefully the technical equipment, technical workers and to maintain their in permanent emergency and technical eligibility for the case of the breakdown; (6) to obtain permanently the files of the values for qualification of the reference levels. This program of monitoring includes the radiation control of surrounding of the NPP Bohunice, in the time of normal work of power-station's blocks, inclusively of all types of trouble-shooting and repairer works in surrounding of the NPP Bohunice, up to distance 20 km from power-station. The monitoring includes: outlets from the NPP Bohunice, monitoring of radiation characteristics in surrounding of the NPP Bohunice, (aerosols, fall-outs, soil), the links of food chains: (grass and fodder, milk, agriculture products), hydrosphere in surrounding (surface waters, drink water, bores of radiation control in complex of the NPP Bohunice, components of the hydrosphere), measurement of radiation from external sources (measurement of the dose rates, measurement of the doses [sk

  15. Sociological investigations on Ignalina NPP and within its surroundings

    International Nuclear Information System (INIS)

    Chiuzhas, A.

    1998-01-01

    The purpose of this study was to determine the impact of Ignalina NPP and Visaginas town on the social territorial processes in the region and to reveal the impact of Ignalina NPP on the regional economic, social, demographic, political and cultural processes in the context of ecological and psychological affect. According to the results of this research three quarters of the inhabitants and the functionaries of local administration hold an opinion that operation of Ignalina NPP posses threat for the population and environment. Meanwhile they are sure that danger of Ignalina NPP is not critical. 21 - 35 % of the local administrators speak for the closure of Ignalina NPP , whereas half of Visaginas residents and three quarters of the local administrators indicate that operation of reactors is expedient. Over 90% of the population do not have sufficient information on the operation of Ignalina NPP. In the opinion of the rest Lithuanian people Ignalina NPP zone is related with the physical danger and the image of Visaginas residents as the 'others', 'strangers'. More than 90% of Ignalina NPP employees are Russian speaking, not native Lithuanians. The social relations of Visaginas with the environment are poor as a result of the situation of the town, lack of communications and cultural self isolation. (author)

  16. Comparison of HRA methods based on WWER-1000 NPP real and simulated accident scenarios

    International Nuclear Information System (INIS)

    Petkov, Gueorgui

    2010-01-01

    Full text: Adequate treatment of human interactions in probabilistic safety analysis (PSA) studies is a key to the understanding of accident sequences and their relative importance in overall risk. Human interactions with machines have long been recognized as important contributors to the safe operation of nuclear power plants (NPP). Human interactions affect the ordering of dominant accident sequences and hence have a significant effect on the risk of NPP. By virtue of the ability to combine the treatment of both human and hardware reliability in real accidents, NPP fullscope, multifunctional and computer-based simulators provide a unique way of developing an understanding of the importance of specific human actions for overall plant safety. Context dependent human reliability assessment (HRA) models, such as the holistic decision tree (HDT) and performance evaluation of teamwork (PET) methods, are the so-called second generation HRA techniques. The HDT model has been used for a number of PSA studies. The PET method reflects promising prospects for dealing with dynamic aspects of human performance. The paper presents a comparison of the two HRA techniques for calculation of post-accident human error probability in the PSA. The real and simulated event training scenario 'turbine's stop after loss of feedwater' based on standard PSA model assumptions is designed for WWER-1000 computer simulator and their detailed boundary conditions are described and analyzed. The error probability of post-accident individual actions will be calculated by means of each investigated technique based on student's computer simulator training archives

  17. 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)

  18. The German simulator center for the training of nuclear power plant operators

    International Nuclear Information System (INIS)

    Hoffmann, E.

    1996-01-01

    Simulator training for nuclear power plant operators in Germany is conducted in The Simulator Center in Essen. The companies operating The Center are KSG/GfS. KSG provides simulators, GfS performs the training. The German Simulator Center is equipped with five simulators in training, nine simulators are under construction and will be ready for training until the beginning of 1997. This institution serves 22 nuclear power plants units in Germany, Switzerland (NPP Goesgen-Daeniken) and the Netherlands (NPP Borssele) and trains 1,800 persons every year. As a common enterprise the company is owned by 12 utilities, which leads to the necessity to prepare common rules and guidelines for simulator specification, training of instructors, assessment of trainees, training material and preparation and methodical running of simulator courses

  19. Improvement of the Nuclear Radiation Protection Training for the Simulator and on sharing method of the Safety Parameter with the Emergency Organization

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sungjin; Park, Daeseung [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Radiation Emergency alert will be announced when the radiological impact is limited within the NPP or radiological impact to go out of the NPP. Radiation Protection Training is scheduled and proceeded to prevent for the radiation accidents, possibility of the radiation accidents, or radiation accident expansion, the training is to reduce the damage to property and health for the nuclear power plant worker and the people near the nuclear power plant. This paper shows the improvement of the nuclear radiation protection training for the simulator and on sharing method of the safety parameter with the emergency organization. Accident shall be correctly and quickly prevented when the NPP accident is inevitable. Therefore the radiation protection training for the operator and the emergency organization will be effective when the accident happens if the simulator has the same environment as the NPP.

  20. Principles of tariff determination for NPP electric power generation

    International Nuclear Information System (INIS)

    Ratnikov, B.E.; Gitel'man, L.D.; Artemov, Yu.N.; Fiantsev, V.S.

    1988-01-01

    Foundations of price-setting and order of accounting arrangement for NPP electric power are considered. NPP tariffs are established proceeding from standard costs of power generation. The standards are differentiated as to NPP groups, depending on technical, regional and natural geographic factors, taking into account the facility type, unit capacity and the number of similar NPP units. The conclusion is made that under conditions of NPP economic independence expansion and creation of prerequisites for going over to self-financing principles and also due to the qualitatively new stage of nuclear power generation development the level of efficiency, forseen by the tariffs, should be increased

  1. 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

  2. Why should nuclear power plant management support the systematic approach to training?

    International Nuclear Information System (INIS)

    Haber, S.B.; Yoder, J.A.

    1998-01-01

    The presentation shows the role of management in training of NPP personnel especially in training for technology transfer and training for transfer of the training capabilities. Systematic approach to training should be used to achieve standard among different industries; consistent, effective and efficient training

  3. Organization of monitoring of agricultural products in NPP region

    International Nuclear Information System (INIS)

    Panteleev, L.I.; Spirin, E.V.; Sanzharova, N.I.

    1990-01-01

    Problem of organizing chemical and radiation monitoring of agricultural products in NPP region is considered. Attention is paid to monitoring during NPP siting and designing, to monitoring of radioactive contamination of agricultural products under normal NPP operation, emergency situations and decommissioning

  4. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    International Nuclear Information System (INIS)

    Haas, P.M.; Selby, D.L.; Hanley, M.J.; Mercer, R.T.

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model

  5. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    Energy Technology Data Exchange (ETDEWEB)

    Haas, P M; Selby, D L; Hanley, M J; Mercer, R T

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model.

  6. 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.)

  7. Study on human factor at NPP

    International Nuclear Information System (INIS)

    Nopp, I.

    1984-01-01

    Factors affecting the reliabilty of the reactor control by an NPP operator are considered on the base of the Czechoslovakia NPP operating experience. The reliability level of NPP operators depends on objective factors (conditions and regime of labour) determining the labour productivity and on subjective ones (psychological morale, physical and mental abilities and occupational level of personnel). Problems of the effect of physical and mental abilities and professional level on the reliability of personnel are considered to be the most important ones. The effect of individual abilities and specific features of the human body on changes in his occupational abilities can be estimated only to a certain degree

  8. Romania, producer and consumer of nuclear fuel

    International Nuclear Information System (INIS)

    Iuhas, Tiberius

    1998-01-01

    A historical sketch of the activity of Romanian Rare Metals Enterprises is presented stressing the valorization of rare metals like: - radioactive metals, uranium and thorium; - dispersed rare metals, molybdenum, monazite; - heavy and refractory metals, titanium and zirconium; rare earths, lanthanides and yttrics. The beginning and developing of research in the nuclear field is in closed relation to the existence on the domestic territory of important uranium ores the mining of which begun early in 1954. The exploitation of Baita-Bihor orebody was followed by that at Ciudanovita, Natra and Dobrei ores in Caras-Severin county. Concomitantly with the ore mining, geological research was developed covering vast areas of country's surface and using advanced investigation tools suitable for increasing depths. The next step in the nuclear fuel program was made by building a uranium concentrate (as ammonium or sodium diuranate) plant. Two purification units for processing the uranium concentrate to sintered uranium dioxide powder were completed and commissioned at Feldioara in 1986. The quality of the uranium dioxide product meets the quality standards requirements for CANDU type nuclear fuel as certified in 1994. Currently, part of the fuel load of Cernavoda reactor is fuel element clusters produced by Nuclear Fuel Plant at Pitesti of sintered powder processed at Feldioara. A list of strategic objectives of the Uranium National Company is presented among which: - maintaining the uranium mining and milling activities in close relation with the fuel requirements of Cernavoda NPP; continuing geological research in promising zones, to find new uranium orebodies, easy to mill cost effectively; decreasing the environmental impact in the geological research areas, in mining and transport affected areas and in the processing plants. The fuel demand of current operation of Cernavoda NPP Unit 1 as well as of future Unit 2 after commissioning are and will be satisfied by the

  9. Condition Monitoring of Sensors in a NPP Using Optimized PCA

    Directory of Open Access Journals (Sweden)

    Wei Li

    2018-01-01

    Full Text Available An optimized principal component analysis (PCA framework is proposed to implement condition monitoring for sensors in a nuclear power plant (NPP in this paper. Compared with the common PCA method in previous research, the PCA method in this paper is optimized at different modeling procedures, including data preprocessing stage, modeling parameter selection stage, and fault detection and isolation stage. Then, the model’s performance is greatly improved through these optimizations. Finally, sensor measurements from a real NPP are used to train the optimized PCA model in order to guarantee the credibility and reliability of the simulation results. Meanwhile, artificial faults are sequentially imposed to sensor measurements to estimate the fault detection and isolation ability of the proposed PCA model. Simulation results show that the optimized PCA model is capable of detecting and isolating the sensors regardless of whether they exhibit major or small failures. Meanwhile, the quantitative evaluation results also indicate that better performance can be obtained in the optimized PCA method compared with the common PCA method.

  10. IAEA world survey on nuclear power plant personnel training

    International Nuclear Information System (INIS)

    1999-01-01

    Training of personnel is acknowledged to be essential for safe and reliable operation of nuclear power plants. The preparation of this TECDOC was recommended by the IAEA International Working group on Nuclear Power Plant Personnel Training and Qualification and represents a unique compilation of information including all aspects of NPP personnel training from 23 Member States and 129 training organizations. The basic aims of this survey are: to provide a worldwide overview of all aspects of NPP personnel training; to foster both national and international cooperation between organizations involved in nuclear training; to provide the means of exchange of experiences and practices in systematic approach to training (SAT). The survey provides information for each corresponding country on the: national system and organization of training; job positions for which SAT is used; training programmes for key operations, maintenance, instructor and other jobs; role of management and the regulatory body; training facilities; recommended training practices; availability of training personnel from organizations outside the country; and contact points. The three main parts of the publication are the summary, the analysis of training programmes for each job position and the analysis of training resources, and the country reports

  11. Training and Public Information Activities of the Milan Copic Nuclear Training Centre

    International Nuclear Information System (INIS)

    Jencic, I.

    2006-01-01

    The mission of the Milan Copic Nuclear Training Centre is training in the field of nuclear technologies and radioactivity. In addition we are actively informing general public about those technologies. Activities can be divided into four areas: training in the area of nuclear technologies, radiological protection training, organization of international training courses and public information. Training in the area of nuclear technologies is the primary mission. Two types of courses are regularly offered: The Theory of nuclear technology is the initial training of future control room operators, and the Basics of nuclear technology is intended for non-control room personnel of Krsko NPP and for staff of some other organizations. Each year there are also some specific courses in this area, mainly for the regulatory body and for the NPP. Jozef Stefan Institute is one of the two institutions in Slovenia, authorized for radiological protection training and the training centre is the actual performer. About 15 courses yearly are organized for people from medicine, industry and science courses about open, closed and industrial sources of ionizing radiation. We are also responsible for the training of NPP Krsko personnel in that area. Organization of international courses is a usually a collaboration with the International Atomic Energy Agency (IAEA), but we have worked also with other international organizations, such as European Commission, US Department of Energy etc. The topics of international courses and workshops cover a wide range from nuclear safety to radiological protection or illegal trafficking of nuclear materials etc. Depending on the subject, part of lectures on these courses is given by domestic experts. 6 - 10 international courses are organized yearly. Very important is the area of public information. Groups of school children and other visitors are coming regularly to listen to a lecture and to visit the exhibition. In 2005, both the lecture and the

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. Project No. 10 - Partial restoration of Ignalina NPP territory

    International Nuclear Information System (INIS)

    2000-01-01

    At present Ignalina NPP territory makes a total of 2544 ha of land. Due to termination of construction activity development and due to the decision taken to shutdown unit 1 the need in such a territory fell off. For normal and safe operation of Ignalina NPP 1440 ha is enough, including 1237 ha for of Ignalina NPP administrative area and 203 ha for auxiliary objects. Ignalina NPP will have to rearrange territory, forestry that was damaged during the construction activities of the plant and to restore the damaged farmlands and to pass the rearranged forestry that belonged to the Ignalina NPP to the Ministry of Forestry. The total estimated cost of the project is about 1.042 M EURO

  17. Main principles of NPP project ecological expert investigation

    International Nuclear Information System (INIS)

    Dibobes, I.K.; Revina, S.K.; Glushkov, V.P.

    1983-01-01

    NPP project ecological expert investigation among the other objectives is to provide implementation of standards, rules and requirements as well as government decrees and international obligations of the USSR concerning the environment protection. The expert investigation takes into consideration both environment protection, regional, resources, ecological, demographic and economic aspects. The NPP siting and the local environment and resources state are estimated as well as the structure of utilization of the latter, the expected damage to the environment due to NPP construction and the measures directed towards the optimal using of natural resources. On the basis of the presented issues suggestions about NPP projects coordination with Goskomgidromet's institutions are given [ru

  18. Cernavoda NPP Unit 1: Operating experience program and plant specific performance indicators (level 2)

    International Nuclear Information System (INIS)

    Teodor, Vasile; Popa, Viorel

    1998-01-01

    The basis for the Operating Experience Program was set in place since early stages of the commissioning phase (1993), when a system based on the Canadian approach was implemented for reporting, reviewing, assessing and establishing of the necessary corrective action for unplanned events. This system provided excellent opportunity to train staff in unplanned event assessment methodology, and prepare the station for the formal reporting process following criticality in accordance with the licensing requirements. The formal process, set in place after criticality is described in Station Instruction Procedure SI-01365-P13 'Unplanned Event Report' and was developed under the supervision of Safety and Compliance Department. In parallel, a program for information exchange and trending of performance indicators was developed by Technical Services Department. The WANO recommendations following August 1997 Peer Review provided the opportunity for a better understanding and reconsideration of the Operating Experience Program. As a result, all the activities related to this topic were assigned to a new structure, within Safety and Compliance Department. As such an Operating Experience Group was created and a new program is now being developed in an integrated and centralized manner. The content of the paper is the following: - Overview; - Operating Experience Program; - Event Analysis (Unplanned Events Assessment System - UEIR Process- and Systematic Analysis of Operational Events - ACR Process); - Information Exchange Program; - Monitoring of Operating Experience - Plant Specific Performance Indicators; - Purpose; - Level 2 Performance Indicators. Four appendices are added containing: - A. Station performance indicators/targets (Level 2); - B. SPI (Station Performance Indicators - Level 2) - Graphics; - C. UEIR, LRS (Safety and Licensing Review Sheet), UEFR (Unplanned Event Follow-up Report), ACR and OPEX forms. (authors)

  19. 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

  20. Automatic control system at the ''Loviisa'' NPP

    International Nuclear Information System (INIS)

    Kukhtevich, I.V.; Mal'tsev, B.K.; Sergievskaya, E.N.

    1980-01-01

    Automatic control system of the Loviisa-1 NPP (Finland) is described. According to operation conditions of Finland power system the Loviisa-1 NPP must operate in the mode of week and day control of loading schedule and participate in current control of power system frequency and capacity. With provision for these requirements NPP is equipped with the all-regime system for automatic control functioning during reactor start-up, shut-down, in normal and transient regimes and in emergency situations. The automatic control system includes: a data subsystem, an automatic control subsystem, a discrete control subsystem including remote, a subsystem for reactor control and protection and overall station system of protections: control and dosimetry inside the reactor. Structures of a data-computer complex, discrete control subsystems, reactor control and protection systems, neutron flux control system, inside-reactor control system, station protection system and system for control of fuel element tightness are presented in short. Two-year experience of the NPP operation confirmed advisability of the chosen volume of automatization. The Loviisa-1 NPP operates successfully in the mode of the week and day control of supervisor schedule and current control of frequency (short-term control)

  1. 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)

  2. Bohunice V1 NPP upgrading programme

    International Nuclear Information System (INIS)

    Kerak, J.

    2001-01-01

    The paper describes whole process of Bohunice V1 NPP nuclear safety and operational reliability level increase which has been performed since units commissioning (1. unit in 1978, 2. unit in 1980), continued Small Reconstruction (1991 -1993) and finished Gradual Upgrading(1994 -2000). The main purpose is to last stage -Gradual upgrading of Bohunice V1 NPP. (author)

  3. 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

  4. 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)

  5. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    MA ZeQing; LIU QiJing; WANG HuiMin; LI XuanRan; ZENG HuiQing; XU WenJia

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models,we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station,Chinese Academy of Sciences in subtropical China. In addition,canopy layer and community NPP were calculated based on 12 years' litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005,average NPP and GPP values based on BGC simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP,while NEP accounted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respiration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  6. Investigation of interfacing NPP simulators with PSCAD software

    International Nuclear Information System (INIS)

    Zahedi, P.

    2006-01-01

    This paper demonstrates a new method of interfacing a NPP simulator with the PSCAD software so that the interaction between the plant dynamics and the grid dynamics can be studied. Through this method, data extracted from NPP simulator, as an object, will be communicated to a server running PSCAD software. This paper will illustrate the use of Remote Procedure Calls (RPC) as a distributed, client-server based application used to establish a connection between NPP simulator running on UNIX server and PSCAD running on a PC. Using this method, the called procedure need not exist in the same address space as the calling procedure. Communication protocols available in the NPP simulator are used to export data from the simulator. (author)

  7. ATUCHA I NPP - Emergency drill practice

    International Nuclear Information System (INIS)

    Sanda, Alejandro; Rosales, Gabriel

    2008-01-01

    Full text: Atucha I NPP performs an Emergency Drill Practice once a year. Its main goals are: -) Fulfill the requirements of the Argentine Nuclear Regulatory Authority (ARN) regarding Atucha I NPP's Operating License; -) Fulfill the commitment with the community regarding the safe and reliable operation Atucha I NPP; -) Verify the response of the Civil Organizations, Security Forces, and Armed Forces, as well as the correct application of the Emergency Plan; -) Perform the 'General Alarm Drill' periodic control; -) Perform a re-training of the members of the Security Advisor Internal Committee (CIAS) on the Internal and External Aspects of the Emergency Plan and on the related procedures; -) Test the Emergency Communications System. New goals are added every year, considering the Drill's scope. This drill comprises two different kinds of practices: Internal practices (practices in the station, with our personnel) and external practices (practices outside the station with governmental organizations). Internal practices comprise: -) Internal and external communications practices; -) Acoustic alarms; -) Personnel gathering in the Meeting Points; -) Safety of selected Meeting Points; -) Personnel count, selective evacuation; -) Iodide Potassium pills distribution; -) CICE (Internal Group for Emergency Control) Coordination. External practices comprise: -) Nuclear Regulatory Authority; -) Argentine Navy, Comando Area Naval Fluvial, Base Naval Zarate; -) Lima firemen; -) Zarate firemen; -) Municipal Civil Defense (Zarate and Lima); -) National Guard, Escuadron Atucha; -) Zarate Regional Hospital; -) Lima Police Department; -) Zarate Police Department; -) Argentine Coast Guard, Zarate; -) Local radios: Radio FM Libre, FM El Sitio; -) First Aid clinic. The following activities are performed together with the aforementioned organizations: -) Formation of an 'Operative committee'; -) Evacuation of citizens in a 3 km radio; -) Control of every access to Lima; -) Control of

  8. Licensing of the Ignalina NPP

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    Since 1991 State Nuclear Power Safety Inspectorate (VATESI) has regulated Ignalina NPP operation by issuing annual operating permits. Those have been issued following submission of specified documents by the Ignalina NPP that have been reviewed by VATESI. However, according to to the procedures that are now established in the Law on Nuclear Energy and subordinate regulations the use of nuclear energy in the Republic of Lithuania is subject to strict licensing. Therefore a decision about the licence for continued operation of unit 1 should be taken. Licence would be granted by VATESI in cooperation with the Ministry of Health, Ministry of Environment and the institutions of local authorities. Ignalina NPP presented to the VATESI safety analysis report (SAR) with other documents. SAR was made mainly by foreign experts and financed by European Bank for Reconstruction and Development (EBRD). VATESI in this process is supported by western regulators. A special project LAP - Licensing Assistance Project was launched to help VATESI perform licensing according western practices

  9. Safety Analysis Report for Ignalina NPP

    International Nuclear Information System (INIS)

    Negrivoda, G.

    1997-01-01

    In December 1994 an agreement was signed between the European Bank for Reconstruction and Development and the Republic of Lithuania for the grant of 32.86 MECU for the safety Improvement at Ignalina NPP. One of the conditions for the provision of the grant, was a requirement for an in-depth analysis of the safety level at Ignalina NPP in the scope and according to the standards acceptable for a western nuclear power plant, and to publish a Safety Analysis Report (SAR). The report should investigate and analyze any factor that could limit a safe operation of the plant, and provide recommendations for actual safety improvements. According to the agreement, Lithuania had to finalize the SAR until 31 December, 1995. The bank has also organized and financed investigation of safety at Ignalina NPP and preparation of the SAR. EBRD made an agreement with Sweden's Vattenfall, which subcontracted well-known companies from Canada, USA, Germany, etc., and also the Russian Research and Development Institute of Power Engineering (NIKIET), reactor designer of Ignalina NPP. The SAR is a very comprehensive document and contains about 8000 pages of text, diagrams and tables. The main findings of the SAR are provided in the article. A large number of discrepancies with modern rules and western practices was detected, but they were not proved to be serious enough to require reactors shutdown. Based on the recommendations of the SAR Ignalina NPP has worked out Safety Improvement Program No. 2 (SIP-2), which is planned for three years and will cost 486 MLT. (author)

  10. Enhanced backpropagation training algorithm for transient event identification

    International Nuclear Information System (INIS)

    Vitela, J.; Reifman, J.

    1993-01-01

    We present an enhanced backpropagation (BP) algorithm for training feedforward neural networks that avoids the undesirable premature saturation of the network output nodes and accelerates the training process even in cases where premature saturation is not present. When the standard BP algorithm is applied to train patterns of nuclear power plant (NPP) transients, the network output nodes often become prematurely saturated causing the already slow rate of convergence of the algorithm to become even slower. When premature saturation occurs, the gradient of the prediction error becomes very small, although the prediction error itself is still large, yielding negligible weight updates and hence no significant decrease in the prediction error until the eventual recovery of the output nodes from saturation. By defining the onset of premature saturation and systematically modifying the gradient of the prediction error at saturation, we developed an enhanced BP algorithm that is compared with the standard BP algorithm in training a network to identify NPP transients

  11. Research on the NPP human factors engineering operating experience review

    International Nuclear Information System (INIS)

    Ren Xiangchen; Miao Hongxing; Ning Zhonghe

    2006-01-01

    This paper addresses the importance of the human factors engineering (HFE) for the design of nuclear power plant (NPP), especially for the design of human-machine interface in the NPP. It also summarizes the scope and content of the NPP HFE. The function, scope, content and process of the NPP human factors engineering operating experience review (OER) are mainly focused on, and significantly discussed. Finally, it briefly introduces the situation of the studies on the OER in China. (authors)

  12. Reserves of labour content reduction in NPP construction

    International Nuclear Information System (INIS)

    Bekerman, R.E.

    1986-01-01

    Specific labour contents when constructing NPP with RBMK-1000 and WWER-1000 type reactors are presented. Factors affecting labour content of NPP construction are shown. Measures aimed at labour content decrease are suggested

  13. 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

  14. 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)

  15. Training and qualification of NPP personnel in Romania

    International Nuclear Information System (INIS)

    Casota, M.V. I.

    1993-01-01

    Romanian nuclear program is completed with a nuclear fuel manufacturing plant, heavy water production plant and major organizations for engineering, manufacturing and erection of systems and components. Systematic Approach to Training, recommended by IAEA-TECDOC-525, has been started to gradually incorporate the current available training programs. 12 figs

  16. Overview of research potential of Institute for Nuclear Research

    International Nuclear Information System (INIS)

    Ciocanescu, Marin

    2007-01-01

    The main organizations involved in nuclear power production in Romania, under supervision of Presidency, Prime Minister and Parliament are: CNCAN (National Commission for Nuclear Activities Control), Nuclear Agency, Ministry of Economy and Commerce, ANDRAD (Waste Management Agency), SNN (Nuclearelectrica National Society), RAAN (Romanian Authority for Nuclear Activities), ICN (Institute for Nuclear Research - Pitesti), SITON (Center of Design and Engineering for Nuclear Projects- Bucharest); ROMAG-PROD (Heavy Water Plant), CNE-PROD (Cernavoda Nuclear Power Plant - Production Unit), CNE-INVEST (Cernavoda Nuclear Power Plant -Investments Unit), FCN (Nuclear Fuel Factory). The Institute for Nuclear Research, Pitesti INR, Institute for Nuclear Research, Pitesti is endowed with a TRIGA Reactor, Hot Cells, Materials Laboratories, Nuclear Fuel, Nuclear Safety Laboratories, Nuclear Fuel, Nuclear Safety. Waste management. Other research centers and laboratories implied in nuclear activities are: ICIT, National Institute for cryogenics and isotope technologies at Rm Valcea Valcea. with R and D activity devoted to heavy water technologies, IFIN, Institute for nuclear physics and engineering, Bucharest, as well as the educational institutions involved in atomic energy applications and University research, Politechnical University Bucharest, University of Bucharest, University of Pitesti, etc. The INR activity outlined, i.e. the nuclear power research as a scientific and technical support for the Romanian nuclear power programme, mainly dedicated to the existing NPP in the country (CANDU). Focused with priority are: - Nuclear Safety (behavior of plant materials, components, installations during accident conditions and integrity investigations); - Radioactive Waste Management Radioactive; - Radioprotection; Product and services supply for NPP. INR Staff numbers 320 R and D qualified and experienced staff, 240 personnel in devices and prototype workshops and site support

  17. Hydrodynamics and sediment transport at Muria Peninsula NPP Site

    International Nuclear Information System (INIS)

    Heni Susiati; Berni A Subki; Harman A

    2011-01-01

    Coastal along the coast of the Muria Peninsula, particularly the location of the Muria NPP site candidate is a dynamic region, the interaction between physical oceanographic factors such as currents, waves and tides in the coastal sediments cause abrasion or accretion. Interactions have resulted in coastal dynamics needs to be considered in siting NPP is essential in order to plan. Capacity of hydro-oceanographic data is essential in order to plan the development of the Muria NPP. The process of selecting a safe site for hydro-oceanographic aspects carried out according to IAEA safety standards on site selection. For the evaluation stage of hydro oceanographic potential site (site survey stage), the analysis is more focused on the tidal along the northern coast, bathymetry, potential water resources and hydrologic systems in the Muria NPP siting locations, Jepara. The method used is a secondary, confirmation of field data collection and interpretation of modeling results. The results showed that the preparation for the construction of NPP need to be evaluated further to coastal conditions with respect to the increase coastal erosion in the area of prospective NPP siting. (author)

  18. 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.

  19. 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

  20. Analysis of the failed threaded rod from the support of the pipelines from CNE Cernavoda

    International Nuclear Information System (INIS)

    Fulger, M.; Mihalache, M.; Velciu, L.; Nitu, A.; Puscasu, C.

    2016-01-01

    The goal of the current study was analysis of one threaded rod from the support of pipelines from CNE Cernavoda raw water cooling system (RCW) to identify the causes of its breakage. For the failure analysis, were used following techniques: optical microscopy, scanning electron microscopy/ energy dispersive X - ray spectrometry (EDS) and mechanical tries (Brinell hardness). The conclusion was the failure had been caused by improper mounting of the rod in the spring guide system. Thus, a complex distribution of tensions emerged, rather than the vertical distribution as designed for the guide with spring. On the other hand, the presence of a hard impurity (titanium carbide), in the threaded region and the usage of a material with greater hardness and with higher chrome composition than specified in the project, had favored the appearance of a fatigue fissure, leading to a tear in the rod. (authors)

  1. Conference: Nuclear Safety at the Ignalina NPP - Achievements and Challenges

    International Nuclear Information System (INIS)

    1999-01-01

    Brief description of conference which took place in Vilnius on 8-9 April 1999 is presented. The aim of the international conference is to review the work carried out, to evaluate its influence on the nuclear safety, to get acquainted with the safety system of the Ignalina NPP. On December 31, the Ignalina NPP celebrated its 15 year anniversary. During that period the Ignalina NPP has produced more than 182 billion kWh of electricity. Nuclear power is not only immense economic benefit but also a syndrome of fear of an atomic bomb and the Chernobyl accident that has formed over the years. Numerous comprehensive international studies have been performed at the Ignalina NPP. After the Chernobyl accident many steps have been taken to improve the safety of the Ignalina NPP. The introduced changes guaranteed that the void coefficient remained negative in all possible circumstances. The Ignalina NPP is intensively preparing for licensing of unit 1

  2. Maintaining staff competence-a NPP operator viewpoint

    International Nuclear Information System (INIS)

    Patrakka, E.

    2000-01-01

    For a nuclear power plant operator, it is crucial to guarantee the safe and economic operation of the power plant as well as to look after the general acceptability of nuclear power. As to human resources management, this requires continuous maintenance and enhancement of the performance of the individuals and organisation. To this end, several development projects have recently been implemented by Teollisuuden Voima Oy (TVO) at the Olkiluoto nuclear power plant, which consists of twin 840 MWe BWR units that commenced their operation in 1978 and 1980. Systematic initial and continuing training programmes are needed to maintain the technical and managerial skills and know-how at a high level. The present stabile state of nuclear power, i.e. operation of ageing plants with personnel ageing as well, requires a variety of actions to reinforce the training efforts. At Olkiluoto NPP, we have carried out an extensive modernization programme that allowed the personnel to strengthen their knowledge and supplement it with the most recent results of development. We have also closely monitored the NPP development projects of the vendors, which has added to the preservation of know-how and understanding of advanced nuclear power technology. We have close contacts to the research institutes and universities, and have performed R and D activities to limited extent. In addition to the projects mentioned above, a co-ordinated development programme, 'TVO 2002', was initiated last year. The main objective of this programme is to ensure the functional preconditions and the competitiveness of the company in a changing environment. The management and operational procedures will be developed in such a way that the goals set for year 2002 will be achieved. The programme is organised as ten projects, which cover a variety of development subjects. One of the focal areas includes projects that can be characterised with the words 'Survey of competencies' and 'Preservation of know

  3. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    Directory of Open Access Journals (Sweden)

    Volmert Ben

    2016-01-01

    Full Text Available In this paper, an overview of the Swiss Nuclear Power Plant (NPP activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  4. 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)

  5. Recent experience of Almaraz NPP in operator training

    International Nuclear Information System (INIS)

    Sanchez Cabanero, J.G.; Gomez de la Torre, J.M.

    1994-01-01

    In recent years the nuclear industry has been paying special attention to boosting nuclear power plant operation. To this end, it has optimized its maintenance, engineering, safety, management and other systems, using the appropriate resources to achieve its target. Optimization of these systems required the allocation of new resources for training plant personnel. The activity of training, which hitherto dedicated most of its attention and resources to the operating area, now extends them to schooling required in other areas of the plant, with the aim of updating the skills and knowledge of personnel to deal with new needs which have arisen. Regulations at present cover the training and qualification of only personnel responsible for handling reactor or for directing plant operation activities and capable of evaluating the nature and magnitude of possible incidents, especially those causing radioactive emissions, and of personnel requiring knowledge and experience to guarantee effective protection of individuals, ie, operators, supervisors, and qualified radiological protection experts. However, it should be borne in mind that, in the future, the training of other plant personnel could also be subject to regulations. (Author)

  6. 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

  7. Current technological trends in development of NPP systems

    International Nuclear Information System (INIS)

    Florescu, Gheorghe; Panaitescu, Valeriu

    2010-01-01

    The recent nuclear research issues look for new technologies and continuous progress in finding different and efficient solutions for sustained and upraising energy demand. The trend of increasing energy consumption and occurring of new and large consumers, especially from Asian countries, imposes finding of new means for clean, large scale and sustained energy production. NPPs availability was continuously monitored and improved; at the same time the safety of the nuclear energy production was under surveillance. The present development of the new technologies, the discoveries of new materials and development of efficient technological processes offer the opportunities for their appropriate implementation and use in the NPP system configurations and functioning/operation. The new technologies and scientific discoveries, and also the international cooperation, offer the opportunities to mitigate the actual barriers in order to cumulate and use advanced energy production, to find new energy sources and to build improved, reliable and safe power plants. The monitoring systems, intelligent sensors and SSCs, nanotechnologies and new/intelligent materials constitute the main ways for improvement of the NPP systems configuration and processes. The paper presents: - The state of the art in the level of the currently applied technologies for nuclear power systems development; - The actual technological limits that need to be over passed for improving the NPP systems ; - The main systems that need improvement and reconfiguration for development of currently operating NPPs as well as raising the operation efficiency, availability and total safety; - The actual energy production issues; - The key arguments in sustaining the R and D new NPP systems development; - Future trends in NPP development; - The limitations in industrial processes knowledge and use. Appropriate R and D in the field of NPP systems have specific characteristics that were considered in paper completion

  8. A new training philosophy: The local system of development of competence

    International Nuclear Information System (INIS)

    Billard, P.

    1996-01-01

    Fifteen years ago, the French Nuclear Program has created a particular climate full of dynamism and enthusiasm, in the accomplishment of which each individual has been motivated, using the strong centralized training system with aims to develop knowledge and skills necessary to be promoted in new jobs. Now a day environment has been changed because of, among other things, the general career development plateau, the aging of installations and personnel and the external pressure on nuclear safety. It is now necessary to move from a centralized training system of development of skills to local systems of development of competencies. But how to keep advantages of standardized nuclear program with individual plant organization which is different from one plant to another? The paper describes how EDF is changing his training organization, the relationship between NPP's and training centres, the roles and responsibilities between corporate resources departments, NPP management and training centres. (author)

  9. Selection, specification, design and use of various nuclear power plant training simulators

    International Nuclear Information System (INIS)

    Bruno, R.; Neboyan, V.

    1997-01-01

    Several IAEA guidance publications on safety culture and NPP personnel training consider the role of training and particularly the role of simulators training to enhance the safety of NPP operations. Initially, the focus has been on full-scope simulators for the training of main control room operators. Presently, a wide range of different types of simulators are used at training center. Several guidance publications concerning development and use of full-scope simulators are currently available. Experience shows that other types of simulators are also effective training tools that allow simulator training for a broader range of target groups and training objectives. Based on this need, the IAEA undertook a project to prepare a report on selection, specification, design and use of various training simulators, which provides guidance to training centers and suppliers for proper selection, specification, design, and use of various form of simulators. In addition, it provides examples of their use in several Member States. This paper presents a summary of the IAEATECDOC publication on the subject. (author)

  10. Emergency preparedness at Barsebaeck NPP in Sweden

    International Nuclear Information System (INIS)

    Olsson, R.; Lindvall, C.

    1998-01-01

    On-site emergency preparedness plan at Barsebaeck NPP is presented. In an emergency the responsibility of the NPP is to alarm the emergency organizations, spend all efforts to restore safe operation, assess the potential source term as to size and time, protect their own personnel, inform personnel and public. Detailed emergency procedures overview is provided

  11. Staffing of nuclear power plants and the recruitment, training and authorization of operating personnel

    International Nuclear Information System (INIS)

    1991-01-01

    This Safety Guide was prepared as part of Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPP). It supplements Safety Series No. 50-C-O(Rev.1) ''Code on the Safety of Nuclear Power Plants: Operation''. The present version of this Guide is a revision which takes into account the developments, particularly in training practices, which have taken place since the first edition appeared in 1979. The objective of this Safety Guide is to outline various factors to be considered in order to ensure that the operating organization has a sufficient number of qualified and motivated personnel for the operation of NPP. The Guide covers the organization for a NPP, the requirements in terms of education and experience for the various members of the operating personnel to be recruited, the recruitment, the training and continuing training programmes, as well as the authorizations for persons whose duties have an immediate bearing on safety

  12. Managing delayed projects. Cernavoda NPP - Romania. Importance of NGO involvement

    International Nuclear Information System (INIS)

    Rotaru, I.

    2003-01-01

    In Romania there is a diversity of civil societies with respect to the attitude towards nuclear power. Among the dedicated societies supporting nuclear power development there are: the Romanian Atomic Forum (Ratomet), affiliated to the European Atomic Forum; the Romanian Nuclear Power Association (Arden), affiliated to the European Nuclear Society; the Romanian Radioprotection Society (SR Rp), affiliated to the Radiation Protection Association. The main dedicated activities of above mentioned Non-governmental Organizations (Ng) are: establishing contacts and organizing meeting with Romanian political decision making factors, mass media representatives, institutional entities, civil society ect.; orienting and co-coordinating activities of Romanian companies involved in production and services for nuclear energy; serving as contact point for relevant international communication and business relation; creating internal working groups for certain theme or sub-domain and suggested solution for a particular issue, including experts even from outside of the association; performing lobby activities ect

  13. 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)

  14. On the NPP structural reliability

    International Nuclear Information System (INIS)

    Klemin, A.I.; Polyakov, E.F.

    1980-01-01

    Reviewed are the main statements peculiarities and possibilities of the first branch guiding technical material (GTM) ''The methods of calculation of structural reliability of NPP and its systems at the stage of projecting''. It is stated, that in GTM presented are recomendations on the calculation of reliability of such specific systems, as the system of the reactor control and protection the system of measuring instruments and automatics and safe systems. GTM are based on analytical methods of modern theory of realibility with the Use of metodology of minimal cross sections of complex systems. It is stressed, that the calculations on the proposed methods permit to calculate a wide complex of reliability parameters, reflecting separately or together prorerties of NPP dependability and maintainability. For NPP, operating by a variable schedule of leading, aditionally considered are parameters, characterizing reliability with account of the proposed regime of power change, i.e. taking into account failures, caused by decrease of the obtained power lower, than the reguired or increase of the required power higher, than the obtained

  15. Approach to training the operators of WWER-440 reactors

    International Nuclear Information System (INIS)

    Pironkov, L.; Minakova, R.

    2002-01-01

    The paper has three parts. (1) Personnel Training and Qualifications (2) Description of Kozloduy NPP Training and Qualification System (TQS) built in the last 7 years and its interfaces with the Certification System and (3) Application of the TQS for the Senior Reactor Operator (SRO). (author)

  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. Unit Commissioning of “Belene” NPP (Bulgaria)

    International Nuclear Information System (INIS)

    2009-01-01

    This presentations gives detailed information about the following topics about commissioning: principles of NPP commissioning; phases of NPP commissioning; organization of commissioning activities; duties and responsibilities of the parties for carrying out unit commissioning activities; responsibility and obligations of the sides during commissioning of power unit; documentation required for power unit commissioning; quality assurance for commissioning activities

  18. Constructive approaches to the space NPP designing

    International Nuclear Information System (INIS)

    Eremin, A.G.; Korobkov, L.S.; Matveev, A.V.; Trukhanov, Yu.L.; Pyshko, A.P.

    2000-01-01

    An example of designing a space NPP intended for power supply of telecommunication satellite is considered. It is shown that the designing approach based on the introduction of a leading criterion and dividing the design problems in two independent groups (reactor with radiation shield and equipment module) permits to develop the optimal design of a space NPP [ru

  19. Chernobyl NPP accident. Overcoming experience. Acquired lessons

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Prister, B.S.

    2006-01-01

    This book is devoted to the 20 anniversary of accident on the Chernobyl NPP unit 4. History of construction, causes of the accident and its consequences, actions for its mitigation are described. Modern situation with Chernobyl NPP decommissioning and transferring of 'Ukryttya' shelter into ecologically safe system are mentioned. The future of Chernobyl site and exclusion zone was discussed

  20. Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    In 1996 the IAEA published a guidebook on Nuclear Power Plant Personnel Training and its Evaluation, which constitutes the recommendations of the IAEA with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the effectiveness of NPP personnel training. As the nuclear power industry continues to be challenged by increasing safety requirements, a high level of competition and decreasing budgets, it becomes more important than ever to have some methodology of ensuring that training contributes a value to the organization. The actual determination of training effectiveness is not an easy task because of the many variables associated with personnel performance. For example, for training to make a difference in job performance, line management should be involved prior to training delivery to identify what performance is desired, but not being achieved. Then, training is developed to meet desired performance, which is followed by practice and continued management reinforcement. Because of these other variables, it is very difficult to prove that training had a sole contribution to performance improvement, but rather one of many contributors needed for performance improvement. The difficulty to isolate training as a sole contributor has been documented in a number of research studies over the recent years. Due to these limitations, a base assumption must be made in order to use any methodology for training effectiveness evaluation. That assumption is that there are some basic principles for developing training and if training programmes are developed and maintained using these principles, then the training provided should be an effective tool to improve the line organization performance. By monitoring various types of training effectiveness indications

  1. Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

    International Nuclear Information System (INIS)

    2003-07-01

    In 1996 the IAEA published a guidebook on Nuclear Power Plant Personnel Training and its Evaluation, which constitutes the recommendations of the IAEA with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the effectiveness of NPP personnel training. As the nuclear power industry continues to be challenged by increasing safety requirements, a high level of competition and decreasing budgets, it becomes more important than ever to have some methodology of ensuring that training contributes a value to the organization. The actual determination of training effectiveness is not an easy task because of the many variables associated with personnel performance. For example, for training to make a difference in job performance, line management should be involved prior to training delivery to identify what performance is desired, but not being achieved. Then, training is developed to meet desired performance, which is followed by practice and continued management reinforcement. Because of these other variables, it is very difficult to prove that training had a sole contribution to performance improvement, but rather one of many contributors needed for performance improvement. The difficulty to isolate training as a sole contributor has been documented in a number of research studies over the recent years. Due to these limitations, a base assumption must be made in order to use any methodology for training effectiveness evaluation. That assumption is that there are some basic principles for developing training and if training programmes are developed and maintained using these principles, then the training provided should be an effective tool to improve the line organization performance. By monitoring various types of training effectiveness indications

  2. Radiation protection in Bohunice NPP. Description of present status

    International Nuclear Information System (INIS)

    Dobis, L.

    2001-01-01

    Radiation protection (RP) at Bohunice NPP has reached the high international standard. The fact was approved by several independent international missions (OSART , WANO, WENRA, ...). A lot of modifications have been done in order to improve the standard of radiation protection. All the BSS requirements have been implemented into the plant regulations before the State Law No 290/1996 and 470/2000 came into the force. Internal audits are regularly performed at NPP in order to reveal potential deficiencies. In 2001 there were 4 such audits focused on quality assurance, software operation, LBB concept and limits and condition of safe operation. State Health Institute, the regulatory body in the radiation protection, performs the inspection at least ones a month. Good relationship with the inspectors of State Health Institute also contributes to the safe operation of the NPP. There were not any radiation accident. All anomalies or radiation events are investigated at a plant level. The results of root cause analysis and proposal of corrective actions are provided to IAEA and WANO databases for the distribution. The Radiation protection department of Bohunice NPP cooperates with the other Czech and Slovak NPPs. Regular meetings on radiation protection and lately also on emergency preparedness are organized. The cooperation is excellent. Occupational exposure is reviewed also with respect of ISOE data. Bohunice NPP (even with high dose burden caused by reconstruction of V1 NPP) can be found in the first half of world PWR speaking about the collective exposure per reactor. V2 NPP itself reaches the lowest collective exposure in the world. All doses are below the limits and kept ALARA. ALARA system has been established already in 1997 at Bohunice NPP and its results are obvious for example looking at dose results during the reconstruction works at V1 NPP. The operation of Bohunice NPP has negligible influence to its surroundings. The values of gas and liquid effluents move

  3. 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

  4. Using the digital reactor control systems at NPP

    International Nuclear Information System (INIS)

    Schirl, G.; Hertel, J.

    2006-01-01

    A conception of application of the digital reactor control systems (RCS) at NPP is presented. The digital RCS architecture and safety ensuring are considered. The strategy and algorithm of the operating NPP equipping with the new digital RCS are given too [ru

  5. 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

  6. Heat delivery from Bohunice NPP, Slovakia

    International Nuclear Information System (INIS)

    Paley, I.

    1998-01-01

    Experience with nuclear district heating in the Slovak Republic is reported. The heating system of the town of Trnava is supplied by the Bohunice NPP and conventional sources. Construction of the hot water heating system from the Bohunice NPP began in 1983. Commercial operation began on 10 December 1987. Heat delivery has gradually increased from 478 TJ in 1988, to 1,104 TJ in 1995. The heat cost is low, resulting in an increasing number of consumers. (author)

  7. NPP Krsko on-line low pressure containment tightness monitoring implementation

    International Nuclear Information System (INIS)

    Dudas, M.; Basic, I.

    2004-01-01

    Containment Integrated Leak Rate Test (CILRT) 1999 in NPP Krsko was completely performed following regulation of 10CFR50 Appendix J Option A and ANSI/ANS 56.8-1987 at a design pressure (3.15 kp/cm2). In 2001 NPP Krsko proposed to Slovenian Nuclear Safety Administration (SNSA) the Technical Specification (TS) and Updated Safety Analysis Report (USAR) changes that describe implementation of new test intervals for Type A, B and C tests according to 10CFR50, Appendix J, Option B. After the positive final independent review of proposed changes by Authorized Institution, NPP Krsko received the License Amendment requiring from NPP Krsko to define technical solution for surveillance of containment tightness between two 10-years CILRT. This paper intends to discuss proposed methods by NPP Krsko, test equipment, performed measurements in 2004, associated analyses and evaluation.(author)

  8. Influence of the crustal and subcrustal Vrancea seismic sources on Cernavoda nuclear power plant site

    International Nuclear Information System (INIS)

    Marmureanu, Gheorghe; Popescu, Emilia; Mircea Radulian

    2002-01-01

    The basis of the seismic hazard assessment in different geographical regions with dense-populated areas and strategic objectives (dams, nuclear power plants, etc.) is the study of seismicity of the seismogenic sources which affect these sites. The purpose of this paper is to provide a complete set of information relative to the Vrancea seismic source (in the crust and the intermediate depth domains) that is fundamental for the seismic hazard evaluation at Cernavoda nuclear power plant site. The analysis that we propose has to deal with the following items: (1) geometrical definition of the seismic sources; (2) setting the earthquake catalog associated to each seismic source; (3) estimation of the maximum possible magnitude; (4) estimation of the frequency - magnitude relationship; (5) computation of the distribution function for focal distance; (6) correlation between focal depth and magnitude; (7) attenuation law. We discuss also the implications of the model parameters on the seismic hazard level. (authors)

  9. Severe accident training simulator APROS SA

    International Nuclear Information System (INIS)

    Raiko, Eerikki; Salminen, Kai; Lundstroem, Petra; Harti, Mika; Routamo, Tomi

    2003-01-01

    APROS SA is a severe accident training simulator based on the APROS simulation environment. APROS SA has been developed in Fortum Nuclear Services Ltd to serve as a training tool for the personnel of the Loviisa NPP. Training with APROS SA gives the personnel a deeper understanding of the severe accident phenomena and thus it is an important part of the implementation of the severe accident management strategy. APROS SA consists of two parts, a comprehensive Loviisa plant model and an external severe accident model. The external model is an extension to the Loviisa plant model, which allows the simulation to proceed into the severe accident phase. The severe accident model has three submodels: the core melting and relocation model, corium pool model and fission product model. In addition to these, a new thermal-hydraulic solver is introduced to the core region of the Loviisa plant model to replace the more limited APROS thermal-hydraulic solver. The full APROS SA training simulator has a graphical user interface with visualizations of both severe accident management panels at the operator room and the important physical phenomena during the accident. This paper describes the background of the APROS SA training simulator, the severe accident submodels and the graphical user interface. A short description how APROS SA will be used as a training tool at the Loviisa NPP is also given

  10. 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.)

  11. Trends of Training Courses Conducted in the Human Resources Development Center of the National Institute for Quantum and Radiological Science and Technology After the Fukushima Dai-Ichi Nuclear Power Plant Accident.

    Science.gov (United States)

    Shimizu, Yuko; Iida, Haruzo; Nenoi, Mitsuru

    2017-07-01

    Environmental contamination with radioactive materials caused by the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident in 2011 raised a serious health concern among residents in Japan, and the demand for radiation experts who can handle the radiation-associated problems has increased. The Human Resources Development Center (HRDC) of the National Institute of for Quantum and Radiological Science and Technology in Japan has offered a variety of training programs covering a wide range of technologies associated with radiation since 1959. In this study, the time-course change in the number and age of the applicants for training programs regularly scheduled at HRDC were analyzed to characterize the demand after the NPP accident. The results suggested that the demand for the training of industrial radiation experts elevated sharply after the NPP accident followed by a prompt decrease, and that young people were likely stimulated to learn the basics of radiation. The demand for the training of medical radiation experts was kept high regardless of the NPP accident. The demand for the training of radiation emergency experts fluctuated apparently with three components: a terminating demand after the criticality accident that occurred in 1999, an urgent demand for handling of the NPP accident, and a sustained demand from local governments that undertook reinforcement of their nuclear disaster prevention program. The demand for the training of school students appeared to be increasing after the NPP accident. It could be foreseen that the demand for training programs targeting young people and medical radiation experts would be elevated in future.

  12. 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

  13. Meeting up-to-date safety requirements in the Russian NPP projects

    International Nuclear Information System (INIS)

    Tepkyan, G. O.; Yashkin, A. V.

    2014-01-01

    Safety features in Russian NPP designs are implemented by the combination of active and passive safety systems • Russian NPP designs are in compliance with up-to-date international and European safety requirements and refer to Generation III+ • Russian state-of-the-art designs have already implemented some design solutions, which take into account “post-Fukushima” requirements. Russian NPP design principles have been approved during the European discussions in spring 2012, including the IAEA extraordinary session addressed to Fukushima NPP accident

  14. Seismic assessment of a site using the time series method

    International Nuclear Information System (INIS)

    Krutzik, N.J.; Rotaru, I.; Bobei, M.; Mingiuc, C.; Serban, V.; Androne, M.

    2001-01-01

    1. To increase the safety of a NPP located on a seismic site, the seismic acceleration level to which the NPP should be qualified must be as representative as possible for that site, with a conservative degree of safety but not too exaggerated. 2. The consideration of the seismic events affecting the site as independent events and the use of statistic methods to define some safety levels with very low annual occurrence probabilities (10 -4 ) may lead to some exaggerations of the seismic safety level. 3. The use of some very high values for the seismic accelerations imposed by the seismic safety levels required by the hazard analysis may lead to very expensive technical solutions that can make the plant operation more difficult and increase the maintenance costs. 4. The consideration of seismic events as a time series with dependence among the events produced may lead to a more representative assessment of a NPP site seismic activity and consequently to a prognosis on the seismic level values to which the NPP would be ensured throughout its life-span. That prognosis should consider the actual seismic activity (including small earthquakes in real time) of the focuses that affect the plant site. The method is useful for two purposes: a) research, i.e. homogenizing the history data basis by the generation of earthquakes during periods lacking information and correlation of the information with the existing information. The aim is to perform the hazard analysis using a homogeneous data set in order to determine the seismic design data for a site; b) operation, i.e. the performance of a prognosis on the seismic activity on a certain site and consideration of preventive measures to minimize the possible effects of an earthquake. 5. The paper proposes the application of Autoregressive Time Series to issue a prognosis on the seismic activity of a focus and presents the analysis on Vrancea focus that affects Cernavoda NPP site by this method. 6. The paper also presents the

  15. 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)

  16. Near Regional and Site Investigations of the Temelin NPP Site

    International Nuclear Information System (INIS)

    Prachar, Ivan; Vacek, Jiri; Heralecky, Pavel

    2011-01-01

    The Temelin NPP is worldwide through heated discussion with nuclear energetic opposition. In addition this discussion goes beyond a border of the Czech Republic. On the other side, results of several international supervisions shown that Temelin NPP is fully comparable with the safest nuclear power plants in the world regarding its technical design and safety functions. This presentation deals with the near regional and site investigations of the Temelin NPP Site. It must be noted that although the Temelin site is situated in the area with low seismicity, item of seismicity is a basic argument against Temelin NPP and therefore a detail seismic hazard assessment was performed

  17. 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

  18. Romania - NPP PLiM Between Regulatory Requirement / Oversight and Operator Safety / Financial Interest

    International Nuclear Information System (INIS)

    Goicea, Lucian

    2012-01-01

    Cernavoda Unit 1 PLiM started in the first third of its design life, to develop as regulatory requirements of the components of standards and programmes and to benefit by earlier implementation of the measures for achieving maximum operating life. CNCAN regulatory present approach on the utility PLiM combines the regulatory requirements on management system, ageing management provisions of periodic safety review, detailed technical requirements of ageing programmes and different techniques focusing only on safety issues. (author)

  19. The Romania industry capability of participating in the development of 1998 Nuclear Program

    International Nuclear Information System (INIS)

    Mocanu, Horia

    1998-01-01

    Nuclear high technologies and know-how have been purchased and entirely assimilated by the Romanian nuclear industry. Also, as result of Romanian research high technologies were implemented as for instance the technologies of fabrication and reprocessing of heavy water. As a result the implication of Romanian industry in supplying equipment and components as well as in building the mounting achievements destined to nuclear power program raised continuously. The cost of the effort to create the nuclear industry infrastructure amounts up to USD 4 billions. To date, owing to reconversion and adaptation to the lower demand of today energy market, important drawback of nuclear Romanian industry are recorded, both in the field of material and personnel investments. So, the material losses at the Cernavoda Unit 2 are estimated to USD 10 millions, while the losses in skilled personnel are estimated to 12,000 specialists, of which 1,500 are graduate persons, 2,000 are technicians and over 8,000 are highly qualified workers. The present process of privatization appear to be not affected by the strategic character of the nuclear field as it is proved by the recent purchase of the main share packets of the IMGB SA and FECNE SA (the plant of NPP equipment) by the trans-national group KVAERNER. Other serious drawbacks are caused by the non-finished investments like the plants for production of titanium and zirconium ingots and titanium and zircaloy tubes, the forth line of heavy water production, the tritium reprocessing unit and the plant for production of long stainless ducts for NPP condensers, etc. In spite of these deficiencies, a large fraction of the questioned industrial enterprises have stated their capacity and willingness in co-financing the Units 2-5 at Cernavoda NPP by production and services

  20. Safeguards at Kozloduy NPP - Experience and expectations

    International Nuclear Information System (INIS)

    Elenkov, Todor

    2001-01-01

    Bulgaria is a party of Non Proliferation Treaty since 5 September 1969. The agreement between IAEA and Bulgaria - INFCIRC 178 - has been in force since 29 February 1972. At that time Bulgaria had one research reactor IRT-2000 in Sofia and two power reactors of WWER-440 type under construction. Now at Kozloduy NPP site there are 4 facilities, which consist of 4 WWER-440 and 2 WWER-1000 type power reactors, producing almost 50% of the electricity in Bulgaria and 1 wet away from reactor spent fuel storage. In 1991 under the green movements and social pressure, the research reactor in Sofia was closed and the construction of the second NPP in Belene with 2 WWER-1000 type reactors was halted. After the transfer in 1994 of the fresh fuel from the research reactor to Kozloduy due to security reasons practically NPP Kozloduy remains the only significant (from safeguards point of view) nuclear site in Bulgaria. In 1972 a 'Nuclear Fuel' group was formed at the Physicists Department in NPP Kozloduy with responsibilities to carry out for safeguards records and reports, fresh and spent fuel transport and control. In 1990 this group was transferred to the Safety Section and since 1992 it exists as 'Control and Accounting for of the Nuclear Materials' - a section in the Safety Department. Currently the section serves all four facilities in NPP Kozloduy and has four people: section head, chief inspector and two inspectors. The main activities of the section include: a) Control of the nuclear fuel location as well as meeting the storage and transport conditions regulations; b) Control of the conditions for normal operations of the installed IAEA surveillance systems; c) Preparation of documents for licensing of fresh and spent nuclear fuel transport; d) Preparation of the official information on nuclear materials location and quantity; e) Preparation of accounting records and the reports for IAEA (ICR, PIL, MBR); f) Co-ordination of the IAEA safeguards inspection activities at NPP

  1. Education and Training for the NPP Workforce

    International Nuclear Information System (INIS)

    Long, R.L.

    2006-01-01

    This paper describes some of the nuclear industry workers skill needed, give some quantitative estimated of the numbers of worker needed, identifies some possible education and training resources and concludes with some suggestion for getting started on this important infrastructure element

  2. Attitude of the population and students to further construction of NPP

    International Nuclear Information System (INIS)

    Machacek, Ladislav

    1993-01-01

    This presentation shows the public opinion poll young people on NPP in the Slovakia i.e. comparative research results on Attitude of the Slovak population (1991 - a sample 1104 respondents, and Slovak students 1992 - a sample 291 respondents) to the nuclear energy and NPP; Source of information about NE and NPP, motivation of apprehensions of young people concerning NE; what meaning for young people have the arguments FOR and AGAINST construction of NPP in Slovakia; whom students from Bratislava believe during discussions about NE

  3. Report of the ASSET (Assessment of Safety Significant Events Team) mission to the Cernavoda nuclear power plant in Romania 8-12 August 1994 Division of Nuclear Safety. Root cause analysis of a significant event that occurred during commissioning of unit 1

    International Nuclear Information System (INIS)

    1994-01-01

    The IAEA Assessment of Safety Significant Events Team (ASSET) report presents the results of the team's investigation of a significant event that occurred during commissioning of Unit 1 of Cernavoda nuclear power plant. The results, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible authorities in Romania. The ASSET team's views presented in this report are based on visits to the plant, on review of documentation made available by the operating organization and on discussions with utility personnel. The report is intended to enhance operational safety at Cernavoda by proposing improvements to the policy for the prevention of incidents at the plant. The report includes, as a usual practice, the official response of the Regulatory Body and Operating Organization to the ASSET recommendations. Figs

  4. New trends in designing NPP control boards

    International Nuclear Information System (INIS)

    Kondrat'ev, V.V.

    1981-01-01

    A short analytical summary of the latest developments and future trends in designing NPP control boards is given. The designs of the Westinghause and the Hynkley-Point NPP control boards are described in detail. The essence of the advanced control board concept consists , firstly, in expanded use of computer-controlled displays for the sake of reducing the content of unimportant information presented to an operator, and, secondary, in better account of human possibilities to convert the NPP operation information into a more suitable form. An enlarged use of the direct digital reactor control utilizing microprocessors is expected. Besides, the employment of full-scale control board mock-ups and information desks as well as testing newly-developed control boards at computer reactor simulators are concluded to be used at all-growing rate [ru

  5. Some problems of NPP construction base improvement

    International Nuclear Information System (INIS)

    Movchan, S.V.

    1984-01-01

    NPP construction bases are characterized by high cost of construction and large area. Duration of base construction makes up 3-4 years, labour contents for their erection constitute 600-900 thousand man-days. Delays in organizing functional base services essentially decelerate construction rates of the main NPP buildings. Maximum joining of separate buildings by their functional assignment and structural peculiarities, wide application of container buildings, partial utilization of permanent buildings of production centre for construction needs; transition to new organizational form of construction based on industrial production of buildings; production of volumetric structural-technological cells with mounted equipment manufactured at specialized plants, mounting NPP components with stock produced cells, consideration of the problem of large power centre creation are necessary for reduction of construction centres, area reduction of cost and duration of their construction

  6. Qinshan NPP large break LOCA safety analysis

    International Nuclear Information System (INIS)

    Shi Guobao; Tang Jiahuan; Zhou Quanfu; Wang Yangding

    1997-01-01

    Qinshan NPP is the first nuclear power plant in the mainland of China, a 300 MW(e) two-loop PWR. Large break LOCA is the design-basis accident of Qinshan NPP. Based on available computer codes, the own analysis method which complies with Appendix k of 10 CFR 50 has been established. The RELAP4/MOD7 code is employed for the calculations of blowdown, refill and reflood phase of the RCS respectively. The CONTEMPT-LT/028 code is used for the containment pressure and temperature analysis. The temperature transient in the hot rod is calculated using the FRAP-6T code. Conservative initial and functional assumptions were adopted during Qinshan NPP large break LOCA analysis. The results of the analysis show the applicable acceptance criteria for the loss-of-coolant accident are met

  7. Construction of large-thickness sand cushions for NPP foundations

    International Nuclear Information System (INIS)

    Krantsfel'd, Ya.L.; Losievskaya, I.K.; Kovalenko, R.P.; Mutalipov, A.

    1982-01-01

    A study is made on some technological peculiarities of preparation of NPP foundations and control methods of foundation density. As an example the experience of cement-sand foundation construction for two 900 MW power-units at the Koeberg South Africa NPP is briefly described. The experience of artificial foundation construction at this NPP indicates both the possibility of obtaining the required quality of cement-sand cushions and commercial construction of large volume of such cushions by acceptable rates and the necessity of unification of work quality characteristics

  8. 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

  9. Eddy currents inspection of CANDU steam generator' tubes using Zetec's ZR-1 Robot: experience in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Hower, S. [Zetec Inc., Quebec, Quebec (Canada); Serban, M. [CNE-Prod U1 Cernavoda (Romania); Vladu, L. [Compcontrol Ing., Bucharest (Romania)

    2006-07-01

    'Full text:' The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience-based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of toolheads, ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, lightweight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The Cernavoda plant has four Advanced 600 MW CANDU-design generators that have been in service since 1996. The paper presents also the Zetec's filed experience and customer experience with this system. It describes the equipment setup in Cernavoda's generator mock-up, functional testes and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (author)

  10. Introduction to the training center and development of SAT-based training materials at Paks NPP

    International Nuclear Information System (INIS)

    Kiss, I.

    1996-01-01

    Training of the plant personnel has always been a top-important issue for the top-management. Before commissioning of unit 1 training had been delivered in training centres of neighbouring countries supporting WWER-440/230 units (Novovoronech, Trnava, Reinsberg, Greifsvald). The commissioning and operational experiences of the first years allowed establishing home training. For this purpose, training programs, Hungarian training materials and tools were developing which is described. In this process, Hungarian academic and research institutes took part from the very beginning

  11. 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

  12. Procedure for Application of Software Reliability Growth Models to NPP PSA

    International Nuclear Information System (INIS)

    Son, Han Seong; Kang, Hyun Gook; Chang, Seung Cheol

    2009-01-01

    As the use of software increases at nuclear power plants (NPPs), the necessity for including software reliability and/or safety into the NPP Probabilistic Safety Assessment (PSA) rises. This work proposes an application procedure of software reliability growth models (RGMs), which are most widely used to quantify software reliability, to NPP PSA. Through the proposed procedure, it can be determined if a software reliability growth model can be applied to the NPP PSA before its real application. The procedure proposed in this work is expected to be very helpful for incorporating software into NPP PSA

  13. Ignalina NPP Safety Analysis: Models and Results

    International Nuclear Information System (INIS)

    Uspuras, E.

    1999-01-01

    Research directions, linked to safety assessment of the Ignalina NPP, of the scientific safety analysis group are presented: Thermal-hydraulic analysis of accidents and operational transients; Thermal-hydraulic assessment of Ignalina NPP Accident Localization System and other compartments; Structural analysis of plant components, piping and other parts of Main Circulation Circuit; Assessment of RBMK-1500 reactor core and other. Models and main works carried out last year are described. (author)

  14. Radionuclide localization at the Chernobyl' NPP territory

    International Nuclear Information System (INIS)

    Mamaev, L.A.; Galkin, G.A.; Khrabrov, S.L.; Polyakov, A.S.; Mikhejkin, S.V.

    1989-01-01

    Experience is generalized of using different dust suppression (DS) compounds during Chernobyl' accident consequence elimination. Polymer DS compounds were used at the NPP operating site; the compounds kept dust-like radioactive contaminations during 1-2 months. DS at the country was realized by means of the compound on base of latex. The conclusion is made that the DS measures improved radiation situation in the NPP zone. 7 refs

  15. Preparation of Long Term Operation in Dukovany NPP, Czech Republic

    International Nuclear Information System (INIS)

    Krivanek, R.; Sabata, M.

    2012-01-01

    Dukovany NPP in the south-east of the Czech Republic operates four VVER 440/213 type units. The first unit was commissioned in 1985 and the last one in 1987. The operational results of the whole NPP have been excellent and NPP permanently belongs between the first quartile of the best operated NPPs in the world in accordance with WANO factors. Large safety improvement programme have been implemented in last 15 years. The original design lifetime of main components is 30 years which means till 2015 and it is understandable that NPP is preparing for long-term operation (LTO). The paper is describing activities carried out and planned for safe and successful LTO. (author)

  16. Low-water considerations for NPP sites

    International Nuclear Information System (INIS)

    Jensen, J.; Frank, T.; Wahl, T.

    2009-01-01

    In the frame of reactor safety considerations flood protection and the evaluation of low-water events are safety relevant issues. Therefore low-water statistics were performed for the coastal region Cuxhaven and the Elbe river estuary. The consideration of the longitudinal profile of water levels during low-tide in connection with surface water effects, morphodynamic changes of the river and anthropogenic modifications is of importance for conclusions concerning the NPP sites in some distance of the reference tide gauge. The authors performed a statistical low-tide analysis for the NPP sites Brunsbuettel and Brokdorf.

  17. NPP Krsko natural circulation performance evaluation

    International Nuclear Information System (INIS)

    Segon, Velimir; Bajs, Tomislav; Frogheri, Monica

    1999-01-01

    The present document deals with an evaluation of the natural circulation performance of the Krsko nuclear power plant. Two calculation have been performed using the NPP Krsko nodalization (both similar to the LOBI A2-77 natural circulation experiment) - the first with the present steam generators at NPP Krsko (Westinghouse, 18% plugged), the second with the future steam generators (Siemens, 0% plugged). The results were evaluated using the natural circulation flow map derived in /1/, and were compared to evaluate the influence of the new steam generators on the natural circulation performance. (author)

  18. SAT-based personnel training for nuclear power plants. Proceedings of a seminar jointly organized under the technical cooperation programme (UKR/4/003) by the International Atomic Energy Agency, Goskomatom of Ukraine, South-Ukrainian NPP and held in Yuzhnoukrainsk, Ukraine, 10-14 April 1995. Working material

    International Nuclear Information System (INIS)

    1995-01-01

    In 1995 the IAEA technical co-operation project ''Training for Safe Operation and Management of Nuclear Power Plants'' (UKR/4/003) has been started with the main goal to improve training systems and training infrastructures to ensure safe and reliable operation of nuclear power plants. As the first step of the project implementation, a seminar on introducing the Systematic Approach to Training for NPP personnel was recommended by the IAEA and G-24 mission on training as one of the primary training needs and priorities of Ukraine. The Seminar was held at the South-Ukrainian Nuclear Power Plant (SUNPP), Yuzhnoukrainsk, Ukraine from 10 to 13 April 1995 and was attended by 35 representatives from GOSKOMATOM, Ministry for Environment Protection and Nuclear Safety, OGPU, and all NPPs of Ukraine

  19. Pressure control modernization for DO2 supply system of the fuel machine

    International Nuclear Information System (INIS)

    Ionescu, T.; Burla, I.; Vasilache, V.

    2005-01-01

    Full text: The analog controllers of the D 2 O Supply System (BSI-35260) were replaced at Cernavoda NPP U1 with a modern solution built on a new platform with powerful Fischer and Porter controllers. During two years of operating experience this new solution demonstrated its capabilities to work without any fault. This paper describes briefly the involved system, the hardware and software aspects of this solution, how the software solution was tested using the Full-Scope Simulator facilities and finally, results of the tests done in the real plant are discussed. (authors)

  20. Pressure control modernization for D2O supply system of the fuel machine

    International Nuclear Information System (INIS)

    Ionescu, T.; Burla, I.; Vasilache, V.

    2005-01-01

    The analog controllers of the D 2 O Supply System (BSI-35260) were replaced at Cernavoda NPP U1 with a modern solution built on a new platform with powerful Fischer and Porter controllers. During two years of operating experience this new solution demonstrated its capabilities to work without any fault. This paper describes briefly the involved system, the hardware and software aspects of this solution, how the software solution was tested using the Full-Scope Simulator facilities and finally, results of the tests done in the real plant are discussed. (authors)

  1. Integrated electronic device for processing impulses from neutron detectors

    International Nuclear Information System (INIS)

    Stoica, Mihai; Pirvu, Ion

    2009-01-01

    The developing of nuclear power is a key factor in decreasing energy Romania's dependence on imports of fossil fuels (oil, natural gas). An important point in achieving this goal is to use the experience acquired in the design and use of the equipment produced with the participation of INR specialists for Cernavoda NPP, Units 1 and 2. The design based on Surface Mount Technology (SMT) and the implementation of electronic interface modules of computer processing and detectors of radiation or nuclear particles contribute both to modernize and increase the performance of equipment. (authors)

  2. 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)

  3. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models, we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station, Chinese Academy of Sciences in subtropical China. In addition, canopy layer and community NPP were calcu- lated based on 12 years’ litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community biomass was 10574 g·m-2; its distribution patterns in tree layer, shrub layer, herbaceous layer, tree root, herbaceous and shrub roots and fine roots were 7542, 480, 239, 1810, 230, 274 and 239 g·m-2, respectively. From 1999 to 2004, the average annual growth rate and litter fall were 741 g·m-2·a-1 (381.31 gC·m-2·a-1) and 849 g·m?2·a?1 (463 gC·m-2·a-1), respectively. There was a significant corre- lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005, average NPP and GPP values based on BGC modeling were 630.88 (343.31 - 906.42 gC·m-2·a-1) and 1 800 gC·m-2·a-1 (1351.62 - 2318.26 gC·m-2·a-1). Regression analysis showed a linear relationship (R2=0.48) between the measured and simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP, while NEP ac- counted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respi- ration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  4. Main directions of Chernobyl training centre activity in conditions of its shut-down

    International Nuclear Information System (INIS)

    Duda, V.

    2002-01-01

    Plan for training centre creation for advanced personnel training in nuclear object decommission and realization of works at 'Ukrytie' is developed. It includes the first stage of works (as ChNPP department) and final (one as self-supporting enterprise)

  5. Actual status of project Mochovce NPP units 3 and 4 completion

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In this presentation author deals with actual status of project Mochovce NPP units 3 and 4 completion. Present state of Mochovce NPP, Units 3 and 4 enables real assumption to completion. It is expected that such supplier companies can be used which are experienced in field of nuclear projects. Based on budget of 2002, it seems that completion costs of 45 billions SKK are real. These figures were confirmed by study performed by TRACTEBEL in 2004. Based on experience from Bohunice NPP completion as well as from Mochovce NPP, Units 1 and 2 completion and if decision milestone and project start up deadlines will be observed according to modified preliminary schedule of Mochovce NPP Units 3 and 4 completion, it seems as real that Unit 3 will be completed till 06/2011 and Unit 4 - till 12/2011.

  6. Review of accident analyses performed at Mochovce NPP

    International Nuclear Information System (INIS)

    Siko, D.

    2000-01-01

    In this paper the review of accident analysis performed in NPP Mochovce V-1 is presented. The scope of these safety measures was defined and development in the T SSM for NPP Mochovce Nuclear Safety Improvements Report' issued in July 1995. The main objectives of these safety measures were the followings: (a) to establish the criteria for selection and classification of accidental events, as well as defining the list of initiating events to be analysed. Accident classification to the individual groups must be performed in accordance with RG 1.70 and IAEA recommendations 'Guidelines for Accidental Analysis of WWER NPP' (IAEA-EBR-WWER-01) to select boundary cases to be calculated from the scope of initiating events; (b ) to elaborate the accident analysis methodology that also includes acceptance criteria for their result evaluation, initial and boundary conditions, assumption related with the application of the single failure criteria, requirements on the analysis quality, used computer codes, as well as NPP models and input data for the accident analysis; (c) to perform the accident analysis for the Pre-operational Safety Report (POSAR); (d) to provide a synthetic report addressing the validity range of codes models and correlations, the assessment against relevant tests results, the evidence of the user qualification, the modernisation and nodding scheme for the plant and the justification of used computer codes. Analyses results showed that all acceptance criteria were met with satisfactory margin and design of the NPP Mochovce is accurate. (author)

  7. The Bohunice NPP V-1 units nuclear safety upgrading

    International Nuclear Information System (INIS)

    Mlcuch, M.

    2000-01-01

    Safety upgrading and operational reliability improvement was carried out by the Bohunice NPP V-1 staff continuously since the plant commissioning. By now, more than 1200 minor or major modifications have been implemented, either by the NPP maintenance staff or by the contractors. Based on findings of safety assessment missions invited by Bohunice NPP in 1990 - 1991, the Czecho-slovak Nuclear Regulatory Authority (CSKAE) issued the decision No. 5/91 of 81 safety upgrading measures to be taken in different areas. These improvements are referred to as the 'Small Reconstruction of the Bohunice V-1 NPP'. Realization of measures during Small reconstruction of the Bohunice NPP V-1 became a power plant, which further operation is acceptable from safety point of view, but it is also necessary further safety improvement. During the period of the Small Reconstruction the development of a Safety Report for the Gradual reconstruction has been completed. Based on this report the SR Nuclear Regulatory Authority issued the Decision No. 1/94, in which requires 59 upgrading measures in different areas to be addressed. The development of Basic Engineering of the Gradual Reconstruction has been contracted to the Siemens AG. Implementation of safety measures are provided through contract with the consortium REKON (which consists of Siemens AG company and Nuclear Power Plants Research Institute Trnava) and other Czech, Russian and Slovak companies. The Gradual Reconstruction of Bohunice NPP V-1 will be finished in 2000. By implementation of the measures carried out during Gradual Reconstruction achievement of an internationally acceptable nuclear safety level will be reached. (author)

  8. To the problem of reliability standardization in computer-aided manufacturing at NPP units

    International Nuclear Information System (INIS)

    Yastrebenetskij, M.A.; Shvyryaev, Yu.V.; Spektor, L.I.; Nikonenko, I.V.

    1989-01-01

    The problems of reliability standardization in computer-aided manufacturing of NPP units considering the following approaches: computer-aided manufacturing of NPP units as a part of automated technological complex; computer-aided manufacturing of NPP units as multi-functional system, are analyzed. Selection of the composition of reliability indeces for computer-aided manufacturing of NPP units for each of the approaches considered is substantiated

  9. 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

  10. The final report of the state scientific programme 'Ignalina NPP and the Environment'

    International Nuclear Information System (INIS)

    1998-03-01

    The final report of the State Scientific Programme 'Ignalina NPP and the Environment' includes the generalised research material on the after effects of Ignalina NPP operation upon natural environment and social processes. The data on changes of thermal state and water balance of lake Drukshiai; the effect of permanent thermal and chemical pollution on the water chemical composition and hydrochemical regime; the geochemical - contaminated state; the condition, dynamics and changes of hydrobiont communities in lake Drukshiai; the bio indication of ecological effects; the toxic and genotoxic influence of Ignalina NPP waste waters and lake Drukshiai water as well as bottom sediments; the state and dynamic of landscape ecosystem components of Ignalina NPP region; the radionuclides in Ignalina NPP area, the medical and biological studies in the Ignalina NPP influence population zone; the impact of Ignalina NPP on social territorial processes in the region are presented. Radioecological and ecotoxilogical state of Ignalina NPP region and lake Drukshiai is estimated as well as changes in lake Drukshiai and Ignalina NPP surrounding area ecosystems under the combine anthropogenic of the plant influence are elucidated. The final report contains the results of final report by the executors of the tasks and themes of the Programme which have been obtained since the beginning of the implementation of the Programme as well as generalising conclusions and recommendations. (author)

  11. Nuclear fuel operation at Balakovo NPP

    International Nuclear Information System (INIS)

    Morozov, A.

    2015-01-01

    The presentation addressed the positive experience of the TVS-2M assemblies implementation at Balakovo NPP in 18 month fuel cycles, at uprated power (104%) and the usage of the axial profiled Gd-rods in order to minimize the power peaking factors and linear heat rate in the upper part in some of the fuel rods. The results of the test operation of fuel rods with different claddings, made by E110M, E125 and E635M alloys at Balakovo NPP were also provided. The recently observed problem with the “white crust” on the cladding surfaces was also discussed

  12. Lifetime evaluation of Bohunice NPP components

    International Nuclear Information System (INIS)

    Kupca, L.

    2001-01-01

    The paper discuss some aspects of the main primary components lifetime evaluation program in Bohunice NPP which is performed by Nuclear Power Plant Research Institute (NPPRI) Trnava in cooperation with Bohunice and other organizations involved. Facts presented here are based on the NPPRI research report which is regularly issued after each reactor fuel campaign under conditions of project resulted from the contract between NPPRI and Bohunice NPP. For the calculations, there has been used some computer codes adapted (or made) by NPPRI and the results are just the conclusive and very brief, presented here in Tables (Figures). (authors)

  13. Safety upgrading program in NPP Mochovce

    International Nuclear Information System (INIS)

    Baumeister, P.

    1999-01-01

    EMO interest is to operate only nuclear power plants with high standards of nuclear safety. This aim EMO declare on preparation completion and commissioning of Mochovce Nuclear Power Plant. Wide co-operation of our company with International Atomic Energy Agency and west European Inst.ions and companies has been started with aim to fulfil the nuclear safety requirements for Mochovce NPP. Set of 87 safety measures was implemented at Mochovce Unit 1 and is under construction at Unit 2. Mochovce NPP approach to safety upgrading implementation is showed on chosen measures. This presentation is focused on the issues category III.(author)

  14. Experience on implementing risk-oriented in-service inspection at NPP in USA

    International Nuclear Information System (INIS)

    Grebenyuk, Yu.P.; Zaritskij, N.S.; Kovyrshin, V.G.; Kostenko, S.P.

    2001-01-01

    Experience of implementing risk-oriented in-service inspection (RIISI) of pipelines at the US NPP analyzed. RIISI processes according to the methodologies developed by Westinghouse and EPRI are described and compared. The information is addressed concerning practical matters of RIISI implementing at NPP Beaver Valley and Arkansas Nuclear One. Regulatory activity of the US NRC while implementing NRC at the US NPP. It is shown that using RIISI at NPP is aimed at improvement of examination efficiency, decreasing costs and occupational dose loads while inspecting pipelines

  15. Perspectives for utilization of the experience from the electrical equipment modernization of Kozloduy NPP units 5 and 6 in case of construction of new NPP

    International Nuclear Information System (INIS)

    Bogdanov, D.

    2005-01-01

    In 2005 a governmental decision for continue the project for construction of Belene NPP was adopted. In case of start of this significant project in short terms, a good option will be to utilize the already achieved experience by the modernization program of units 5 and 6 of Kozloduy NPP. The process of construction of new NPP is associated with significant amount of engineering, civil construction works, equipment order and delivery, installation works, testing and commissioning activities. It is vital necessity to have optimal technology, strict organization for project implementation and excellent documentation. From technical point of view the experience from the modernization of units 5 and 6 of Kozloduy NPP will be very important in case of utilization of similar types of WWER 1000 units. According to the 'Feasibility study for construction of Belene NPP', the most favorable option is to accomplish the already partially constructed Unit 1 on the basis of upgraded WWER B-320 design - WWER 1000 B-392, in order to fulfill IEC 331-3A, IEC 332-3A, and of US NRC Regulatory Guide 1.70 and to construct the second unit on the basis of ASE WWER/1000 B-466. However, for any type of unit selected, the achieved experience will be an important basis. This article is focused mostly on the modernization aspects of some electrical systems of Kozloduy NPP

  16. Evaluation of the atmospheric transport modeling tools used at the Ignalina NPP

    International Nuclear Information System (INIS)

    Jasiulionis, R.

    2004-01-01

    The atmospheric transport modeling system at the Ignalina NPP is part of the radionuclide monitoring system and is designed to help associate radionuclide network signals with possible source regions. The evaluation of the Atmospheric Transport Modeling Tools Used at the Ignalina NPP was based on results published in last years. The model based on semi-empirical formulae of turbulent diffusion in the air and local meteorological data were used for calculation of concentration of radionuclides emitted through the Ignalina NPP stack. Meteorological data (wind velocity and direction as well as temperature at a height of 2 and 30 meters) were obtained from the meteorological station of the Ignalina NPP at Visaginas. Using the Hybrid Single-Particle Lagrangian Integrated Trajectory (HYSPLIT) model, trajectories of air masses transport to the Ignalina NPP region (56.55 N, 26.57 E) during 95 hours at heights of 100, 500 and 1000 m were calculated. The dispersion in the ground-level air of emissions through the Ignalina NPP stack can also be calculated using the HYSPLIT model. The data on the radionuclide activity concentrations in the air at the measurements site and results of calculation can used for the establishment of their field in the Ignalina NPP region. (author)

  17. NPP Krsko Containment Response Following Main Steam Line Break

    International Nuclear Information System (INIS)

    Spalj, S.; Grgic, D.; Cavlina, N.

    2000-01-01

    This paper presents the calculation of thermohydraulic environmental parameters (pressure and temperature) inside containment of Krsko NPP after postulated Main Steam Line Break (MSLB) accident. This analysis was done as a part of the ambient parameters specification in the frame of the NPP Krsko Equipment Qualification (EQ) project. The RELAP5/mod2 computer code was used for the determination of MSLB mass and energy release and computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment. The analysis was performed for spectrum of break sizes to account for possible steam superheating during accidents with smaller break sizes. (author)

  18. A functional model for simulator based training in the pacific basin

    International Nuclear Information System (INIS)

    Lam, K.; MacBeth, M.J.

    1998-01-01

    According to expert estimate, the nuclear power installed capacity in the Pacific Basin region may reach 20 GWe by the year 2010. Facing a phenomenal growth in nuclear power development in the region, the development of high quality nuclear human resources for 'nuclear power ready' developing countries in the Pacific Basin is an important issue at this time. This paper recommends a timely and cost-effective functional training model to the Pacific Basin countries. The model utilizes high quality simulation executed on low cost and readily available PCs to deliver desktop simulator based training programs, as an efficient and economical complement to full scope simulators, which may not be available for initial training until five years after the NPP project has started. The objective is to ensure the goals of self-reliance and the transfer of necessary NPP knowledge at the onset of the project, to build up a technological infrastructure in areas vital for subsequent technical support of the NPP in design, commissioning, and operator training: comprehension of control systems; familiarization of plant responses to accident conditions; man machine interface (MMI) functions and interactions; early guide to commissioning and operating procedures; presentation to safety reviewers, etc. An example of this model is demonstrated with the use of the (1) CANDU 9 (CANada Deuterium Uranium 900 MW Pressurized Heavy Water Reactor) desktop nuclear simulator and (2) CASSIM (CASsiopeia SIMulation development system). (author)

  19. 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

  20. Assessment of NPP VIIRS Ocean Color Data Products: Hope and Risk

    Science.gov (United States)

    Turpie, Kevin R.; Meister, Gerhard; Eplee, Gene; Barnes, Robert A.; Franz, Bryan; Patt, Frederick S.; Robinson, Wayne d.; McClain, Charles R.

    2010-01-01

    For several years, the NASA/Goddard Space Flight Center (GSFC) NPP VIIRS Ocean Science Team (VOST) provided substantial scientific input to the NPP project regarding the use of Visible Infrared Imaging Radiometer Suite (VIIRS) to create science quality ocean color data products. This work has culminated into an assessment of the NPP project and the VIIRS instrument's capability to produce science quality Ocean Color data products. The VOST concluded that many characteristics were similar to earlier instruments, including SeaWiFS or MODIS Aqua. Though instrument performance and calibration risks do exist, it was concluded that programmatic and algorithm issues dominate concerns. Keywords: NPP, VIIRS, Ocean Color, satellite remote sensing, climate data record.

  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. The local impacts of Borssele NPP closing down

    International Nuclear Information System (INIS)

    Mandos, J.L.

    2000-01-01

    The municipal council of Borsele considers that the use of nuclear energy is a question of national policy, but considers itself responsible for town and country planning, safety and employment. The two latter aspects are especially significant if plans for shutdown are concerned. Confidence in safety of the NPP in Borsele has increased in recent years due to transparent information policy of the power plant itself as well as the local government and most of the employees living in the area. If considering the circumstances under which the decision about the closure of NPP one could sees this is a purely political decision. The local government will continue the close cooperation with the National government and the Parliament in solving the problem of employment and social impact of NPP shutdown

  3. Technical innovations at NPP Dukovany - for safe and efficient operation

    International Nuclear Information System (INIS)

    Sabata, M.; Vasa, I.

    2000-01-01

    Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

  4. Current status of NPP generation IV

    International Nuclear Information System (INIS)

    Yohanes Dwi Anggoro; Dharu Dewi; Nurlaila; Arief Tris Yuliyanto

    2013-01-01

    Today development of nuclear technology has reached the stage of research and development of Generation IV nuclear power plants (advanced reactor systems) which is an innovative development from the previous generation of nuclear power plants. There are six types of power generation IV reactors, namely: Very High Temperature Reactor (VHTR), Sodium-cooled Fast Reactor (SFR), Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), and Super Critical Water-cooled Reactor (SCWR). The purpose of this study is to know the development of Generation IV nuclear power plants that have been done by the thirteen countries that are members of the Gen IV International Forum (GIF). The method used is review study and refers to various studies related to the current status of research and development of generation IV nuclear power. The result of this study showed that the systems and technology on Generation IV nuclear power plants offer significant advances in sustainability, safety and reliability, economics, and proliferation resistance and physical protection. In addition, based on the research and development experience is estimated that: SFR can be used optimally in 2015, VHTR in 2020, while NPP types GFR, LFR, MSR, and SCWR in 2025. Utilization of NPP generation IV said to be optimal if fulfill the goal of NPP generation IV, such as: capable to generate energy sustainability and promote long-term availability of nuclear fuel, minimize nuclear waste and reduce the long term stewardship burden, has an advantage in the field of safety and reliability compared to the previous generation of NPP and VHTR technology have a good prospects in Indonesia. (author)

  5. 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)

  6. Regulatory activities in gaining assurance of training program effectiveness in Canada

    International Nuclear Information System (INIS)

    Legare, Michele

    2003-01-01

    This presentation shows the regulator's point of view on evaluating a training program effectiveness. The mission of the Training Program Evaluation Section of the Canadian Atomic Energy Control Board is to obtain and document assurance that the training of NPP operators is effective in providing them with the knowledge and skills needed to become and remain competent. Proposals are made to be considered when drafting the IAEA guideline on evaluation of training program effectiveness

  7. 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)

  8. Two CANDU fueling machines tested at the Institute For Nuclear Research - Pitesti

    International Nuclear Information System (INIS)

    Doca, Cezar; Cojocaru, Virgil

    2005-01-01

    In 2003, as a national and European premiere, at the Institute for Nuclear Research Pitesti (INR), the Fueling Machine Head no.4 (F/M) for the Nuclear Power Plant Cernavoda - Unit 2 was successfully tested. In 2005, a second Fueling Machine (no.5) was tested for the Nuclear Power Plant Cernavoda - Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate in Romania the CANDU technology. To perform the tests of these machines at INR Pitesti, a special testing rig was built and is available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing operation. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any other CANDU Reactor owner. This experience will support the next steps concerning F/M commissioning in the NPP Cernavoda - Unit 2 and also give the confidence to the end-users that the Institute's team can provide technical assistance during the operation. Also, the obtained results demonstrate that the overall refurbishment of the F/M control system in Unit 1 and Unit 2 will be possible. The paper presents: - a short description of the F/M head;- a short description of the F/M test rig; - the computer control system; - the F/M testing activities; -results and expectations. (authors)

  9. Two CANDU fueling machines tested at the Institute For Nuclear Research - Pitesti

    International Nuclear Information System (INIS)

    Doca, C.; Cojocaru, V.

    2005-01-01

    Full text: In 2003, as a national and European premiere, at the Institute for Nuclear Research Pitesti (INR), the Fueling Machine Head no.4 (F/M) for the Nuclear Power Plant Cernavoda - Unit 2 was successfully tested. In 2005, a second Fueling Machine (no.5) was tested for the Nuclear Power Plant Cernavoda - Unit 2. The Institute's main objective is to develop scientific and technological support for the Romanian Nuclear Power Program. Testing the Fueling Machines at INR Pitesti is part of the overall program to assimilate in Romania the CANDU technology. To perform the tests of these machines at INR Pitesti, a special testing rig was built and is available for this goal. Both the testing rig and staff had successfully assessed by the AECL representatives during two missions. There was a delivery contract between GEC Canada and Nuclear Power Plant Cernavoda - Unit 2 to provide the Fueling Machines no. 4 and no. 5 in Romania before testing operation. As a first conclusion, the Institute for Nuclear Research Pitesti has the facilities, the staff and the experience to perform possible co-operations with any other CANDU Reactor owner. This experience will support the next steps concerning F/M commissioning in the NPP Cernavoda - Unit 2 and also give the confidence to the end-users that the Institute's team can provide technical assistance during the operation. Also, the obtained results demonstrate that the overall refurbishment of the F/M control system in Unit 1 and Unit 2 will be possible. The paper presents: - a short description of the F/M head;- a short description of the F/M test rig; - the computer control system; - the F/M testing activities; -results and expectations. (authors)

  10. Medical consequences of NPP and TPP operation

    International Nuclear Information System (INIS)

    Bliznakov, V.

    1996-01-01

    Results from a comparative analysis of health conditions of the staff in the Kozloduy NPP and the Maritsa Iztok TPP are reported. It is found that the general disease incidence with temporary incapacity for work of Kozloduy workers is lower than those data for the workers at thermal power stations. The incidence of some social diseases like neoplasms, TBC, hypertension, ischemia etc. is also lower for the staff of NPP. No cases of radiation injuries have been registered for a period of 21 years

  11. NPP Krsko Living PSA Concept

    International Nuclear Information System (INIS)

    Vrbanic, I.; Spiler, J.

    2000-01-01

    NPP Krsko developed PSA model of internal and external initiators within the frame of the Individual Plant Examination (IPE) project. Within this project PSA model was used to examine the existing plant design features. In order to continue with use of this PSA model upon the completion of IPE in various risk-informed applications in support of plant operation and evaluations of design changes, an appropriate living PSA concept needed to be defined. The Living PSA concept is in NPP Krsko considered as being a set of activities pursued in order to update existing PSA model in a manner that it appropriately represents the plant design, operation practice and history. Only a PSA model which is being updated in this manner can serve as a platform for plant-specific risk informed applications. The NPP Krsko living PSA concept is based on the following major ponts. First, the baseline PSA model is defined, which is to be maintained and updated and which is to be reference point for any risk-informed application. Second, issues having a potential for impact on baseline PSA model are identified and procedure and responsibilities for their permanent monitoring and evaluation are established. Third, manner is defined in which consequential changes to baseline PSA model are implemented and controlled, together with associated responsibilities. Finally, the process is defined by which the existing version of baseline PSA model is superseded by a new one. Each time a new version of baseline PSA model is released, it would be re-quantified and the results evaluated and interpreted. By documenting these re-quantifications and evaluations of results in a sequence, the track is being kept of changes in long-term averaged risk perspective, represented by long-term averaged frequencies of core damage and pre-defined release categories. These major topics of NPP Krsko living PSA concept are presented and discussed in the paper. (author)

  12. NPP Krsko small break LOCA analysis

    International Nuclear Information System (INIS)

    Mavko, B.; Petelin, S.; Peterlin, G.

    1987-01-01

    Parametric analysis of small break loss of coolant accident for the Krsko NPP was calculated by using RELAP5/MOD1 computer code. The model that was used in our calculations has been improved over several years and was previously tested in simulation (s) of start-up tests and known NPP Krsko transients. In our calculations we modelled automatic actions initiated by control, safety and protection systems. We also modelled the required operator actions as specified in emergency operating instructions. In small-break LOCA calculations, we varied break sizes in the cold leg. The influence of steam generator tube plugging on small break LOCA accidents was also analysed. (author)

  13. Grassland Npp Monitoring Based on Multi-Source Remote Sensing Data Fusion

    Science.gov (United States)

    Cai, Y. R.; Zheng, J. H.; Du, M. J.; Mu, C.; Peng, J.

    2018-04-01

    Vegetation is an important part of the terrestrial ecosystem. It plays an important role in the energy and material exchange of the ground-atmosphere system and is a key part of the global carbon cycle process.Climate change has an important influence on the carbon cycle of terrestrial ecosystems. Net Primary Productivity (Net Primary Productivity)is an important parameter for evaluating global terrestrial ecosystems. For the Xinjiang region, the study of grassland NPP has gradually become a hot issue in the ecological environment.Increasing the estimation accuracy of NPP is of great significance to the development of the ecosystem in Xinjiang. Based on the third-generation GIMMS AVHRR NDVI global vegetation dataset and the MODIS NDVI (MOD13A3) collected each month by the United States Atmospheric and Oceanic Administration (NOAA),combining the advantages of different remotely sensed datasets, this paper obtained the maximum synthesis fusion for New normalized vegetation index (NDVI) time series in 2006-2015.Analysis of Net Primary Productivity of Grassland Vegetation in Xinjiang Using Improved CASA Model The method described in this article proves the feasibility of applying data processing, and the accuracy of the NPP calculation using the fusion processed NDVI has been greatly improved. The results show that: (1) The NPP calculated from the new normalized vegetation index (NDVI) obtained from the fusion of GIMMS AVHRR NDVI and MODIS NDVI is significantly higher than the NPP calculated from these two raw data; (2) The grassland NPP in Xinjiang Interannual changes show an overall increase trend; interannual changes in NPP have a certain relationship with precipitation.

  14. 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.

  15. Retrofitting of NPP Computer systems

    International Nuclear Information System (INIS)

    Pettersen, G.

    1994-01-01

    Retrofitting of nuclear power plant control rooms is a continuing process for most utilities. This involves introducing and/or extending computer-based solutions for surveillance and control as well as improving the human-computer interface. The paper describes typical requirements when retrofitting NPP process computer systems, and focuses on the activities of Institute for energieteknikk, OECD Halden Reactor project with respect to such retrofitting, using examples from actual delivery projects. In particular, a project carried out for Forsmarksverket in Sweden comprising upgrade of the operator system in the control rooms of units 1 and 2 is described. As many of the problems of retrofitting NPP process computer systems are similar to such work in other kinds of process industries, an example from a non-nuclear application area is also given

  16. Preventive maintenance program of motorized operated valves (MOV) at Cernavoda NPP

    International Nuclear Information System (INIS)

    Groza, M.; Moldoveanu, Edy

    2001-01-01

    This is a Power Point presentation. The following objectives are addressed: A. Determine the target of MOV program; B. Define the strategy for MOV; C. Establish the MOV program execution phases; D. Identification of key parameters; E. Examples. The target of MOV program is to improve the safety by ensuring the adequacy of safety valves and the reliability of safety equipment and, subsequently, to ensure the economic operation of the plant. Consequences of MV malfunction are indicated. The strategy for MOV program development is both general, namely, to define the minimal requirements of preventive /corrective maintenance activities for all MOV's according to design/ manufacture specification and particular, namely to identify MV's specific problems and the need for increasing/decreasing the preventing maintenance tasks or frequency established in 'general' MOV program. Strategy for MOV program development implies: - Establish MOV program applicability; - Develop diagnostic strategy (define key parameters ); - Perform program for engineering review; - Establish program for preventive maintenance; - Revise procedures for operating and maintenance tests; - Dynamic evaluation of MOV. The program execution phases are listed as follows: 1. Perform risk assessment of the MOV's to determine criticality level (program applicability); 2. Collect data to fill in MOV Application Data Sheet; 3. Perform engineering review to determine functional parameters acceptable range and determine key parameters; 4. Analysis for maintenance tasks / frequencies selection and determination of implementing actions (engineer review); 5. Prepare work packages for availability confirmation; 6. Schedule and plan corrective actions or provide input to other programs; 7. Schedule and plan implementing actions in preparation for program field execution; 8. Program field implementation; 9. Program monitoring, evaluation and optimization. The criteria defining the key operational and maintenance parameters are presented. Examples are given for minimum periodic maintenance tasks as well as for mechanical inspections and I - C measurements. Diagnostic sheets are also presented

  17. Simulating the transient regime for main condensate system at Cernavoda NPP

    International Nuclear Information System (INIS)

    Nita, Iulian; Gheorghiu, Mihai; Prisecaru, Ilie; Dupleac, Daniel

    2005-01-01

    The purpose of this project is to make a Thermal Hydraulic Analysis of Main Condensate System for getting real-time answer of installation during regimes occurring during normal and abnormal operation. To obtain the analyses the MMS code was used. The boundaries of the systems analysis are extended to Main Feedwater System in order to get a realistic response of Deaerator equipment which are situated between those two systems and have entrances from both systems. In this way we made a complex analysis with main condenser and steam generators as boundaries. We obtained a model for the entire chain of condensate and feedwater preheater with interface just turbine bleed steam. From that we could reduce the number of assumptions necessary to make the analysis. The analyses consist in hydraulics and thermal hydraulics analyses, respectively. For the first case analysed are: - the nominal operation regime with main condensate pumps; - start-up regime with total circulate of condensate to condenser; - 25% MCR (Maximum Continuous Rate) regime (this regime was used in designing the condensate regulating valves at low flow; - 40% MCR regime (with circulate of some condensate flow to condenser); - operating regime of 60% MCR with one main condensate pump operating; - operating regime with auxiliary condensate pump; - operating regime with discharging a condensate flow to condensate storage tank. The thermal hydraulic analyses deal with normal and abnormal operating regimes, respectively. In the first case analysed are the following regimes: - nominal operating regime with main condensate pump operating 100% MCR; - transient regime, 100-80% MCR; - transient regime, 100-80-60% MCR with two pumps in operation and 60 % MCR with one main condensate pump in operation; - transient regime, 100-80-60-60-40 % MCR; - shut-down regime; - start-up regime from Hot zero power to rated power regime. Finally, for the abnormal operating regimes the analyses concerned: - transient regime 100-90% MCR with by-pass of LP1 (low pressure heater) and CC (Condensate Cooler); - transient regime, 100-90% MCR with by-pass of LP2 and LP3; - turbine trip; - reactor trip; - loss of two main condensate pumps. The results were compared with Heat Balance made by General Electric (turbine supplier) for several stationary regimes. (authors)

  18. Assessing the consequences in a nuclear accident scenario at Cernavoda NPP

    International Nuclear Information System (INIS)

    Margeanu, Sorin; Angelescu, Tatiana

    2004-01-01

    Having in view a possible nuclear incident, considerable planning is necessary to reduce at manageable levels the types of decisions leading to effective responses concerning the public protection. One of the most important parts of an emergency response plan is the computerized system which allows to predict the radiological impact of the accident and to provide information in a manageable and effective form for evaluating alternative countermeasure strategies in the various stages of the accident. In this paper the PC-COSYMA results for early containment failure of a CANDU reactor are presented. The deterministic health effects arising in nuclear accident situation are also presented. As source term we have used the core inventory obtained with ORIGEN computer code. The essential input parameters for PC-COSYMA computer code are also done. (authors)

  19. Training of NPP operators: OJT completes use of non replica simulator

    International Nuclear Information System (INIS)

    Billoen, G. van

    1996-01-01

    In the paper, it is discussed the contribution of a Multifunctional Optimised Scope Simulator (MOSS), to the training of nuclear power plant operators and we will explain how this tool can be integrated into a training plan including On the Job Training (OJT). Then it is analyzed to what extent OJT and MOSS based training can be complementary

  20. The Chernobyl NPP decommissioning: Current status and alternatives

    International Nuclear Information System (INIS)

    Mikolaitchouk, H.; Steinberg, N.

    1996-01-01

    After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations