WorldWideScience

Sample records for cernavoda npp training

  1. 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

  2. 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)

  3. 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

  4. 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)

  5. 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)

  6. 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

  7. 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)

  8. 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

  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. 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

  11. 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

  12. 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)

  13. 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

  14. 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.

  15. 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)

  16. 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

  17. 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)

  18. 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)

  19. 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)

  20. 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)

  1. 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

  2. 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)

  3. 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)

  4. 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)

  5. 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)

  6. 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)

  7. 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)

  8. 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)

  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. 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)

  11. 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)

  12. 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)

  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. 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)

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. 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)

  4. 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

  5. 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

  6. 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

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. 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)

  17. 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)

  18. 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)

  19. 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

  20. 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)

  1. 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)

  2. 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)

  3. 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)

  4. 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

  5. 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)

  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. 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

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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

  3. 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)

  4. 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)

  5. 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

  6. 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)

  7. 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.

  8. 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

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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)

  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. 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

  6. 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

  7. 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)

  8. 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

  9. 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)

  10. 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

  11. 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

  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. 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)

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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

  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. 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

  1. 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.)

  2. 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)

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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)

  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. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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.)

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  5. 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)

  6. 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)

  7. 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

  8. 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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  10. 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

  11. 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)

  12. 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.

  13. 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

  14. 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

  15. 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)

  16. 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)

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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)

  2. 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

  3. 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

  4. 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.)

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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)

  17. 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

  18. Use of radiation maps in a virtual training environment for NPP field operators

    Energy Technology Data Exchange (ETDEWEB)

    Nystad, Espen; Droeivoldsmo, Asgeir; Sebok, Angelia

    2002-08-15

    Virtual reality (VR) provides a useful tool for training because it offers the student direct experience with the material to be learned. In the nuclear industry, VR provides a safe method of training workers on tasks to be performed in radiation-exposed areas. VR training may be used for planning operations so they can be performed quickly and efficiently, thus reducing worker radiation doses. This study evaluated three types of radiation distribution training for the Halden Boiling Water Reactor (HBWR) hall. Two training types were presented using VR models and computerized radiation maps; the third type of training used a paper map showing the reactor hall and the radiation distribution. Participants were instructed to learn the radiation layout and practice walking along a route in the reactor hall. They were also instructed to learn to identify the location of points that they would later measure. Following training, participants in the three training groups participated in the same experimental session. During the experimental session, participants applied the skills they had acquired in training by walking through the reactor hall and performing the measuring tasks they had learned about in the training session. The VR training included a guided condition, where users were shown the path they would need to learn, and a non-guided condition, where users were relatively free to explore. These two conditions provided active (non-guided) and passive (guided) training conditions. A number of performance measures were collected, including radiation awareness, presence, usability, and objective performance measures. Participants in the VR non-guided (active learning) condition demonstrated higher radiation awareness, reported higher transfer of training, and recognized more measure points than subjects in the VR guided (passive learning) and/or map conditions. The results of this study indicate that VR can provide a useful medium for training spatial skills. The

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  20. 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

  1. 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

  2. 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

  3. Computer based training for NPP personnel (interactive communication systems and functional trainers)

    International Nuclear Information System (INIS)

    Martin, H.D.

    1987-01-01

    KWU as a manufacturer of thermal and nuclear power plants has extensive customer training obligations within its power plant contracts. In this respect KWU has gained large experience in training of personnel, in the production of training material including video tapes an in the design of simulators. KWU developed interactive communication systems (ICS) for training and retraining purposes with a personal computer operating a video disc player on which video instruction is stored. The training program is edited with the help of a self developed editing system which enables the author to easily enter his instructions into the computer. ICS enables the plant management to better monitor the performance of its personnel through computerized training results and helps to save training manpower. German NPPs differ very much from other designs with respect to a more complex and integrated reactor control system and an additional reactor limitation system. Simulators for such plants therefore have also to simulate these systems. KWU developed a Functional Trainer (FT) which is a replica of the primary system, the auxiliary systems linked to it and the associated control, limitation and protection systems including the influences of the turbine operation and control

  4. SIMULA - C a simplified PC simulation training fool developed for the initial training of NPP operations personnel

    International Nuclear Information System (INIS)

    Reuhl, R.

    1997-01-01

    During initial training of some 50 young reactor operators and shift supervisors in the last 5 years in Biblis it was found that it takes some time before trainees gain a food overview of the most important plant systems and develop a ''feeling'' of the dynamic plant behaviour which is an important prerequisite for the first full-scope simulator training courses. To enhance this, a PC software training tool was developed SIMULA - C. (author)

  5. 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

  6. 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

  7. 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.)

  8. 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)

  9. The impact of the internalisation of the decommissioning costs at Cernavoda NPP

    International Nuclear Information System (INIS)

    Metes, Mircea; Goicea, Andrei

    2004-01-01

    The 'decommissioning of the nuclear power plant' means to release the site where a nuclear installation has been operated in such manner that this site could be further used, without any restriction, by the present or future generations. This is an important and complex requirement related to sustainable development. The decommissioning is a complicated and costly process; therefore it is imperative to start its preparation as early as possible, to ensure the creation of the necessary financial resources and to carefully schedule all the phases to be performed after the plant's permanently shutdown. The paper presents different possible strategies for the decommissioning, recommended by the International Atomic Energy Agency-Vienna, as well as some elements of the decommissioning experience acquired in the world. Special attention is given to the issue of the financial resources which must be provided by the nuclear power plant, during its operational life, with the corresponding impact on the cost of the electrical energy delivered by the plant. The practice of the internalization of the decommissioning costs is worldwide accepted; it is an approach specific to nuclear sector, proving once more its compatibility with the environmental protection and sustainable development. The sustainable development consists in such solutions that are able to satisfy the needs of the present generation without hampering the ability of the future generations to satisfy their own needs. In the nuclear energy sector, sustainability is provided by the following specific features: (1) Nuclear energy was and shall be in the future an important factor in security of energy supply. Due to the availability of the primary energy resources (fissile and fertile materials), nuclear electricity is and shall be accessible at affordable price on a permanent and reliable basis. (2) Nuclear energy as a part of the energy mix can diminish non-renewable energy consumption, prevent the exhaustion of fossil energy resources and minimise long-term impacts of the energy industry on climate change. (3) Nuclear industry is committed to minimising environmental impacts, including the safe management of the radioactive wastes and spent fuel up to the final disposal, ensuring the safety and complying with social welfare. In this respect, all nuclear companies are committed to leave clean sites after permanently shutdown of the nuclear plants

  10. 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

  11. 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)

  12. Successful factors to a better maintenance effectiveness in Cernavoda NPP 's Unit 1

    International Nuclear Information System (INIS)

    Riedel, M.; Bigu, D.

    2001-01-01

    Two tables are presented titled 'Existing maintenance-specific and maintenance-related plant programs' and 'New programs intended to be developed', respectively. In the first table the following items are indicated and commented: 1. Corrective maintenance program; 2. EQ Program; 3. Equipment maintenance history program; 4. In service inspection program; 5. Lube oil analysis program; 6. MOVs program; 7. Operational test procedures; 8. Performance evaluation program; 9. Preventive maintenance program; 10. Spares management program; 11. Vibration monitoring program. In table 2 the following items are indicated and commented: 1. Check Valves program; 2. Electrical Cable Diagnostics; 3. Erosion-corrosion; 4. Temperature monitoring (infra red thermography; noncontact thermometer); 5. Airborne Ultrasound Detection program; 6. PdM Program. A flowchart is presented in figure 1 showing the maintenance strategies' selection. In figure 2 there is presented a flowchart showing the plants maintenance current approach. Finally, in figure 3 the station maintenance program is presented in a diagram structured on the following fields: concepts, requirements, strategies, specific programs and plans

  13. 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)

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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%

  19. 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

  20. National autonomous university of Mexico RELAP/SCDAPSIM-based plant simulation and training applications to the Laguna Verde NPP

    International Nuclear Information System (INIS)

    Chavez-Mercado, C.; Hohorst, J.K.; Allison, C.M.

    2004-01-01

    The RELAP/SCDAPSIM code, designed to predict the behavior of reactor systems during normal and accident conditions, is being developed by Innovative Systems Software as part of the International SCDAP Development and Training Program (SDTP). This code is being used as the simulator engine for the National Autonomous University of Mexico's Simulation and Training Facility located at the Campus Morelos in Jiutepec, Mexico. This paper describes the RELAP/SCDAPSIM code, the Simulation and Training facility at the National Autonomous University of Mexico, and the application of the training system to the Laguna Verde Nuclear Power Plant located in the Mexican state of Veracruz. (author)

  1. 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.

  2. 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.

  3. Experiences on implementation of on-the-job training programmes for maintenance personnel in Asco and Vandellos II NPP

    International Nuclear Information System (INIS)

    Gonzalez Anez, F.

    2002-01-01

    This paper presents a process and methodology for definition and implementation of On-Job-Training Programmes (OJTP) for new maintenance personnel in Asco and Vandellos II. The content of these OJTP has been defined for each maintenance job position. A simplified task analysis was carried out to specify common and specific training. Generally, the specific maintenance training programs includes training modules in classroom and workshop environment on (1) maintenance of components and (2) maintenance fundamentals of mechanical, electrical and instrumentation. This specific training has been finally completed with a OJT programme based on the execution, observation or/and discussion about the main maintenance activities under entitled worker supervision. Each lesson, task or activity is defined in a format where the training objective, milestones and deliverables are specified. The list of activities makes up the OJTP. It is based on applicable plant procedures and maintenance instruction to each job position. Several participants or actors have been defined to implement the OJTP: co-ordinator of the process, tutors for each OJT task, line maintenance manager and trainee. Co-ordinator is the link among all actors. He knows the OJTP scope and plans the training activities according to the line maintenance manager. Co-ordinator carries out a tracking process, informs to training and maintenance managers about the progress in the programme, elaborates the progress and final reports and keeps training records. Tutors, usually entitled workers in the job position, transfer the knowledge to the trainee and discuss, review and assess the trainee's performance. Trainee carries out the scheduled tasks, keeps records of work done, prepares deliverables and informs about his activities to the Co-ordinator. The OJT programme for each new maintenance worker starts with a launching meeting with all involved actors. The goals of this meeting are to explain the OJTP scope and

  4. Organizational aspects of recruiting, training, maintaining the level of professional skills and retraining of NPP operations personnel in Russia

    International Nuclear Information System (INIS)

    Veltchinsky, V.

    1993-01-01

    The organization of personnel work during WWER-1000 operation is presented as recommended by the Russian operating organization. The system is described of recruiting, training control of professional activities, maintaining of professional skills and retraining of the Russian nuclear power plant operation personnel (PKPO system). The basic documentation of the PKPO system is listed. (Z.S.) 1 fig

  5. Operational Readiness Verification, Phase 3. A Field Study at a Swedish NPP during a Productive Outage (Safety-train Outage)

    International Nuclear Information System (INIS)

    Hollnagel, Erik; Gauthereau, Vincent; Persson, Bodil

    2004-01-01

    This report describes the results from Phase III of a study on Operational Readiness Verification (ORV) that was carried out from December 2002 to November 2003. The work comprised a field study of ORV activities at a Swedish NPP during a planned productive outage [subavstaellning], which allowed empirical work to be conducted in an appropriate environment with good accessibility to technical staff. One conclusion from Phase I of this project was the need to look more closely at the differences between three levels or types of tests that occur in ORV: object (component) test, system level test and (safety) function test, and to analyse the different steps of testing in order to understand the nontrivial relations between tests and safety. A second conclusion was the need to take a closer look at the organisation's ability to improvise in the sense of adjusting pre-defined plans to the actual conditions under which they are to be carried out. Phase II of the project found that although all three types of test occurred, they were rather used according to need rather than to a predefined arrangement or procedure. The complexity of ORV could be understood and described by using the concepts of Community of Practice, embedding, and Efficiency-Thoroughness Trade-Off. In addition, organisation and the different communities of practice improvise by adjusting pre-defined plans or work orders to the existing conditions. Such improvisations take place both on the levels of individual actions, on the level of communities of practice, and on the organisational level. The ability to improvise is practically a necessity for work to be carried out, but is also a potential risk. Phase III of the project studied how tasks are adapted relative to the different types of embedding and the degree of correspondence between nominal and actual ORV. It also looked further at the different Communities of Practice that are part of maintenance and ORV, focusing on the coordination and

  6. Operational Readiness Verification, Phase 3. A Field Study at a Swedish NPP during a Productive Outage (Safety-train Outage)

    Energy Technology Data Exchange (ETDEWEB)

    Hollnagel, Erik [Linkoeping Univ. (Sweden). Dept. of Computer and Information Science; Gauthereau, Vincent; Persson, Bodil [Linkoeping Univ. (Sweden). Dept. of Industrial Engineering

    2004-01-01

    This report describes the results from Phase III of a study on Operational Readiness Verification (ORV) that was carried out from December 2002 to November 2003. The work comprised a field study of ORV activities at a Swedish NPP during a planned productive outage, which allowed empirical work to be conducted in an appropriate environment with good accessibility to technical staff. One conclusion from Phase I of this project was the need to look more closely at the differences between three levels or types of tests that occur in ORV: object (component) test, system level test and (safety) function test, and to analyse the different steps of testing in order to understand the nontrivial relations between tests and safety. A second conclusion was the need to take a closer look at the organisation's ability to improvise in the sense of adjusting pre-defined plans to the actual conditions under which they are to be carried out. Phase II of the project found that although all three types of test occurred, they were rather used according to need rather than to a predefined arrangement or procedure. The complexity of ORV could be understood and described by using the concepts of Community of Practice, embedding, and Efficiency-Thoroughness Trade-Off. In addition, organisation and the different communities of practice improvise by adjusting pre-defined plans or work orders to the existing conditions. Such improvisations take place both on the levels of individual actions, on the level of communities of practice, and on the organisational level. The ability to improvise is practically a necessity for work to be carried out, but is also a potential risk. Phase III of the project studied how tasks are adapted relative to the different types of embedding and the degree of correspondence between nominal and actual ORV. It also looked further at the different Communities of Practice that are part of maintenance and ORV, focusing on the coordination and communication between

  7. 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 '

  8. 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)

  9. 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

  10. 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)

  11. 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

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. 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

  17. 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)

  18. 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)

  19. 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)

  20. 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

  1. Gamma irradiation tests of concrete material recommended for storage casks of spent nuclear fuel arising from Cernavoda NPP

    International Nuclear Information System (INIS)

    Dulama, M.; Deneanu, N.; Dulama, C.; Baboescu, E.

    2001-01-01

    Considerable effort is being devoted to the Romania's Nuclear Spent Fuel and Waste Management R and D Program to develop engineered barriers for the containment of nuclear fuel waste under conditions of deep geological disposal. Engineering practice suggests that the concrete should fulfil the requirements of long term physical stability and resistance to radiation. With an appropriate system of metal reinforcement, it should be possible to obtain the tensile and impact strength required, avoiding the risk of mechanical damage during handling and emplacement. In accordance with the concept developed by CITON-Bucharest, presently, the dry storage of spent nuclear fuel is thought by two choices: - The alternative of dry storage type MMB3; - The alternative of dry storage type TRANSTOR. By using ORIGEN and PELSHIE computer codes, we evaluated the gamma radiation dose absorbed by the concrete walls of the storage vault both in MMB3 and in TRANSTOR designing variants. The irradiation tests were performed at the Gamma Irradiation Facility of the Institute for Nuclear Research. (authors)

  2. Thermal-hydraulic analyses of the recirculated cooling water from cernavoda n.p.p. unit 1

    International Nuclear Information System (INIS)

    Pancef, R.; Anghel, N.; Nita, I. P.

    2013-01-01

    The paper presents the results from a very complex and large analysis performed for the Recirculated Cooling Water System. The analysis was required in order to increase the flow rate for moderator heat exchangers and introduction of a new consumer: urban heating. The system capability to supply with cooling agent all this consumers at all operating regimes from the design manual of the system had to be checked. One concluded that the required modification to the system had no influence in operating the system in all operating condition but there is an issue is regarding the necessity to recalculate the heat load from the moderator heater. The analysis was calibrated by using measurements from the plant, which have been obtained with ultrasonic flowmeters and local indicators. The analysis concludes that the system can change the requirements to the moderator heat exchangers and a new turbine building consumer (urban heating) can be introduced. (authors)

  3. 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

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. 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)

  9. Temelin NPP commissioning experiences

    International Nuclear Information System (INIS)

    Hanus, V.

    2002-01-01

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

  10. Dukovany NPP maintenance management

    International Nuclear Information System (INIS)

    Siegel, F.

    2005-01-01

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

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

  1. Dukovany NPP operation

    International Nuclear Information System (INIS)

    Vlcek, Jaroslav

    2010-01-01

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

  2. 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

  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. 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)

  5. 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)

  6. 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

  7. 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

  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. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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

  15. 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.

  16. Workflow in Almaraz NPP

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  17. Shock absorber in Ignalina NPP

    International Nuclear Information System (INIS)

    Bulavas, A.; Muralis, J.

    1996-09-01

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

  18. 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.

  19. 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

  20. 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)

  1. 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

  2. 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

  3. Development status of the cryogenic distillation system in Cernavoda Tritium Removal Facility

    International Nuclear Information System (INIS)

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

    2009-01-01

    Full text: The reference design technology for the heavy water detritiation plant of Cernavoda CANDU station is based on combination of Liquid Phase Catalytic Exchange (LPCE) and Cryogenic Distillation (CD) processes. Based on this technology, tritium is transferred from the heavy water to a deuterium stream in the catalyzed isotopic exchange process, LPCE, followed by a final enrichment within the cryogenic distillation cascade. The final step is the tritium storage on metallic hydride. The basic function of the Cryogenic Distillation System (CDS) is the separation of tritium from the tritiated deuterium coming from the LPCE column in the following conditions: - the final product has to be tritium with a concentration of at least 99%; - it must be provided a detritiation factor of at least 100 (the ration between the tritium concentration in the deuterium stream fed to the CD system and the tritium concentration in the returned stream to the LPCE); - the deuterium must be enriched up to 99.995%, by removing the protium; - provisions for safe discharge of the entire inventory of the CD cascade into buffer vessels shall be implemented. To summarize, the present status of the project consists of technical documentation for all the components of CDS, including the P and ID (Pipping and Instrumentation Diagram), preliminary data sheets, technical specifications, drawings for the major components as the buffer vessels, coldbox, etc, and 3D models as well for almost all the components. (authors)

  4. 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)

  5. 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

  6. 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)

  7. 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

  8. 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

  9. 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

  10. 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

  11. Safety culture at Mochovce NPP

    International Nuclear Information System (INIS)

    Markus, Jozef; Feik, Karol

    2002-01-01

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

  12. 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

  13. 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)

  14. Cernavoda Unit 2: - BOP 3D model proposal for a possible organization of site activities

    International Nuclear Information System (INIS)

    Ghiesura, G.; Scarsin, Sioli; Orlandi, S.

    1999-01-01

    The scope of this activity is to define characteristics and advantages of the 3D model of Cernavoda BOP to this set up at site for engineering and construction activities. This model will provide a modern and proven tool able to strongly support the site activities with particular regard to the following: 1. engineering activities, - plant arrangement 'double check' for resolution of clashing; - easy management of future design changes; - real time plant configuration updating as soon as any design modification is approved and integrated in the model; - preparation of high quality documentation for procurement, construction and commissioning; - prompt availability of the as built configuration of the plant as soon as the last modification is frozen; 2. material procurement activities, - definition of the priorities in the construction material procurement according to the construction planning by area; - inventory list of equipment, pipes, fittings, valves, cable trays and ventilation ducts to be installed in each construction area; 3. construction activities, - definition of construction sequences, with particular reference in the congested areas, for piping cable trays (electrical and C-and-I) and ventilations ducts; - definition of piping spools by construction contractors; - follow-up of the activities in each area (i.e. construction, painting, insulation, flushing, pressure testing, etc); 4. turn-over and commissioning, - check of the progress. The success of this approach is based on the following: i) proper management of the remote workstations providing easy and reliable access to the model; ii) subdivision of the Integrated Building in construction areas, whose detail design may be allotted to Romanian organizations with multidisciplinary tasks; iii) integration in the model of the remote developed engineering in order to validate the details of the design. (authors)

  15. Simulators for NPP operators

    International Nuclear Information System (INIS)

    Yuzhakov, A.Yu.

    2010-01-01

    The author reports on the application of full-scale simulators for training and maintaining proficiency of unit control room operators that is an essential element of Russian NPPs personnel education system. The existing simulators for the unit control room operating personnel are listed. The integrated approach to developing and maintaining the training hardware is described. The integrated approach is being implemented on the basis of observance of the existing requirements to training hardware, improvement of regulations, control from a single centre responsible for the provision of support to the activities, inclusion into the plans of simulators for development of skills for operating control over equipment and systems, as well as control from local boards [ru

  16. 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

  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. Safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    1995-01-01

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

  19. Redesign of emergency water supply system by-pass line from Cernavoda NPP Unit 1 and 2 using self regulating valves

    International Nuclear Information System (INIS)

    Tenescu, Mircea; Bigu, Melania; Nita, Iulian Pavel

    2010-01-01

    In this paper one considered improving the EWS (emergency water supply system) by-pass line in order to replace current manual operated valve with an self operated valve. This change is necessary in order to reduce the human error events in operation of the system in case of a DBE (design basis earthquake). The paper describes a theoretical and practical operation of a system using self regulating flow rate valves. Basically, the elimination of a possible human error in operating a system is important for nuclear safety in case of a DBE because it makes it avoidable in normal reactor cooling systems. The paper describes checking of the functioning of this equipment in operating conditions, investigating how it responds to various operating regimes. (authors)

  20. 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

  1. ASSET experience at Paks NPP

    International Nuclear Information System (INIS)

    Szabo, I.

    1997-01-01

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

  2. 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

  3. ASSET experience at Paks NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-10-01

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

  4. 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

  5. Nuclear Fuel in Cofrentes NPP

    International Nuclear Information System (INIS)

    2002-01-01

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

  6. 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)

  7. Welding facilities for NPP assembling

    International Nuclear Information System (INIS)

    Rojtenberg, S.S.

    1987-01-01

    Recommendations concerning the choice of equipment for welding in pre-assembling work shops, in the enlarging assembling shops and at the assembling site, are given. Advanced production automatic welders and semiautomatic machines, applied during the NPP equipment assembling as well as automatic machines specially produced for welding the main reactor components and pipelines are described. Automatic and semiautomatic machine and manual welding post supply sources are considered

  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. 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

  10. 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)

  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. 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. 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

  14. Consideration for a tritium removal facility at the Cernavoda Nuclear Power Station

    International Nuclear Information System (INIS)

    2006-01-01

    Full text: A pre-feasibility study considering process options for a Tritium Removal Facility at the Cernavoda Nuclear Power Station has been completed by ICIT and AECL. Three different process options were considered. These three options differ in the front-end process used to transfer tritium from heavy water to deuterium gas. All three options use cryogenic distillation (CD) as a back end process to extract tritium from the deuterium gas stream and concentrate it into a small volume stream of pure DT or T 2 that can be immobilized on a titanium sponge. The first option for the front-end process is Liquid Phase Catalytic Exchange (LPCE). The LPCE column is used to transfer the tritium from the heavy water to a recirculating stream of deuterium gas. The separation of hydrogen isotopes takes place in the cryogenic distillation column. Tritium-depleted deuterium gas from the CD system is fed back to the LPCE column. The cryogenic distillation system concentrates the tritium into a small volume of elemental tritium for storage. Tritiated heavy water that has been purified to remove catalyst poisons is fed to the top of the LPCE column. The heavy water leaving the column is depleted in deuterium. Both existing detritiation plants built to detritiate CANDU reactors (the Darlington TRF in Canada and the Wolsung TRF in Korea) use variations of the LPCE-CD process. The second option uses electrolysis to convert tritiated heavy water into oxygen and tritiated deuterium gas. The deuterium gas is sent to the Cryogenic Distillation system to extract and concentrate the tritium. The tritium depleted deuterium gas is recombined with the electrolytic oxygen to give a tritium-depleted heavy water product. The third option uses a Combined Electrolysis and Catalytic Exchange (CECE) front end. A CECE process concentrates the tritium in the water and, using water electrolysis, converts the concentrated tritium into deuterium gas. An overhead catalytic recombiner converts the

  15. 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

  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. 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

  18. Display systems for NPP control

    International Nuclear Information System (INIS)

    Rozov, S.S.

    1988-01-01

    Main trends in development of display systems used as the means for image displaying in NPP control systems are considered. It is shown that colour display devices appear to be the most universal means for concentrated data presentation. Along with digital means the display systems provide for high-speed response, sufficient for operative control of executive mechanisms. A conclusion is drawn that further development of display systems will move towards creation of large colour fields (on reflection base or with multicolour gas-discharge elements)

  19. 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

  20. Safety culture in Ignalina NPP, regulatory view

    Energy Technology Data Exchange (ETDEWEB)

    Maksimovas, G [VATESI (Lithuania)

    1997-09-01

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

  1. Safety culture in Ignalina NPP, regulatory view

    International Nuclear Information System (INIS)

    Maksimovas, G.

    1997-01-01

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

  2. 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

  3. 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)

  4. 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).

  5. 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)

  6. 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

  7. 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

  8. Operating Experience at NPP Krsko

    International Nuclear Information System (INIS)

    Kavsek, D.; Bach, B.

    1998-01-01

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

  9. 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)

  10. 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)

  11. 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)

  12. 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

  13. On-line maintenance at Cofrentes NPP

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  14. 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.

  15. Role of PRA in new NPP projects

    International Nuclear Information System (INIS)

    Julin, A.; Sandberg, J.; Virolainen, R.

    2012-01-01

    In Finland, a plant specific, Level 1 and 2 Probabilistic Risk Analysis (PRA) is required as a prerequisite for issuing the construction license and operating license. The use of PRA in various applications and the main insights are presented. These applications include e.g. PRA support to the design of SSCs (Systems, Structures and Components), definition of pre-service and in-service inspection programs, evaluation of the safety classification of SSCs, development of procedures, training and in definition of risk informed technical specifications, periodic testing and on-line preventive maintenance programs. In addition, PRA shall be used to assess the adequacy and coverage of the phase and system commissioning programs. Also the potential risks related to commissioning tests during nuclear test phase, shall be assessed with the help of PRA. In OL3 project, risk informed approach has been applied on a large scale for the first time in the design, construction and commissioning of a new NPP unit. Pre-nuclear commissioning tests have started at OL3 site and the plant is foreseen to begin commercial operation in 2013. Decisions have been made to launch new NPP projects. Teollisuuden Voima Oyj (TVO) is planning to build a new unit (OL4) at Olkiluoto site and a new utility, Fennovoima, is planning to build one unit at one of two alternative green field sites in Northern parts of Finland. Insights from PRAs of operating NPPs have been used in the evaluation of possible new sites to ensure that the site specific concerns and environmental conditions are adequately taken into account in the design of SSCs. Although the seismic activity at the Olkiluoto site is low, a comprehensive seismic risk analysis is being conducted. Its results support the review of the deterministic seismic design. For new sites, a probabilistic seismic hazard analysis has been carried out for the determination of the design earthquake. Experiences from OL3 licensing have been utilized in the

  16. 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.

  17. 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.)

  18. Conceptual design of covering method for the proposed LILW near-surface repository at Cernavoda

    International Nuclear Information System (INIS)

    Diaconu, Daniela

    2003-01-01

    The disposal concept of the low and intermediate level (LIL) wastes resulting during NPP operation combines both the natural and engineered barriers in order to ensure the safety of the environment and population. Saligny site has been proposed for LIL waste disposal. Preliminary performance assessments indicate that the loess and clay layers are efficient natural barriers against water flow and radionuclide migration through the vadose zone to the local aquifers. At present, the studies on site characterization are concentrated on investigation of the potential factors affecting the long-term integrity of the disposal facility. This analysis showed that surface erosion by wind and water and bio-intrusion by plant roots and burrowing animals could affect the long-term disposal safety. Based on the preliminary erosion results, as well as on the high probability of bio-intrusion by the plant roots and burrowing animals (i.e. moles, mice), different covering systems able to ensure the long-term safety of the repository has been proposed and analyzed. FEHM and HYDRUS 2D water flow simulations have been performed in order to compare their efficiency in the diminution of the infiltration rate in the repository. From this point of view, the covering system combining the capillary barrier and the resistive layer proved to have the best behavior

  19. 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)

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  7. 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

  8. 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)

  9. Environmental impact assessment of NPP decommissioning

    International Nuclear Information System (INIS)

    Hinca, R.

    2009-01-01

    In this presentation the following potential impacts of decommissioning of NPP are discussed: - Impacts on population; Impacts on natural environment; Land impacts; Impacts on urban complex and land utilisation; Possible impacts on area as a result of failure.

  10. 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

  11. NPP operation and modern high technologies

    International Nuclear Information System (INIS)

    Kuznetsov, V.V.

    1992-01-01

    Examples are considered of modern high technology introduction into daily practice of NPP operation, namely: satellite communication systems, robots, non-destructive testing, optical-fiber techniques, laser measuring means and others

  12. 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)

  13. 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)

  14. Nuclear Power Plant (NPP) safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The multidisciplinary aspects of the activities involved in the nuclear power plant (NPP) licensing, are presented. The activities of CNEN's technical staff in the licensing of Angra-1 and Angra-2 power plants are shown. (E.G.) [pt

  15. Cuba: Juragua NPP. Project Control. Annex 5

    International Nuclear Information System (INIS)

    Serradet, M.A.

    1999-01-01

    This annex deals with project control. The long suspension of Juragua NPP has affected personnel, equipment and site structures. Efforts are being made to revive the plant and to protect existing resources (assets). An action plan has been prepared. (author)

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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

  1. 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

  2. Suomi NPP Ground System Performance

    Science.gov (United States)

    Grant, K. D.; Bergeron, C.

    2013-12-01

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

  3. 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)

  4. 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

  5. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias

    2013-06-01

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

  6. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias

    2013-06-01

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

  7. ORSEC technological risks, Blayais NPP

    International Nuclear Information System (INIS)

    2016-01-01

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

  8. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-06-15

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

  9. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-06-15

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

  10. 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.

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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)

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

    International Nuclear Information System (INIS)

    Gueorguiev, B.

    2002-01-01

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

  18. 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

  19. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Stuller, J.; Brandejs, P.; Miasnikov, A.; Svab, M.

    1999-01-01

    In beginning, a history of legislative process regulating industrial utilisation of nuclear energy is given, including detailed list of decrees issued by the first regulatory body supervising Czech nuclear installations - Czechoslovak Atomic Energy Commission (CSKAE). Current status of nuclear regulations and radiation protection, especially in connection with Atomic Act (Act No 18/1997 Coll.), is described. The Atomic Act transfers into the Czech legal system a number of obligations following from the Vienna Convention on Civil Liability for Nuclear Damage and Joint Protocol relating to the Application of the Vienna and Paris Convention, to which the Czech Republic had acceded. Actual duties and competence of current nuclear regulatory body - State Office for Nuclear Safety (SUJB) - are given in detail. Execution of the State supervision of peaceful utilisation of nuclear energy and ionising radiation is laid out in several articles of the Act, which comprises: control activities of the SUJB, remedial measures, penalties. Material and human resources are sufficient for fulfilment of the basic functions for which SUJB is authorised by the law. For 1998, the SUJB allotted staff of 149, approximately 2/3 of that number are nuclear safety and radiation protection inspectors. The SUJB budget for 1998 is approximately 180 million Czech crowns (roughly 6 million US dollars). Inspection activity of SUJB is carried out in three different ways: routine inspections, planned specialised inspections, inspections as a response to a certain situation (ad-hoc inspections). Approach to the licensing of major plant upgrades and backfittings are mainly illustrated on the Temelin NPP licensing. Regulatory position and practices concerning review activities are presented. (author)

  20. 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.

  1. Evaluation of the safety margins during shutdown for NPP Krsko

    International Nuclear Information System (INIS)

    Bencik, V.; Sadek, S.; Bajs, T.

    2004-01-01

    In the paper the results of RELAP5/mod3.3 calculations of critical parameters during shutdown for NPP Krsko are presented. Conservative evaluations have been performed at NPP Krsko to determine the minimum configuration of systems required for the safe shutdown operation. Critical parameters in these evaluations are defined as the time to start of the boiling and the time of the core dry-out. In order to have better insight into the available margins, the best estimate code RELAP5/mod3.3 has been used to calculate the same parameters. The analyzed transient is the loss of the Residual Heat Removal (RHR) system, which is used to remove decay heat during shutdown conditions. Several configurations that include open and closed Reactor Coolant System (RCS) were considered in the evaluation. The RELAP5/mod3.3 analysis of the loss of the RHR system has been performed for the following cases: 1) RCS closed and water solid, 2) RCS closed and partially drained, 3) Pressurizer manway open, Steam Generator (SG) U tubes partially drained, 4) Pressurizer and SG manways open, SG U tubes completely drained, 5) Pressurizer manway open, SGs drained, SG nozzle dams installed and 6) SG nozzle dams installed, pressurizer manway open, 1 inch break at RHR pump discharge in the loop with pressurizer. Both RHR trains were assumed in operation prior to start of the transient. The maximum average steady state temperature for all analyzed cases was limited to 333 K. (author)

  2. 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)

  3. 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

  4. 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

  5. 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

  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. 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

  8. 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

  9. 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

  10. 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

  11. Radioactive waste problems in the Kozloduy NPP

    International Nuclear Information System (INIS)

    Videnov, N.; Stanchev, V.

    1995-01-01

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

  12. 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)

  13. 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.

  14. Knowledge management during decommissioning of Chornobyl NPP

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  15. Radioactive waste problems in the Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  16. 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

  17. 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

  18. 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)

  19. 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)

  20. 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)

  1. 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

  2. Vandellos 1 NPP decommissioning feedback experience

    International Nuclear Information System (INIS)

    Fernandez, Rodriguez A.

    2003-01-01

    necessary to support in order to reuse and apply the model to others projects. This knowledge and experience are mostly in three areas: -Data Bases, -Basic Document and - Lessons Learned which are described. Lessons Learned are summarized in eleven conclusions: a) The dilemma about the difference between an installation in operation and a decommissioning works. A NPP in operation is an installation; a NPP in decommissioning process is an activity, this impact is fundamental from the documentary and controls points of view; b) The flexibility of the time schedule of the project. In opposition with a construction, the time schedule of a decommissioning project it possible to maintain with small delays due to the versatility of parallel tasks; c) The authorization procedure is one of the key points, before and during the process. As a new activity, decommissioning was born without specifics regulation; day by day all the actors realize that is necessary to reflect back together in order to define and establish new standards to regulate the decommissioning processes; d) The prevention of the risks on site is a topic not only related to the Protection Radiation, the conventional risks have more importance in the decommissioning tasks. The issue of the new regulation about it, impact directly in the executions of the works. The training and the information to the workers are the best corrective tool again the risks; e) Some performances or characteristics of the auxiliary systems must be taken in account in the procurement process for decommissioning, namely, the modularity, versatility of the auxiliary systems and the reuse as a way of reducing wastes and save row materials. The radiation protection is the subject concern during all the operations; Important issues of radioprotection as operational radiological history, the characterization of the materials and the environment to prevent the risk, and special care with the internal contamination of the body; g) The very big

  3. Vandellos 1 NPP decommissioning feedback experience

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Rodriguez A. [Empresa Nacional de Residuos Radioactivos, ENPRESA, Madrid (Spain)

    2003-07-01

    necessary to support in order to reuse and apply the model to others projects. This knowledge and experience are mostly in three areas: -Data Bases, -Basic Document and - Lessons Learned which are described. Lessons Learned are summarized in eleven conclusions: a) The dilemma about the difference between an installation in operation and a decommissioning works. A NPP in operation is an installation; a NPP in decommissioning process is an activity, this impact is fundamental from the documentary and controls points of view; b) The flexibility of the time schedule of the project. In opposition with a construction, the time schedule of a decommissioning project it possible to maintain with small delays due to the versatility of parallel tasks; c) The authorization procedure is one of the key points, before and during the process. As a new activity, decommissioning was born without specifics regulation; day by day all the actors realize that is necessary to reflect back together in order to define and establish new standards to regulate the decommissioning processes; d) The prevention of the risks on site is a topic not only related to the Protection Radiation, the conventional risks have more importance in the decommissioning tasks. The issue of the new regulation about it, impact directly in the executions of the works. The training and the information to the workers are the best corrective tool again the risks; e) Some performances or characteristics of the auxiliary systems must be taken in account in the procurement process for decommissioning, namely, the modularity, versatility of the auxiliary systems and the reuse as a way of reducing wastes and save row materials. The radiation protection is the subject concern during all the operations; Important issues of radioprotection as operational radiological history, the characterization of the materials and the environment to prevent the risk, and special care with the internal contamination of the body; g) The very big

  4. 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

  5. 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

  6. 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

  7. 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)

  8. 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

  9. 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.)

  10. Radioactive source management in Daya Bay NPP

    International Nuclear Information System (INIS)

    Mao Chun Yang

    2000-01-01

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

  11. Safety upgrading of Bohunice V1 NPP

    International Nuclear Information System (INIS)

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. It consist of next chapters: (1) Introductory speeches; (2) Nuclear power plant WWER 440; (3) Safety improvement; (4) Bohunice Nuclear power plants subsidiary; (5) Siemens; (6) REKON; (7) VUJE Trnava, Inc. - Engineering, Design and Research Organisation; (8) Album

  12. NPP Mochovce - a project of extraordinay significance

    International Nuclear Information System (INIS)

    Chwolik, I.; Debru, M.

    2000-01-01

    In this paper and in this presentation the reactor safety upgrading of two blocks of the NPP V-1 Bohunice, some results of participation on safety upgrading by the German-French consortium EUCOM (Framatome and Siemens-KWU) are presented. (author)

  13. External hazards considered for Paks NPP

    International Nuclear Information System (INIS)

    Kiss, Tibor

    2000-01-01

    PAKS NPP was built according to Soviet construction standards which took into account meteorological aspects but no documents for other external hazards were available. Main activities concerning earthquakes cover reevaluation of the plant site, seismic safety technological concept, improving the seismic resistance, installation of seismic monitoring and protection system, and seismic PSA

  14. Safety culture development at Daya Bay NPP

    International Nuclear Information System (INIS)

    Zhang Shanming

    2001-01-01

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

  15. Development of the NPP Kozloduy informational system

    Energy Technology Data Exchange (ETDEWEB)

    Katsarov, Y; Manchev, B [Risk Engineering Ltd., Sofia (Bulgaria)

    1996-12-31

    A unified computer system to be implemented in the Kozloduy NPP is described. It allows to generate all general indicators and documents for plant operation needed according to the national regulation and WANO Performance Indicators. The system combines multi-purpose data collection with probabilistic analysis, evaluation of the human factor and optimization of the regulated verification of the equipment. 3 refs.

  16. NPP radioactive waste processing and solidification

    International Nuclear Information System (INIS)

    Nikiforov, A.S.; Polyakov, A.S.; Zakharova, K.P.

    1983-01-01

    The problems of proce-sing NPP intermediate level- and low-level liquid radioactive wastes (LRW) are considered. Various methods are compared of LWR solidification on the base of bituminization, cement grouting and inclusion into synthetic resins. It is concluded that the considered methods ensure radioactive radionuclides effluents into open hydronetwork at the level below the sanitary, standards

  17. Biotic elements of NPP techno-ecosystem

    International Nuclear Information System (INIS)

    Protasov, A.A.; Silaeva, A.A.

    2013-01-01

    Specific features of biotic elements in the NPP techno-ecosystems were considered and compared with natural ecosystems. Relationships between biotic communities and environmental factors that are specific to the techno-ecosystems were discussed, and the problems of limitation of biological hindrances in operation of equipment, principles of hydrobiological and environmental monitoring were considered.

  18. Slovakia: Mochovce NPP. Project control. Annex 10

    International Nuclear Information System (INIS)

    Bodorik, K.

    1999-01-01

    This annex deals with project control. Mochovce NPP suffered considerable delay primarily due to lack of money. This situation was corrected and construction resumed in 1996. Throughout the 'dormant' period the plant received considerable support from the major contractors, who maintained skeleton staff at site. Significant safety and managerial improvements are being introduced and a strategic plan for the plant has been developed. (author)

  19. Development of NPP safety regulation in Russia

    International Nuclear Information System (INIS)

    Vishnevsky, Y.G.; Gutsalov, A.T.; Bukrinsky, A.M.; Gordon, B.G.

    1999-01-01

    The presentation describes the organisation scheme of Russian safety regulatory bodies, their tasks and responsibilities. Legislative and regulatory basis of NPP safety regulations rely on the federal laws: Law on the Use of Nuclear Energy and Law on Radiation Safety of the Population. Role of international cooperation and Improvement of regulatory activities in Russia are emphasised

  20. 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)

  1. 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

  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. 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)

  4. 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)

  5. 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

  6. 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)

  7. 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)

  8. 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

  9. Human errors in NPP operations

    International Nuclear Information System (INIS)

    Sheng Jufang

    1993-01-01

    Based on the operational experiences of nuclear power plants (NPPs), the importance of studying human performance problems is described. Statistical analysis on the significance or frequency of various root-causes and error-modes from a large number of human-error-related events demonstrate that the defects in operation/maintenance procedures, working place factors, communication and training practices are primary root-causes, while omission, transposition, quantitative mistake are the most frequent among the error-modes. Recommendations about domestic research on human performance problem in NPPs are suggested

  10. Modernization of the oldest Swedish NPP

    International Nuclear Information System (INIS)

    Hagberth, Ronald

    1998-01-01

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

  11. Intelligent system for accident identification in NPP

    International Nuclear Information System (INIS)

    Hernandez, J.L.

    1998-01-01

    Accidental situations in NPP are great concern for operators, the facility, regulatory bodies and the environmental. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre-operational Probabilistic safety Assessment and the Thermal hydraulic Safety Analysis of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid from the combination of the artificial intelligence techniques fuzzy logic and artificial neural networks. The system works with variables from the process of the first circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  12. Quality of Industry Support to NPP Krsko

    International Nuclear Information System (INIS)

    Nemcic, K.

    2008-01-01

    NPP Krsko developed program for Supplier evaluation and performance. During the regular control of suppliers and evaluation of industry support to NPP Krsko quality problems were reported. Different quality systems were evaluated and different suppliers as: design organizations, equipment manufacturers, material vendors were audited or surveillance was performed. This paper discuss and report various cases where quality issues were problems based on audit results and present actions and efforts undertaken by the NE Krsko Quality Assurance Department to improve performance of the contractors, vendors, suppliers. New and different quality standards as approach in numerous articles are described as improvement or quality changes but also 'different opinion exist'. This paper also presents the author view and approach how to solve the possible future problems with different quality systems and organisations used by industry who support daily operation of NE Krsko and give recommendations for future nuclear projects.(author)

  13. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  14. NPP Temelin. Status of safety improvements

    International Nuclear Information System (INIS)

    1999-01-01

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

  15. 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

  16. 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)

  17. AGNES - safety reassessment of Paks NPP

    International Nuclear Information System (INIS)

    Gado, J.

    1995-01-01

    The main goal of the AGNES (Advanced General and New Evaluation of Safety) project for the reassessment of the safety of Paks Nuclear Power Plant, Hungary, was to improve the safety culture of the technology at Paks. A report was prepared on the reassessment of the Paks NPP safety. The analysis was divided into four groups: systems analysis, analysis of design basis accidents, severe accident analysis, and level 1 probabilistic safety analysis. Proposed safety enhancement measures are discussed. (N.T.)

  18. Design safety improvements of Kozloduy NPP

    International Nuclear Information System (INIS)

    Hinovski, I.

    1999-01-01

    Design safety improvements of Kozloduy NPP, discussed in detail, are concerned with: primary circuit integrity; reactor pressure vessel integrity; primary coolant piping integrity; primary coolant overpressure protection; leak before break status; design basis accidents and transients; severe accident analysis; improvements of safety and support systems; containment/confinement leak tightness and strength; seismic safety improvements; WWER-1000 control rod insertion; upgrading and modernization of Units 5 and 6; Year 2000 problem

  19. On some methods of NPP functional diagnostics

    International Nuclear Information System (INIS)

    Babkin, N.A.

    1988-01-01

    Methods for NPP functional diagnosis, in which space and time dependences for controlled variable anomalous deviations change are used as characteristic features, are suggested. The methods are oriented for operative recognition of suddenly appearing defects and envelop quite a wide range of possible anomalous effects in an onject under diagnostics. Analysis of transients dynamic properties caused by a failure is realized according to the rules, which do not depend on the character of anomalous situation development

  20. Supercompaction of radioactive waste at NPP Krsko

    International Nuclear Information System (INIS)

    Fink, K.; Sirola, P.

    1996-01-01

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

  1. Using bentonite for NPP liquid waste treatment

    International Nuclear Information System (INIS)

    Bui Dang Hanh

    2015-01-01

    During operation, nuclear power plants (NPPs) release a large quantity of water waste containing radionuclides required treatment for protection of the radiation workers and the environment. This paper introduces processes used to treat water waste from Paks NPP in Hungary and it also presents the results of a study on the use of Vietnamese bentonite to remove radioactive Caesium from a simulated water waste containing Cs. (author)

  2. Perspectives of Living PSA in NPP Krsko

    International Nuclear Information System (INIS)

    Vrbanic, I.; Kastelan, M.

    1996-01-01

    Nuclear power plant Krsko has completed the Level 1/Level 2 Probabilistic Safety Analysis (PSA) for internal initiating events and is in the process of completing the same for the external initiators. The analysis completed up to now has provided a valuable insight into a plant risk profile. In NPP Krsko there is a plan to use the PSA model as a permanent tool for the risk based applications and incorporate it into a decision making process. In order to achieve this there is a need to permanently maintain the PSA model in a manner that it reflects both the plan configuration/design at a time point and the operational experience up to the time point. All the activities aimed toward keeping the PSA model up-to-dated in this sense are usually referred to as a Living PSA (LPSA) program. NPP Krsko is in the process of defining and proceduralizing a LPSA program that would be plant specific and based on known world practices. Further, in order to be suitable for risk based applications the PSA model must be flexible in a sense that modifications to the base case model may be done easily and requantifications performed quickly as to evaluate various conditions imposed by real or hypothetical situations. NPP Krsko PSA model has been based on licensing type software. The requirements specified above dictate the transfer of the overall model to an application oriented software of newer generation with larger capabilities. The transfer becomes a part of a mentioned ongoing effort aimed at establishing LPSA model and concept. The paper present this effort and the perspectives of LPSA concept and risk based applications in NPP Krsko. (author)

  3. Simulation of reinforced concrete NPP structures

    International Nuclear Information System (INIS)

    Zverev, A.B.; Yaskevich, E.E.; Tarannikov, V.N.; Loginov, A.Ya.; Lagutov, V.I.

    1989-01-01

    Analysis of stress-strained state of NPP frame structures at different stages of their operation using the method of physical simulation, is conducted. Comparison of model investigations to the data of full-scale deformation measurement allows one to define the strength resource of the structures under operation. Bench test layout and results of investigations into strength, deformation, thermal-physical and acoustic emission parameters of the investigated processes during model loading, are presented

  4. Safety enhancement in NPP Bohunice

    International Nuclear Information System (INIS)

    Lipar, M.; Mihalik, M.

    1997-01-01

    The upgrading and safety enhancement of both the Bohunice V-1 and V-2 reactors is described in detail. The total estimated cost of the gradual reconstruction of these two units during 1996 to 1999 is 180 mil. US dollars. For the 1995 to 1997 period, the actions common for both units include a quality assurance programme, a personnel training programme, installation of a multifunction simulator, implementation of symptom-oriented operation procedures, installation of diagnostic systems, of a site security system, and of a teledosimetric system. At present, the main maintenance tasks are: to carry out major repair of units, to remedy service interruptions, to enhance equipment service availability, to enhance the technical level of corrective actions at equipment. Investment into maintenance level upgrade has grown from 7.5 mil. Slovak crowns in 1994 to estimated 32 mil. in 2000. The partners of international cooperation are mentioned. (M.D.)

  5. 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

  6. 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)

  7. 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

  8. 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.

  9. 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.)

  10. About choosing the power unit of NPP

    International Nuclear Information System (INIS)

    Alekseev, P.N.; Mordashev, V.M.; Proshkin, A.A.; Stukalov, V.A.; Subbotin, S.A.; Tsibul'skij, V.F.; Chernilin, Yu.F.

    2008-01-01

    The present-day domestic nuclear power industry faces the necessity to make both process and economy related decisions. The mentioned decisions should cover all the aspects of the nuclear power complex. In particular, as of now, no substantiation of the present-day and the future requirements for the power unit of the WWER and fast reactor NPPs is available. The choice of the unit power of an NPP should involve consideration of all factors and should not be boiled down to the efforts to ensure the minimization of the investment and the operation constituents of the electric power generation costs. The aim of the present paper was to ensure elaboration of the recommendations to substantiate the optimal unit power of NPP power units based on the analysis of various factors to design, to construct and to operate an NPP (investment, time of construction, the unscheduled shutdown losses, the unification, the fabrication quality, the accident damage, etc.), and the electrical network potentialities and the regional electric power demands [ru

  11. Safety parameter display system for Kalinin NPP

    International Nuclear Information System (INIS)

    Andreev, V.I.; Videneev, E.N.; Tissot, J.C.; Joonekindt, D.; Davidenko, N.N.; Shaftan, G.I.; Dounaev, V.G.; Neboyan, V.T.

    1995-01-01

    The paper discusses the safety parameter display system (SPDS), which is being designed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. As compared with the traditional scope of functions of this kind of systems, the functionality of KlnNPP SPDS is significantly expanded due to the inclusion in it the operator support function ''computerized procedures''. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis center and to the crisis center of the State utility organization concern ''Rosenergoatom''. (author). 3 refs, 6 figs, 1 tab

  12. The NPP Isar comprehensive Aging Management Program

    International Nuclear Information System (INIS)

    Zander, Andre; Ertl, Stefan

    2012-01-01

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

  13. Tritium liquid effluents from the Krsko NPP

    International Nuclear Information System (INIS)

    Savli, S.; Krizman, M.; Nemec, T.; Cindro, M.; Stritar, A.; Vokal Nemec, B.; Janzekovic, H.

    2007-01-01

    In the past, 12-months' fuel cycles in the Krsko NPP had not caused any problems regarding compliance with its Technical Specifications and license limits on liquid tritium releases (20 TBq/year, 8 TBq/three months). The first 18-months' fuel cycle, which was introduced in 2004, required fuel with higher enrichment, higher boron concentration in the primary coolant and more fuel rods with burnable poisons. In 2005, the NPP operated without refueling outage for the whole year and produced the highest amount of energy so far. Due to these facts and a few unplanned shutdowns and power reductions, production of tritium and releases increased strongly in 2005. As a result, the Krsko NPP hardly succeeded to stay within regulatory limits on tritium releases. However, the three-months' limit was exceeded in the first quarter of 2006. On the basis of conclusions acquired from the SNSA's study and practice of other European countries the SNSA considerably increased the annual limit of permitted liquid tritium releases (from 20 TBq to 45 TBq) and abolished the three-months' limit. At the same time, the SNSA reduced the limit of fission and activation products by halves. (author)

  14. Optimization of radiation protection at Bohunice NPP

    International Nuclear Information System (INIS)

    Dobis, L.; Svitek, J.

    2003-01-01

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

  15. 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)

  16. Safety Culture Survey in Krsko NPP

    International Nuclear Information System (INIS)

    Strucic, M.; Bilic Zadric, T.

    2008-01-01

    The high level of nuclear safety, stability and competitiveness of electricity production, and public acceptability are the main objectives of Krsko Nuclear Power Plant. This is achievable only in environment where strong Safety Culture is taking dominant place in the way how employees communicate, perform tasks, share their ideas and attitudes, and demonstrate their concern in all aspects of work and coexistence. To achieve these objectives, behaviour of all employees as well as specific ethical values must become more transparent and that must arise from the heart of organization. Continuous ongoing and periodic self assessments of Safety Culture in Krsko NPP present major tools in implementation process of this approach. Benefits from Periodic interdisciplinary focused self assessment approach, which main intention is finding the strengths and potential areas for improvements, was used second time to assess the area of Safety Culture in Krsko NPP. Main objectives of self assessment, performed in 2006, were to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. For the purpose of effective self assessment, extensive questionnaire was used to obtain information that is representative for whole organization. Wide range of questions was chosen to cover five major characteristics of safety culture: Accountability for safety is clear, Safety is integrated into all activities, Safety culture is learning-driven, Leadership for safety is clear and Safety is a clearly recognized value. 484 Krsko NPP employees and 96 contractors were participated in survey. 70-question survey provided information that was quantified and results compared between groups. Anonymity of participant, as well as their willingness to contribute in this assessment implicates the high level of their openness in answering the questions. High number of participant made analysis of

  17. 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.)

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. 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

  6. Organizational development at Forsmark NPP

    International Nuclear Information System (INIS)

    Metzen, H.

    2001-01-01

    Forsmark is a three unit BWR site with a total capacity of 3200 MW. Units 1 and two are identical and went into commercial operation in 1980 and 1981. Unit 3 is of a later design with an output of 1200 MW and has been operating since 1985. The average availability for the site has been over 90% for the last 10 years, and the total busbar cost has been competitive. A consistent management strategy has been used to achieve the good results. Several organizational modifications have been made during the years to adapt the organization to changing internal and external conditions. An overall goal regarding staffing has been to keep the number of employees at the same level as in 1985 when Unit 3 went into commercial operation. During the time period from 1975, when the operational organization was formed, until today, the focus for the organization has changed several times. During the commissioning period the focus was on training and establishing routines and procedures. During the first years of operation development of maintenance programs and taking over activities from the supplier dominated. Next area in focus was increasing availability and making the outages more efficient. Several minor modifications to the plant were made to support maintenance activities. More focus on cost reduction and increasing the production through technical modifications were next. After 15 years of operation the need for replacement of components to ensure reliable operation was evident. A program for major modifications was developed, aiming at 40 years lifetime. Deregulation of the Nordic Electricity Market now calls for further reductions in production costs. (author)

  7. Design of NPP of new generation being constructed at the Novovoronezh NPP site

    International Nuclear Information System (INIS)

    Afrov, A.; Berkovich, V.; Generalov, V.; Dragunov, Yu.; Krushelnitsky, V.

    1999-01-01

    The design of a new generation NPP is described, underscoring advances in physical attributes and passive safety systems based on experiences with earlier designs at operating NPPs. This paper elaborates on systems for handling and storing radioactive wastes, on refinements in containment measures and on experimental and analytic validation of critical design factors. (author)

  8. Jpss System Architecture Npp to the Future

    Science.gov (United States)

    Furgerson, J.; Trumbower, G.

    2012-12-01

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

  9. Corporate portal system at PAKS NPP, Hungary

    International Nuclear Information System (INIS)

    2009-01-01

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

  10. Strategy for decommissioning of NPP's in Germany

    International Nuclear Information System (INIS)

    Rittscher, D.; Sterner, H.

    2003-01-01

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

  11. 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

  12. Contamination control by laundry monitor at NPP

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  13. Preparation of NPP Dukovany periodic safety review

    International Nuclear Information System (INIS)

    Dubsky, L.; Vymazal, P.

    2004-01-01

    Dukovany NPP in Czech Republic performs a periodic safety review for the second time after approximately 20 years of operation. The history of the Safety Report and its transformation into an internationally accepted form complying with IAEA standards is described. The deterministic and probabilistic assessment of the plant's safety-related design and state is applied to determine whether and to what extend the relevant protective goals are fulfilled by the existing plant design. A description of the step-by-step process is presented together with the creation of methods and criteria for PSR evaluation prepared by Nuclear Research Institute Rez

  14. Chernobyl NPP accident: a year later

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Borovoj, A.A.; Demin, V.F.

    1988-01-01

    Consideration is being given to measures on liquidation of Chernobyl accident aftereffects, conducted since August, 1986. One of the most important measures lay in construction of the ''shelter'', which must provide long-term conservation of accidental unit. Works on decontamination of reactor area and contaminated populated regions were continued. Measures on providing safety of population and its health protection were performed. An attention was paid to long-term investigations on studying delayed aftereffects of the accident, monitoring of invironment, development and introduction of measures on improving NPP safety. Prospects of further development of nuclear power engeneering and possibilities of improving its safety are considered

  15. WWER-type NPP spray ponds screen

    International Nuclear Information System (INIS)

    Nikolova, M.; Jordanov, M.; Denev, J.; Markov, D.

    2003-01-01

    The objective of this study is to develop a protection screen of WWER-type NPP spray ponds. The screen design is to ensure reduction of the water droplets blown by the wind and, if possible, their return back to the spray ponds. The cooling capacity of the ponds is not to be changed below the design level for safety reasons. Computational fluid dynamics analysis is used to assess the influence of each design variant on the behavior of the water droplets distribution. Two variants are presented here. The one with plants is found not feasible. The second variant, with steel screen and terrain profile modification is selected for implementation. (author)

  16. The accidents during shutdown conditions Temelin NPP

    International Nuclear Information System (INIS)

    Sykora, M.; Mlady, O.

    1996-01-01

    Two parallel activities oriented for the accidents during shutdown conditions are performed at Temelin NPP: Development of symptom based emergency operating procedures (EOPs) applicable for the accidents which could occur during operational modes 1 through 4; independent evaluation of plant safety as part of the Temelin Shutdown probabilistic assessment to define the accidents which could occur during mode 5 and 6 for which the EOPs must be extended. Both these activities are in progress now because Temelin plant is still in the construction phase

  17. Safe 15 Terawatt of Temelin NPP

    International Nuclear Information System (INIS)

    Sula, M.

    2010-01-01

    In this work author presents a project Safe 15 Terawatt realised on the Temelin NPP. This project is one of the eight key projects of the CEZ group, associated in the 'Programme of efficiency'. The project started in June 2007 with long-term goals for horizon of year 2012. The safety indicators will be reached of the first quarter level of world's nuclear power plant - by the end of the first decade. By the end of year 2012 we will have achieved annual production of 15 billion kWh - in the Czech Republic: 15 Terawatt.

  18. Baltic NPP Project specifics and current status

    International Nuclear Information System (INIS)

    2011-01-01

    Project overview: 2 x 1194 MW Units (AES-2006 series); Location in Kaliningrad region of the; Russian Federation; Operation dates: Unit 1 – Oct 2016; Unit 2 – Apr 2018; Site preparatory works ongoing. This is first NPP project in the Russian Federation providing opportunity for participation of foreign investors. Foreign investors may acquire up to 49% share. Cross-border transmission lines developed under separate project with participation of foreign investors. Conclusion: At the selected set of assumptions, the project is financially feasible in all scenarios

  19. Social consequences of closing the Ignalina NPP

    International Nuclear Information System (INIS)

    Baubinas, R.; Burneika, D.

    2001-01-01

    The possible social consequences of closing the Ignalina Nuclear Power Plant are studied. The social and economical situation in Visaginas and in the Utena region as a precondition for possible social consequences is shown. Also, two main groups of factors that can possibly influence the situation in the labour market are analysed. The problems of the enterprises that create working places and of the inhabitants of Visaginas whose possible behaviour can affect the situation in the labour market are discussed. Also, some proposals to neutralize the social costs of closing the Ignalina NPP are made. (author)

  20. Characterization of Ignalina NPP RBMK Reactors Graphite

    International Nuclear Information System (INIS)

    Hacker, P.J.; Neighbour, G.B.; Levinskas, R.; Milcius, D.

    2001-01-01

    The paper concentrates on the investigations of the initial physical properties of graphite used in production of graphite bricks of Ignalina NPP. These graphite bricks are used as nuclear moderator and major core structural components. Graphite bulk density is calculated by mensuration, pore volumes are measured by investigation of helium gas penetration in graphite pore network, the Young's modulus is determined using an ultrasonic time of flight method, the coefficient of thermal expansion is determined using a Netzsch dilatometer 402C, the fractured and machined graphite surfaces are studied using SEM, impurities are investigated qualitatively by EDAX, the degree of graphitization of the material is tested using X-ray diffraction. (author)

  1. Core power capability verification for PWR NPP

    International Nuclear Information System (INIS)

    Xian Chunyu; Liu Changwen; Zhang Hong; Liang Wei

    2002-01-01

    The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced. The radial and axial power distributions of normal operation (category I or condition I) and abnormal operation (category II or condition II) are simulated by using neutronics calculation code. The linear power density margin and DNBR margin for both categories, which reflect core safety, are analyzed from the point view of reactor physics and T/H, and thus category I operating domain and category II protection set point are verified. Besides, the verification results of reference NPP are also given

  2. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    1997-01-01

    6th Nuclear society information meeting dealt with the completion of the Mochovce NPP with regard to implementation of safety measures. It was aimed to next problems: I. 'Survey' presentation on the situation of the nuclear power industry in partner countries; II. Basic technical presentations; III. Presentations of operators of the other VVER 440/213 NPPs on their activities in the field of safety improvement in relation to IAEA recommendations; IV. Technical solutions of safety improvements ranked with IAEA degree 3 (Report SC 108 VVER); V: Technical solutions of selected Safety Measures ranked with IAEA degree 2 and 1 (Report SC 108 VVER)

  3. Calculation of NPP pipeline seismic stability

    International Nuclear Information System (INIS)

    Kirillov, A.P.; Ambriashvili, Yu.K.; Kaliberda, I.V.

    1982-01-01

    A simplified design procedure of seismic pipeline stability of NPP at WWER reactor is described. The simplified design procedure envisages during the selection and arrangement of pipeline saddle and hydraulic shock absorbers use of method of introduction of resilient mountings of very high rigidity into the calculated scheme of the pipeline and performance of calculations with step-by-step method. It is concluded that the application of the design procedure considered permits to determine strains due to seismic loads, to analyze stressed state in pipeline elements and supporting power of pipe-line saddle with provision for seismic loads to plan measures on seismic protection

  4. Nuclear Oversight Function at Krsko NPP

    International Nuclear Information System (INIS)

    Bozin, B.; Kavsek, D.

    2010-01-01

    The nuclear oversight function is used at the Krsko NPP constructively to strengthen safety and improve performance. Nuclear safety is kept under constant examination through a variety of monitoring techniques and activities, some of which provide an independent review. The nuclear oversight function at the Krsko NPP is accomplished by Quality and Nuclear Oversight Division (SKV). SKV has completed its mission through a combination of compliance, performance and effectiveness-based assessments. The performance-based assessment is an assessment using various techniques (observations, interviews, walk-downs, document reviews) to assure compliance with standards and regulations, obtain insight into performance, performance trends and also to identify opportunities to improve effectiveness of implementation. Generally, the performance-based approach to oversight function is based on some essential elements. The most important one which is developed and implemented is an oversight program (procedure). The program focuses on techniques, activities and objectives commensurate with their significance to plant operational safety. These techniques and activities are: self-assessments, assessments, audits, performance indicators, monitoring of corrective action program (CAP), industry independent reviews (such as IAEA's OSART and WANO Peer Review), industry benchmarking etc. Graded approach is an inherent product of a performance based program and ranking process. It is important not only to focus on the highest ranked performance based attributes but to lead to effective utilization of an oversight program. The attributes selected for oversight need to be based on plant specific experience, current industry operating experience, supplier's performance and quality issues. Collaboration within the industry and effective utility oversight of processes and design activities are essential for achieving good plant performance. So the oversight program must integrate relevant

  5. 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)

  6. Selection of index complex for the NPP operator activity efficiency

    Energy Technology Data Exchange (ETDEWEB)

    Kolesnik, A I; Chertorizhskij, E A

    1984-01-01

    Preconditions for choice of NPP operator activity efficiency index are determined. Results of the choice are given and a method for determination of generalized and particular parameters by means of which NPP operator activity efficiency can be estimated is considered. An algorithm of diagnosis of reason for unsuccess of operator activity based on assessment of psychological factors of complicacy is suggested.

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. Use of NESTLE computer code for NPP transition process analysis

    International Nuclear Information System (INIS)

    Gal'chenko, V.V.

    2001-01-01

    A newly created WWER-440 reactor model with use NESTLE code is discussed. Results of 'fast' and 'slow' transition processes based on it are presented. This model was developed for Rovno NPP reactor and it can be used also for WWER-1000 reactor in Zaporozhe NPP

  12. 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

  13. 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

  14. Economical aspect of the decommissioning for NPP

    International Nuclear Information System (INIS)

    Daryoko, M.

    1998-01-01

    The estimated, analysed and founding of the economical aspect at decommissioning of Nuclear Power Plant (NPP) have been studied. The data that have been obtained from literature, then the calculation and analysing have been done base to the future condition. The cost for NPP decommissioning depend on the internal factor such as type, capacity and safe storage time, and the external factor such as policy, manpower and the technology preparation. The successfulness of funding, depend on the rate of inflation, discount rate of interest and the currency fluctuation. For the internal factor, the influence of the type of the reactor (BWR or PWR) to the decommissioning cost is negligible, the big reactor capacity (±1100 MW), and the safe storage between 30 to 100 years are recommended, and for the external factor, specially Indonesia, to meet the future need the ratio of decommissioning cost and capital cost will be lower than in develop countries at the present (10%). The ratio between decommissioning fund and electricity generation cost relatively very low, are more less than 1.79 % for 30 years safe storage, and discount rate of interest 3%, or more less than 0.30 % for safe storage 30 years, and discount rate of interest 6%. (author)

  15. Central alarm system replacement in NPP Krsko

    International Nuclear Information System (INIS)

    Cicvaric, D.; Susnic, M.; Djetelic, N.

    2004-01-01

    Current NPP Krsko central alarm system consists of three main segments. Main Control Board alarm system (BETA 1000), Ventilation Control Board alarm system (BETA 1000) and Electrical Control Board alarm system (BETA 1100). All sections are equipped with specific BetaTone audible alarms and silence, acknowledge as well as test push buttons. The main reason for central alarm system replacement is system obsolescence and problems with maintenance, due to lack of spare parts. Other issue is lack of system redundancy, which could lead to loss of several Alarm Light Boxes in the event of particular power supply failure. Current central alarm system does not provide means of alarm optimization, grouping or prioritization. There are three main options for central alarm system replacement: Conventional annunciator system, hybrid annunciator system and advanced alarm system. Advanced alarm system implementation requires Main Control Board upgrade, integration of process instrumentation and plant process computer as well as long time for replacement. NPP Krsko has decided to implement hybrid alarm system with patchwork approach. The new central alarm system will be stand alone, digital, with advanced filtering and alarm grouping options. Sequence of event recorder will be linked with plant process computer and time synchronized with redundant GPS signal. Advanced functions such as link to plant procedures will be implemented with plant process computer upgrade in outage 2006. Central alarm system replacement is due in outage 2004.(author)

  16. Plant lifetime management at Jose Cabrera NPP

    International Nuclear Information System (INIS)

    Martin, Jorge; Garcia, Piedad

    1998-01-01

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

  17. NPP unusual events: data, analysis and application

    International Nuclear Information System (INIS)

    Tolstykh, V.

    1990-01-01

    Subject of the paper are the IAEA cooperative patterns of unusual events data treatment and utilization of the operating safety experience feedback. The Incident Reporting System (IRS) and the Analysis of Safety Significant Event Team (ASSET) are discussed. The IRS methodology in collection, handling, assessment and dissemination of data on NPP unusual events (deviations, incidents and accidents) occurring during operations, surveillance and maintenance is outlined by the reports gathering and issuing practice, the experts assessment procedures and the parameters of the system. After 7 years of existence the IAEA-IRS contains over 1000 reports and receives 1.5-4% of the total information on unusual events. The author considers the reports only as detailed technical 'records' of events requiring assessment. The ASSET approaches implying an in-depth occurrences analysis directed towards level-1 PSA utilization are commented on. The experts evaluated root causes for the reported events and some trends are presented. Generally, internal events due to unexpected paths of water in the nuclear installations, occurrences related to the integrity of the primary heat transport systems, events associated with the engineered safety systems and events involving human factor represent the large groups deserving close attention. Personal recommendations on how to use the events related information use for NPP safety improvement are given. 2 tabs (R.Ts)

  18. Corrective action program at Krsko NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  19. Forsmark NPP I and C modernization strategy

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  20. NPP Krsko Periodic Safety Review action plan

    International Nuclear Information System (INIS)

    Bilic Zabric, T.

    2006-01-01

    In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

  1. Fiddle at financing of Mochovce NPP

    International Nuclear Information System (INIS)

    Beer, G.

    2003-01-01

    Slovak police found out and documented racket in financing of third and fourth block of Mochovce NPP. Damage should be 144 millions Slovak crowns. Investigator consequently accused twenty-three Slovaks from foundation, trump up and supporting of criminal group and deception. Two persons are suggested to be taken to custody. Skoda Praha, which was general supplier of construction for 1,5 billions Slovak crowns, in 2001 allowed to create a connection to let the finances between Slovenske elektrarne, a.s., Bratislava as investor and Skoda as subcontractor to be paid through three mediator companies. Companies got authorization to balance the relationship among all interested subjects. Confused network of 118 treaties was created. They invoiced reward from money current based on these treaties. Reward represented up to 70 per cent of transferred resources in some cases. According to Minister of Domestic Affairs Vladimir Palko it will be necessary to find out where is actually the money. For the time being nobody from NPP is among accused. (Author)

  2. Brief Assessment of Krsko NPP Decommissioning Costs

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  3. Corrective action program at Krsko NPP

    International Nuclear Information System (INIS)

    Skaler, F.; Divjak, G.; Kavsek, D.

    2004-01-01

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

  4. Monitors for the surveillance of NPP components

    International Nuclear Information System (INIS)

    Giera, H.D.; Grabner, A.; Hessel, G.; Koeppen, H.E.; Liewers, P.; Schumann, P.; Weiss, F.P.; Kunze, U.; Pfeiffer, G.

    1985-01-01

    Noise diagnostics have reached a level where it is possible and efficient to integrate this method as far as possible into the control and safety system of the NPP. The communication between the noise diagnostic system and the plant operator is the main problem of integration. It is necessary to refine the diagnostic results in such a manner that the operator can use them without being skilled in noise analysis respectively without contacting a noise specialist. Moreover, in this way the noise specialist can be released from routine surveillance. For selected processes which have already intensively been investigated because of their inherent risk this can be achieved by means of autonomously working monitors. Independently the monitors perform signal processing and diagnosis. In general this means that they classify the technical condition of the monitored component into one of the two categories: ''normal'' or ''anomalous''. The result will be annunciated to the plant operator who will in the first step of the development contact the noise specialist only if anomalies have occurred in order to clarify the cause. At the NPP ''Bruno Leuschner'' Greifswald, three hardware monitors for loose parts detection, control rod surveillance and main coolant pump diagnosis are being tested. Additionally a so-called software monitor for diagnosing the pressure vessel vibrations is in preparation. The techniques and the hardware used for the monitors as well as planned further improvements of the integration of noise diagnostics into the control and safety system are discussed in this paper. (author)

  5. Can the Ignalina NPP be safe?

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    Many countries started using nuclear power before Lithuania, the IAEA and NEA were established and have been functioning efficiently, numerous conventions have been signed that control nuclear activities, nuclear safety regulations and standards have been set. Lithuania which is striving to integrate into the West European structures and to become a member of the 'club' of the world's nuclear states, has become a full and equal member of the IAEA and recognises its recommendations. Furthermore, it has signed or joined international conventions and is doing its best to introduce the practice of controlling nuclear safety applied in western countries. Nuclear safety cannot be taken as something finite that does not change. The requirements of nuclear and radiation safety are continuously redefined taking into consideration scientific discoveries and inventions as well as technical progress. Safety assurance can be the only criterion that should determine whether the nuclear power plant can be operated in Lithuania. The safety analysis report confirmed that the Ignalina NPP can be safely operated until the channel-graphite gap closes. The experiments conducted to date have convincingly shown that by the year 2000 the gap will not close in any of the fuel channels of unit 1. It can be hoped that the submitted studies, analyses and assessments will confirm that the Ignalina NPP meets Lithuania's nuclear safety requirements that have been drawn up in compliance with the recommendations of IAEA

  6. Equipment Reliability Process in Krsko NPP

    International Nuclear Information System (INIS)

    Gluhak, M.

    2016-01-01

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

  7. 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

  8. Automated personal dosimetry monitoring system for NPP

    International Nuclear Information System (INIS)

    Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D.

    2006-01-01

    Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using thermoluminescent

  9. Report on Fukushima Daiichi NPP precursor events

    International Nuclear Information System (INIS)

    2014-01-01

    The main questions to be answered by this report were: The Fukushima Daiichi NPP accident, could it have been prevented? If there is a next severe accident, may it be prevented? To answer the first question, the report addressed several aspects. First, the report investigated whether precursors to the Fukushima Daiichi NPP accident existed in the operating experience; second, the reasons why these precursors did not evolve into a severe accident. Third, whether lessons learned from these precursor events were adequately considered by member countries; and finally, if the operating experience feedback system needs to be improved, based on the previous analysis. To address the second question which is much more challenging, the report considered precursor events identified through a search and analysis of the IRS database and also precursors events based on risk significance. Both methods can point out areas where further work may be needed, even if it depends heavily on design and site-specific factors. From the operating experience side, more efforts are needed to ensure timely and full implementation of lessons learnt from precursor events. Concerning risk considerations, a combined use of risk precursors and operating experience may drive to effective changes to plants to reduce risk. The report also contains a short description and evaluation of selected precursors that are related to the course of the Fukushima Daiichi NPP accident. The report addresses the question whether operating experience feedback can be effectively used to identify plant vulnerabilities and minimize potential for severe core damage accidents. Based on several of the precursor events national or international in-depth evaluations were started. The vulnerability of NPPs due to external and internal flooding has clearly been addressed. In addition to the IRS based investigation, the WGRISK was asked to identify important precursor events based on risk significance. These precursors have

  10. 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

  11. Simulator for NPP Temelin and I and C system assessment

    International Nuclear Information System (INIS)

    Krcek, V.

    1997-01-01

    The paper provides a brief overview over the NPP Temelin simulator design features, the recent status and the future planned steps of the simulator system integration, testing and operation. The simulator is designed as the full scope control room replica type simulator with stimulation of the selected special I and C subsystems as are used on the man-machine interface in the reference unit main control room. The primary goal of the simulator is provide plant operators and other plant technical staff with comprehensive training in all aspects of the plant control and monitoring under the operating conditions simulated in the real-time (normal operation, incident and accident scenarios). The quality and scope of simulation offers possibility to use efficiently simulator as well for a wide spectrum of the engineering analyses to help the plant designers evaluate, verify and improve especially I and C system algorithms, plant operating instructions as well as the MCR man-machine design before the reference unit startup. The paper deals with simulation approach used for in depth analyses, assessment and potential improvements of the sophisticated and complex I and C system algorithms developed and prepared for implementation in the reference plant on the state-of-the-art digital platform of Westinghouse technology (Eagle system cabinets, WDPF system units, NPL cabinets, etc.), using display based version of the full scope simulator as an efficient supporting tool for this analyses. (author)

  12. 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

  13. 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)

  14. 20 Years of Dukovany NPP Operation and Plans for Future

    International Nuclear Information System (INIS)

    Vlcek, J.

    2006-01-01

    NPP Dukovany (4x440MW), the first Czech nuclear power plant and a keystone of Czech Electricity Grid, in 2005 celebrated 20 years of successful operation. In my presentation I am going to speak about next areas. I will start about construction and commissioning history of Dukovany NPP, then I'll put forward what milestones of Dukovany NPP operation were accomplished, I'll say examples about our modernisation and investment activities (including replacement of IandC equipment, modifications for increasing of power and support grid services) and in the end our plans for future. (author)

  15. 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)

  16. The preliminary success of ALARA implementation in Daya Bay NPP

    International Nuclear Information System (INIS)

    Yang Maochun; Chen Degan

    2000-01-01

    Based on the practical condition of the plant and in reference to advanced management experiences worldwide, Daya Bay Nuclear Power Plant has established its own peculiar management system for radiation protection management and ALARA implementation. The characteristics of the system are: radiation protection training to all workers, active involvement of all managers and staffs, and whole process safety control to maintenance activities. The management philosophy of 'workers are responsible for their own radiation safety' is adopted in the plant. A strict, formalized and systematic whole staff radiation protection training, evaluation, authorization and periodically refreshing mechanism had been established and executed in the plant. In the organizational point of view, the responsibilities of line managers were specified in plant procedures, ALARA coordination organization on plant level and for specific activities were established. Meanwhile, the plant highlighted the defining, following up, controlling and advertising of radiation protection targets. All these measures made radiation protection management be the responsibilities of a safety network in which whole staffs are involved. In the practical radiation protection activities, the plant focuses on works of high radiation risk and performs whole process control. In addition, professional radiation protection staff played an important and active role in technical advisory and control of radiation protection. Satisfactory results have been achieved in Daya Bay NPP in radiation protection in the past years. The collective dose including that of contractors per unit and year have been declining from 0.99 man·Sv/Unit·Year in 1995 to 0.667 man·Sv/Unit·Year in 1998, which were consistently lower than the best quartile result of PWR plants in WANO reports each year. Individual dose was also controlled at a very low level, no one was overexposed in the past years

  17. Construction of Belene NPP in Bulgaria

    International Nuclear Information System (INIS)

    JSC Atomstroyexport

    2010-01-01

    Presentations concluding remarks: ASE has performed its scope of responsibilities under the Agreement of 29.11.2006 and has achieved great results regarding both the Technical part of the Project and its organization; Though there is a number of unsettled issues under the Project, in particular, the issue related to financing, ASE is willing to continue the Project and works on its development; The Russian Party believes that in case the activities under the Project are continued, Belene NPP will be constructed with high quality and within the time limits prescribed in the Agreement of 29.11.2006: 59 months before Unit 1 take-over into operation and 71 month before Unit 2 take-over into operation, starting from concreting of foundation slab of Unit 1 Reactor building

  18. Crushed stone production plant for NPP building

    International Nuclear Information System (INIS)

    Obolenskij, V.Ya.

    1982-01-01

    The project of the granite-crushed stone quarry - the large modern plant producing building materials, is presented. The quarry is designated for providing NPP and other power objects building with high-strength crushed stone. The plant consists of: quarry; crushing-sorting plant with maintenance objects arranged on its ground; basis and service stores of explosive materials; tail facility and purifying systems; water supply purifying stations; water storage basin. The plant is reserved for 2335 thousand m 3 yearly utoput of crushed stone; the staff consists of 535 persons, the budgeted cost of building is 26.6 million rubles. Physicochemical characteristics of granosyenites of the ''Granitnoye'' deposit - the raw material resource base of the plant and technological scheme of the crushing-sorting plant are given. Planned measures on building organization and recultivation of disturbed grounds are presented

  19. Concreting organization during Chernobylsk NPP construction

    International Nuclear Information System (INIS)

    Lysyuk, R.I.; Kareva, A.P.

    1984-01-01

    Conreting organization during the Chernobylsk NPP construction is described. Processes of extra heavy concrete production and placement, which specific mass constitutes 4t/m 3 at the age of 28 days wiath metallic aggregates and 3.3-3.5 t/m 3 at the same age without aggregates, are considered in short. Basic characteristics of this concrete are presented. At the 4th power unit labour contents for construction works were a 1.5 times lower as compared to the 3rd power unit erection. This progress was achieved by round-the-clock operation of the concrete plant with the 800 m 3 /day output and also by utilization of special equipment for mechanized concrete placement: concrete pumps, automatic concrete mixer, manipulators and concrete pipelines

  20. Industry Operating Experience Process at Krsko NPP

    International Nuclear Information System (INIS)

    Bach, B.; Bozin, B.; Cizmek, R.

    2012-01-01

    Experience has shown that number of minor events and near misses, usually without immediate or significant impact to plant safety and reliability, are precursors of significant or severe events due to the same or similar root or apparent cause(s). It is therefore desirable to identify and analyze weaknesses of the precursor problems (events) in order to prevent occurrence of significant events. Theoretically, significant events could be prevented from occurring if the root cause(s) of these precursor problems could be identified and eliminated. The Operating Experience Program identifies such event precursors and by reporting them to the industry, plant specific corrective actions can be taken to prevent events at other operational plants. The intent of the Operating Experience Program is therefore to improve nuclear power plant safety and reliability of the operating nuclear power plants. Each plant develops its own Operating Experience Program in order to learn from the in-house operating experience as well as from the world community of nuclear plants. The effective use of operating experience includes analyzing both plant and industry events in order to identify fundamental weaknesses and then determining appropriate plant-specific actions that will minimize the likelihood of similar events. Learning and applying the lessons from operating experience is an integral part of station safety culture and is encouraged by managers throughout the top plant administrative programs and procedures. Krsko NPP is developed it own Operating Experience Program by using the most relevant INPO/WANO/IAEA guidelines as well as its own knowledge, skills an operating practice. The Operating Experience Program is a part of the Corrective Action Program, which is among top management programs, thus program is strongly encouraged by top management. The purpose of Operating Experience Program is to provide guidance for using, sharing, and evaluating operating experience information