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Country Profile SynopsisSize: 6,592,850 square miles (nearly twice the size of the United States)
Electricity Production1: 771.9 billion kWh (1998)
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Russia has nine nuclear power plants with 29 reactors. In 1999, the nuclear power plants in Russia produced 14 percent of the electricity; in the far western parts of Russia, the share was higher, near 30 percent. The Kola, Leningrad, and Smolensk nuclear power plants supply half of northwest Russia's electricity requirements.
About 97 percent of Russia's nuclear generating capacity comes from reactors built to the RBMK and VVER designs. DOE's cooperative safety program works closely with several Russian organizations.
Plant Manager: Pavel L. Ipatov
Chief Engineer: Victor I. Ignatov
Utility: Rosenergoatom
Telephone No.: 7-845-70-32638
Fax: 7-845-70-26209
Unit | Reactor Model | Net Output | Initial Start | Status |
---|---|---|---|---|
1 | VVER-1000 | 950 MWe | 12/1985 | Operating |
2 | VVER-1000 | 950 MWe | 10/1987 | Operating |
3 | VVER-1000 | 950 MWe | 12/1988 | Operating |
4 | VVER-1000 | 950 MWe | 3/1993 | Operating |
5 | VVER-1000 | 950 MWe | Construction Suspended | |
6 | VVER-1000 | 950 MWe | Construction Suspended |
Operator training is a key factor in improving safety of day-to-day operations. At the Balakovo plant, a major DOE effort has been to establish the Balakovo Training Center, a fully equipped training facility at which reactor operators from other Russian reactors have been trained in the Systematic Approach to Training methodology (1993-1998). Center specialists have developed job-specific and general safety-related courses for use at the center and at other Russian reactors (1994-1998). Other major projects are focused on developing improved operating procedures and practices (1994-1997) and providing an analytical simulator and upgrading a full-scope simulator to enhance effectiveness of training (1996-1999). Projects to upgrade safety systems and to transfer the capabilities for performing in?depth safety assessments are under way.
Plant Manager: Oleg M. Saraev
Chief Engineer: Nikolai N. Oshkanov
Utility: Rosenergoatom
Telephone No.: 7-343-77-36350
Fax: 7-343-77-31070
Unit | Reactor Model |
Net Output | Initial Start | Status |
---|---|---|---|---|
1 | LWGR- 1000 |
102 MWe | 4/1964 | Shut Down 6/1983 |
2 | LWGR- 1000 |
146 MWe | 12/1969 | Shut Down 1/1990 |
3 | BN-600 | 560 MWe | 11/1981 | Operating |
4 | BN-800 | 750 MWe | Construction Suspended |
At Beloyarsk nuclear power plant, DOE projects have focused on improving the training of plant managers and operators (1996-1998).
Plant Manager: Mikhail V. Chudakov
Chief Engineer: Andrey A. Dementjev
Utility: Rosenergoatom
Telephone No.: 7-413-62-24448
Fax: 7-413-62-24888
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | LWGR | 12 MWe | 12/1973 | Operating |
2 | LWGR | 12 MWe | 12/1973 | Operating |
3 | LWGR | 12 MWe | 12/1975 | Operating |
4 | LWGR | 12 MWe | 12/1976 | Operating |
DOE is supporting efforts to improve the safety of day-to-day operations at the Bilibino plant. DOE projects have been focused primarily on improving training for plant staff (1996-1998); providing an analytical simulator to enhance training effectiveness (1997-2000); providing safety maintenance equipment and technology (1997-2000); and establishing improved communication links with Moscow and with the Alaskan Emergency Response Office (1996).
Plant Manager: Stanislav I. Antipov
Chief Engineer: Vasily I. Aksenov
Utility: Rosenergoatom
Telephone No.: 7-082-55-44742
Fax: 7-082-55-44591
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | VVER- 1000 |
950 MWe | 4/1984 | Operating |
2 | VVER- 1000 |
950 MWe | 11/1986 | Operating |
3 | VVER- 1000 |
950 MWe | Under Construction | |
4 | VVER- 1000 |
950 MWe | Construction Suspended |
DOE's efforts focus primarily on improving the safety of day-to-day operations at the Kalinin plant. Projects include improving the training of plant management and staff (1994-1998) and providing a full-scope simulator to enhance effectiveness of training (1995-2001).
Plant Manager: Yuri V. Kolomtsev
Chief Engineer: Vasily V. Omelchuk
Utility: Rosenergoatom
Telephone No.: 7-815-32-68350
Fax: 7-815-32-68140
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | VVER- 440/230 |
411 MWe | 6/1973 | Operating |
2 | VVER- 440/230 |
411 MWe | 11/1974 | Operating |
3 | VVER- 440/213 |
411 MWe | 2/1981 | Operating |
4 | VVER- 440/213 |
411 MWe | 10/1984 | Operating |
DOE efforts at the Kola plant are directed primarily toward improving the safety of day-to-day operations and upgrading critical plant safety systems. Projects focus on developing emergency operating instructions (1993-2001), upgrading the confinement system (1993-1997), and improving other engineered safety systems (1993-1998). Projects also are in place to perform safety assessments and to transfer capabilities for performing plant safety analyses (1996-2001) and to provide a full-scope simulator to enhance staff training (1995-2000).
Plant Manager: Yuriy I. Slepokon
Chief Engineer: Vyacheslav M. Rjakhin
Utility: Rosenergoatom
Telephone No.: 7-071-31-41819, -53350, -41839
Fax: 7-071-31-41849, -54329
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | RBMK- 1000 |
925 MWe | 10/1976 | Operating * |
2 | RBWK- 1000 |
925 MWe | 12/1978 | Operating |
3 | RBWK- 1000 |
925 MWe | 8/1983 | Operating |
4 | RBMK- 1000 |
925 MWe | 10/1985 | Operating |
5 | RBMK- 1000 |
925 MWe | Under Construction | |
* Operating under a "trial period." |
DOE efforts at the Kursk plant focus on improving the safety of day-to-day operations and upgrading critical plant safety systems. Projects include providing tools, equipment, and training to improve plant safety maintenance (1995-1999) and upgrading key engineered safety systems (1993-2000).
Operator exchanges that trained plant personnel to develop improved operating safety procedures and practices were completed.
Emergency operating instructions that promote safety through improved accident mitigation strategies were developed for the plant. Analysis to support the implementation of these procedures is under way.
Mechanical pump/motor shaft alignment equipment was provided to the plant along with training by U.S. specialists.
State-of-the-art machines to cut pipes in vital safety systems precisely and prepare pipe ends for welding were provided to the plant. Previously, workers cut pipes needing replacement by hand, which caused inaccurate welds and potential leakage.
Valve-seat resurfacing equipment and a vibration monitoring and shaft alignment system for improving safety maintenance activities were provided to the plant
Basic equipment was provided for the development and support of training materials at the plant. This equipment included computers and a server, software, printers, a photocopier, overhead projectors, projector screens, and various consumables and office supplies.
Instructors from the plant were trained in the Systematic Approach to Training methodology and in instructor skills.
The transfer of the Systematic Approach to Training methodology and training materials developed at the Balakovo Training Center to the Kursk plant was completed. A pilot course on laser shaft alignment was developed and implemented.
A seismically qualified, direct-current power supply system (including batteries) was installed at the plant.
A safety parameter display system was installed and tested at Unit 2.
Automated ultrasonic test equipment for detecting flaws in piping and other pressure boundary components was delivered to the plant. Associated training was provided.
Prototypes of high-temperature protective clothing for inspecting steam leaks were provided for the plant. (High-temperature protective clothing was subsequently provided to each of the nuclear power plants operated by Rosenergoatom.)
Plant Manager: Valery Lebedev
Chief Engineer: Yury V. Garusov
Utility: Leningrad Nuclear Power Plant
Telephone No.: 7-812-69-61397
Fax: 7-812-69-62518
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | RBMK- 1000 |
925 MWe | 9/1973 | Operating |
2 | RBMK- 1000 |
925 MWe | 5/1975 | Operating |
3 | RBMK- 1000 |
925 MWe | 9/1979 | Operating |
4 | RBMK- 1000 |
925 MWe | 12/1980 | Operating |
DOE efforts at the Leningrad plant focus on improving the safety of day-to-day operations and upgrading critical plant safety systems. DOE projects are in place for developing emergency operating instructions (1993-2001), providing modern safety maintenance tools and techniques (1995-1999), and performing in-depth safety assessments (1996-2002). In addition, projects are under way to provide an improved fire detection system (1995-2000).
Operator exchanges that trained plant personnel to develop improved operating safety procedures and practices were completed.
Emergency operating instructions that promote safety through improved accident mitigation strategies for the plant were developed. Analysis necessary to support the implementation of these procedures is under way.
Valve-seat resurfacing equipment, a pipe lathe/weld-preparation machine, and a vibration monitoring and shaft alignment system for improving safety maintenance activities were provided to the plant.
Basic equipment was provided for the development and support of training at the plant. This equipment included computers, printers, a scanner, photocopiers, overhead projectors, projector screens, video equipment, and various consumables and office supplies.
The transfer of the Systematic Approach to Training methodology and training materials developed at the Balakovo Training Center to the Leningrad plant was completed. Pilot courses for Shift Supervisors and Control Room Reactor Operators were developed and implemented.
The plant has staffed a safety analysis group to support the probabilistic safety assessment and full-scope in?depth safety assessment (ISA). The plant is taking the lead in identifying the scope and content of the ISA.
Project planning to expand the plant's Unit 2 safety assessment to a full-scope
in-depth safety assessment necessary to meet Russian regulatory requirements
was completed. An in-depth safety assessment for Unit 2 was initiated. In
support of the assessment, system descriptions and a safety analysis were
completed. Plant-specific reliability and operational data are being collected.
Quantification of an internal-event probabilistic risk assessment was completed.
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | VVER- 210 |
265 MWe | 12/1964 | Shut Down 2/1988 |
2 | VVER- 365 |
336 MWe | 4/1970 | Shut Down 8/1990 |
3 | VVER- 440/230 |
385 MWe | 12/1971 | Operating |
4 | VVER- 440/230 |
385 MWe | 12/1972 | Operating |
5 | VVER- 1000 |
950 MWe | 4/1980 | Operating |
Plant Manager: Vyacheslav A. Vikin
Chief Engineer: Vladimir S. Zarubaev
Utility: Rosenergoatom
Telephone No.: 7-073-64-73305
Fax: 7-073-64-73302
DOE efforts at the Novovoronezh plant focus on improving the safety of day-to-day operations and upgrading critical plant safety systems. DOE projects include providing an analytical simulator to improve reactor operator training (1995-1998); developing and implementing emergency operating instructions (1993-1997); and performing in-depth safety assessments (1996-2001). Other projects include improving key plant safety systems (1994-2001) and providing safety parameter display systems (1994-2002).
Operator exchanges that trained plant personnel to develop improved operating safety procedures and practices were completed.
All twenty-nine symptom-based emergency operating instructions that promote safety at the plant through improved accident mitigation strategies were approved and implemented at Unit 3.
The Unit 3 VVER-440/230 analytical simulator project was completed and the simulator was declared operational in 1998.
Basic equipment was provided for the development and support of training at the plant. This equipment included personal computers, office furniture, overhead projectors, projector screens, and whiteboards.
The transfer of the Systematic Approach to Training methodology and training materials developed at the Balakovo Training Center to the Novovoronezh plant was completed. A pilot course for Shift Supervisors was developed and implemented.
Instructors have been trained in the Systematic Approach to Training methodology and in instructor skills.
Safety parameter display systems were provided for Units 3 and 4.
A Level 1 internal events probabilistic risk assessment for Unit 3 was completed. A walkdown and screening analysis for external events analysis was completed.
A RELAP model of Unit 3 and technical guidelines were completed for a design basis accident analysis.
Plant Manager: Sergey P. Krylov
Chief Engineer: Akhmed Fereev
Utility: Rosenergoatom
Telephone No.: 7-081-53-72350
Fax: 7-095-59-25241
Unit | Reactor Model |
Net Output |
Initial Start |
Status |
---|---|---|---|---|
1 | RBMK- 1000 |
925 MWe | 9/1982 | Operating |
2 | RBMK- 1000 |
925 MWe | 4/1985 | Operating |
3 | RBMK- 1000 |
925 MWe | 12/1989 | Operating |
At Smolensk nuclear power plant, DOE efforts are directed toward improving safety of day-to-day operations and improving critical plant safety systems. Projects include developing emergency operating instructions (1994-2001); providing improved maintenance tools, equipment, and techniques (1995-1999); and improving fire prevention and detection systems (1993-2002).
Operator exchanges that trained plant personnel to develop improved operating safety procedures and practices were completed.
Emergency operating instructions that promote safety through improved accident mitigation strategies were developed. Analysis necessary to support the implementation of these procedures is under way.
Valve-seat resurfacing equipment, a pipe lathe/weld-preparation machine, and a vibration monitoring and shaft alignment system for improving safety maintenance activities were provided to the plant.
The transfer of the Systematic Approach to Training methodology and training materials developed at the Balakovo Training Center to the Smolensk plant was completed. Pilot courses on laser shaft alignment, shift supervisor responsibilities, and control room reactor operations were developed and implemented.
Basic equipment was provided for the development and support of training at the plant. This equipment included computers, printers, software, a scanner, overhead projectors, and various consumables and office supplies.
A deterministic fire hazards safe shutdown study was completed for Unit 3. Vulnerabilities identified in the analysis will be prioritized for remediation based on risk significance.
Fire doors, fire detectors, fire protection equipment, penetration sealant material, and a fire brigade radio system were provided to the plant to improve fire protection. Installation of the fire detection system is scheduled to be completed in 2000.
Eighty low-current, 400-V circuit-breakers were installed in the plant
for in-plant demonstration. Nineteen 6-kV circuit-breaker assemblies were
tested and certified. These assemblies were provided for in-plant testing
in 2000. Testing was also performed on high-current 400-V circuit-breaker
assemblies.
The Russia International Nuclear Safety Center (RINSC) was founded in accordance with a joint Declaration on Establishing International Nuclear Safety Centers, adopted in January 1996, during the Sixth Session of the Gore-Chernomyrdin Commission on economical and technological cooperation in Washington, D.C. The Russian Minister for Atomic Energy has made the Russian Center accountable to the Department of Nuclear Power for its technical activities and to the Department of International Relations for its international cooperation. The Coordinating Council of the Center, which includes the leaders of the project member companies, is chaired by the Minister of Atomic Energy. The Center's Director is the Scientific Secretary of the Council. The selection of projects and their results are reviewed and evaluated by the Coordinating Council.
The RINSC is under the general direction of the Russian Minister for Atomic Energy. Professor Doctor Sergei E. Bougenko (Phone Number: 7-095-263-7310; Fax Number: 7-095-264-4010) is the Technical Director of the Center.
The RINSC carries out research and development studies to ensure the safety of nuclear power plants, research reactors, space, and maritime nuclear reactors. The leading agencies within Minatom, as well as nuclear-related companies, research centers and institutes, universities, and the Russian Academy of Sciences, participate in the Center's projects. Results of the Center's research and development efforts are subjected to independent peer review.
Historically, the United States and the Russian Federation both have had significant research programs on many of the topics that are vital to the safety of nuclear reactors. Unique capabilities and strengths have been developed in each country over the years. The leaders of the two countries have recognized the benefits of combining these strengths by engaging in collaborative research. This approach applies the best talents to the problems that must be addressed and it will maximize the benefits that can be derived from the available resources. The Russian International Nuclear Safety Center and the U.S. International Nuclear Safety Center collaborate on the nuclear safety projects listed below.
Development of Russian Nuclear Safety Database
Measurement and Review of Material Properties Data
Compilation of Information on Russian Nuclear Safety Research Facilities, Experiments, and Computer Codes
Development of Advanced Coupled Neutronic/Thermal Hydraulic/Mechanics Codes
Accident Management Technology Development for Russian Nuclear Power Plants
Validation of Russian Computer Codes for Transient Analysis of Design Basis Accidents
Validation of Three?Dimensional Structural Analysis Software and Models
Development of Techniques for Monitoring and Diagnostics of Sensors, Systems, and Equipment
Development of a Strategic Plan for Russian Nuclear Safety Research.
Five of the projects were initiated in January 1997; the other four projects were initiated in the middle of 1997. Some portions of these projects are being conducted in Russian laboratories and other portions are being conducted in United States laboratories.
One of the most significant accomplishment from the collaborative efforts between RINSC and USINSC has been the development of Safety Information Databases at the USINSC and at RINSC. They are accessible on the Internet at www.insc.anl.gov and www.insc.ru and they have received world-wide attention (8 million hits over the last two years).
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| Contents | Foreword | Program Overview | Armenia | Bulgaria | Czech Republic | Hungary | Kazakhstan | Lithuania | Russia | Slovakia | Ukraine | Appendix A | Appendix B | Appendix C | Contacts | | ![]() |
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The content was last modified on
08/27/2001
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