Information on Russian NPPs Currently Operating and under Construction
Overview
of VVER Units under Construction in Russia
Eight VVER units are now under construction at the Novovoronezh-2, Leningrad-2,
Baltic and Rostov sites (see Table 1).
Table 1
NPP
Unit No.
Unit Type
Design
Year of
Commissioning
2015
2016
Location
Novovoronezh-2
1
2
VVER-1200
VVER-1200
AES-2006
AES-2006
Novovoronezh,
Voronezh Region
Leningrad-2
1
2
VVER-1200
VVER 1200
AES-2006
AES-2006
2015
2017
Sosnovy Bor,
Leningrad Region
Baltic
1
VVER-1200
AES-2006
2018
Neman,
Kaliningrad Region
Rostov
2
3
VVER-1200
VVER-1000
AES-2006
V-320
2021
2014
4
VVER-1000
V-320
2019
Volgodonsk,
Rostov Region
The AES-2006 design meets all modern international safety requirements. It applies
active channels of the safety systems (duplicating each other), a melt localization
device, a passive heat removal system from the reactor containment and a passive
heat removal system from the steam generators. The design comprises protection
from external risks.
Novovoronezh-2
Novovoronezh-2 is a leading power plant of the new AES-2006 design with VVER1200.
OAO Atomenergoproekt is the general contractor for design and construction of
Novovoronezh-2.
The construction is based on the AES-2006 design developed by Atomenergoproekt
applying the VVER-1200 reactor. AEAS-2006 is a unified design of a power plant
comprising the latest achievements of the domestic engineering thought. AES-2006 is
based on the technical decisions of the AES-92 design.
The first on-site activities commenced in June 2007.
On June 24, 2008, Atomenergoproekt began concreting the foundation slab of the
reactor building of Unit 1 – the basic construction stage of Novovoronezh-2.
On July 12, 2009, the foundations of Unit 2 were laid.
1
Leningrad-2
OAO St. Petersburg Research and Design Institute Atomenergoproekt is the general
contractor for the design of Leningrad-2.
Leningrad-2 is a result of evolutionary development of the most widespread and, as a
sequence, technically perfect type of plants – an NPP with VVER-1200. Its closest
analogue if the Tianwan NPP in China, also designed by St. Petersburg AEP and
commissioned in 2007.
The first concrete was poured into the foundation slab of the Unit 1 reactor building
in 2008, which signified the beginning the basic stage of construction.
In April 2010, the construction of the Unit 2 reactor building was begun.
Baltic
OAO St. Petersburg Research and Design Institute Atomenergoproekt is the general
contractor for the design of the Baltic NPP.
Baltic is a nuclear plant of the AES-2006 series with a VVER-1200 based on the
design of Lenigrad-2.
The ceremony of laying the foundation stone of the Baltic NPP took place on
February 25, 2010.
Rostov
OAO Nizhny Novgorod Engineering Company Atomenergoproekt (NIAEP), which
has designed and operated Units 1 and 2 of the Rostov NPP, is the general contractor
for the design of Rostov 3 and 4.
The Rostov NPP is from a series of unified NPP designs with VVER-1000 meeting
the requirements of mass construction. These are series VVER units with the V-320
reactor, enhanced PGV-1000M steam generators and an electrical capacity of up to
1,100 MW each. That is, Rostov will have units with VVER-1000 (V-320) reactors
similar to the existing ones.
Preparatory work prior to the full-scale construction of Units 3 and 4 were begun in
the middle of 2009.
The construction of Unit 3 was begun in November 2009.
The full-scale construction of Unit 4 was begun in June 2010.
Technical Characteristics of VVERs of Nuclear Plants under Construction
The V-491 reactor applied in the AES-2006 design is a further improvement of the
VVER-1000 reactors and developed in line with the latest requirements and
achievements of nuclear engineering.
2
OAO OKB Gidropress is the general designer of the reactor, and Kurchatov Institute
is a scientific leader of the reactor and nuclear plant.
The reactor systems include a VVER-1200, pressurization system and four
circulation loops, each containing a PGV-1000MKP steam generator, a GCNA-1391
main circulation pump and primary circuit pipes Dn 850.
For main characteristics and parameters of the reactor in general and AES-2006
reactor equipment see Table 2.
Table 2
Parameter
Value
1. Reactor thermal rating, MW
3,200
2. Electrical rating, MW
1198.8
3. Run time at thermal rating during a year (effective),
hours per year
8,400
4. Available plant capability factor (average for NPP
lifetime), at least
90%
5. Maximum burnup, average for fuel assemblies, MW
days per kg U
up to 70
6. Maximum linear heat current, W/cm
420
7. Number of fuel assemblies per core, pieces
163
8. Coolant pressure at core outlet, absolute, MPa
16.2+0.3
9. Coolant temperature at reactor inlet, С
298.6  4
10. Coolant temperature at reactor outlet, С
11. Coolant flow rate through reactor, m3/h
12. Generated steam pressure at steam generator header
outlet, absolute, MPa
2
329.7+5
85,600+2,900
7.00+0.10
13. Generated steam temperature in steam generator shell,
287.0+1.0
14. Evaporative capacity of one steam generator (at feed
water temperature of 225°С and continuous blowout flow rate
of 15 tons per hour), tons per hour
1,600+112
С
15. Generated steam moisture at steam generator header
outlet, %, at least
16. NPP life, years
17. Heating capacity of unit, Gcal/h (MW)
0.2
50
250 (300)
3
Overview
of VVER Units Currently Operating in Russia
Novovoronezh
The Novovoronezh NPP is one of the oldest facilities of the Russian Federation's
atomic energy. When Novovoronezh 1 was started on September 30, 1964, it marked
the beginning of the history of atomic energy not only in Russia but in a number of
countries of Eastern and Central Europe.
Novovoronezh fully provides the electrical energy needs of Voronezh Region, and up
to 90% of heating needs of the town of Novovoronezh.
It is the first Russian NPP with water-moderated water cooled reactors VVER. For
more than forty years, a total of five units with VVERs have been constructed and
commissioned. Each of the currently operating reactors is a leading one, a prototype
of series power water-moderated water-cooled reactors VVER-440 and VVER-1000.
The plant was constructed in four stages:
- stage one – Unit 1 (VVER-210 in 1964);
- stage two – Unit 2 (VVER-365 in 1969);
- stage three – Units 3 and 4 (VVER-440 in 1971 and 1972);
- stage four – Unit 5 (VVER-1000 in 1980).
In 1984, after 20 years of operations, Unit 1 was shutdown, and in 1990 – Unit 2 for
their further decommissioning. At present, Novovoronezh 3, 4 and 5 are in operation.
Circulating water sources of the plant are:
- Units 3 and 4 – cooling towers;
- Unit 5 – a cooling pond.
Make-up water to the cooling towers and cooling pond comes from the Don river.
For the first time in Europe, Units 3 and 4 underwent a unique set of work to extend
their lifetime beyond the designed one for 15 years. Relevant Rostechnadzor licenses
were obtained.
After a unique refurbishment and upgrade of Unit 5, its operating life was extended
beyond the designed one, and the first Russian million-plus unit with a VVER was recommissioned on September 22, 2011.
As a result, Novovoronezh 5, which was previously a Gen II unit, now belongs to
Gen III. It fully complies with the modern Russian standards and IAEA
recommendations.
The installed capacity of Novovoronezh is 1,834 MW.
For information on the operating units of the Novovoronezh NPP see the table below.
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Unit
No.
3
4
5
Installed
capacity,
MW
417
417
1000
Reactor type
Reactor
plant type
Turbine type
Generator
type
Date of
start-up
VVER-440
VVER-440
VVER-1000
V-179
V-179
V-187
K-220-44
K-220-44
K-500-60/1500
TVV-220-2
TVV-220-2
TVV-500-4
12.12.1971
28.12.1972
31.05.1980
Considering the lessons learnt after the Fukushima-Daiichi accident, the following
has been done:
1. Stress tests of the NPP units with the issue of the 18.11.2011 Report on
Safety Analysis of the Novovoronezh NPP under Extreme External
Effects;
2. Additional mobile emergency equipment to mitigate design basis
accidents and manage beyond design basis ones was supplied:
- 7 diesel generators;
- 4 high pressure diesel pumps;
- 10 motor pumps;
3. A set of organizational and technical actions to mitigate consequences of
beyond design basis and severe beyond design basis accidents is
implemented as planned and to be completed in 2016 in the following
major areas: seismic stability, power supply, heat removal, explosion
protection, control and management of emergency preparedness.
The scheduled additional emergency actions will increase the survivability and
independence of the plant under beyond design basis accidents for 5 to 10 days, and,
hence, allow safety enhancement of the NPP in general.
Since 2001 Novovoronezh has seen a number of international peer audits and
inspections:
- the IAEA is planning to perform an OSART mission in 2015;
- WANO peer audits in 2004, 2007 and 2011;
- International insurance inspections in 2011 and 2012.
Location: Voronezh Region, distance to the satellite town of Novovoronezh) – 3.5
km; to the regional centre of Voronezh – 45 km.
Contacts: address: Russia 396072 Voronezh Region, Novovoronezh.
Tel.: +7-473-64-7-33-39; +7-915-543-45-82.
E-mail: postmaster@nvnpp.vrn.ru
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Kola
The Kola NPP is the first nuclear plant in Russia constructed beyond the Arctic
Circle.
Electrical energy generation of the Kola NPP is about 60% of the total amount of
Murmansk Region. The plant supplies energy to the Kolenergo power network of
Murmansk Region and Karelenergo power network of the Republic of Karelia.
In terms of organization, Kola is divided into the first stage (Units 1 and 2) and
second stage (Units 3 and 4) due to design differences of the VVER-400 reactors of
the V-230 design (Units 1 and 2) and of the V-213 design (Units 3 and 4).
In 1991 to 2005, a large-scale renovation of the equipment was performed on the first
stage at Units 1 and 2, which allowed making them compatible with new
requirements of the safety regulations and extending the operating life for 15 years
beyond the designed one, which was 30 years.
In 2007, reconstruction of Units 3 and 4 was begun. In 2011, Rostechnadzor issued
the license to operate Unit 3 beyond the design operating life, which was 30 years.
Lake Imandra is a source of circulating water supply for Units 1, 2, 3 and 4 of the
nuclear plant.
The installed capacity of the Kola NPP is 1,760 MW.
Or information on the operating units of the Kola NPP see the table below.
Unit
No.
1
2
3
4
Installed
capacity,
MW
440
440
440
440
Reactor type
Reactor
plant type
Turbine type
Generator
type
Date of
start-up
VVER-440
VVER-440
VVER-440
VVER-440
V-230
V-230
V-213
V-213
K-220-44
K-220-44
K-220-44
K-220-44
TVV-220-2
TVV-220-2
TVV-220-2
TVV-220-2
29.06.1973
09.17.1974
24.03.1981
11.10.1984
Considering the lessons learnt after the Fukushima-Daiichi accident, the following
has been done:
1. Stress tests of the NPP units with the issue of the 17.11.2011 Report on
Safety Analysis of the Kola NPP under Extreme External Effects;
2. Additional mobile emergency equipment to mitigate design basis
accidents and manage beyond design basis ones was supplied:
- 8 diesel generators;
- 4 high pressure diesel pumps;
- 12 motor pumps;
3. A set of organizational and technical actions to mitigate consequences of
beyond design basis and severe beyond design basis accidents is
implemented as planned and to be completed in 2016 in the following
6
major areas: seismic stability, power supply, heat removal, explosion
protection, control and management of emergency preparedness.
The scheduled additional emergency actions will increase the survivability and
independence of the plant under beyond design basis accidents for 5 to 10 days, and,
hence, allow safety enhancement of the NPP in general.
Since 2001 Kola has seen a number of international peer audits and inspections:
- the IAEA is planning to perform an OSART mission in 2014;
- WANO peer audits in 2001, 2006, 2008 and 2012;
- International insurance inspection in 2008.
The Kola NPP ranked No. 2 among the best Russian nuclear plants in 1996, 2001,
2005, 2006, 2007 and 2008, and was twice recognized the winner of the industrial
safety culture competition in 2006 and 2008.
Location: Kola Peninsula, distance to the satellite town (Polyarnie Zori) – 11 km;
distance to the regional centre (Murmansk) – 170 km.
Contacts: address: Russia 184230 Murmansk Region, Polyarnie Zori.
Tel.: +7-815-32-4-36-41; +7-921-280-00-89.
E-mail: kolanpp@kolatom.murmansk.ru
Balakovo
The Balakovo NPP is the largest power producer in Russia.
The NPP operates four units with VVER-1000 (design V-320). Each of the units has
a two-circuit heat flow system. Each of the unified units is a separately standing
building consisting of a reactor building, turbine hall, deaerator floor and electrical
equipment room.
The primary equipment is located together with the reactor in a reinforced concrete
containment lined with sheet steel inside.
A cooling pond is a source of circulating water supply for Units 1, 2, 3 and 4. Makeup of the cooling pond comes from the Saratov Reservoir on the Volga river.
Installed capacity of the Balakovo NPP is 4,000 MW.
For information on the operating units of the NPP see the table below.
Unit
No.
1
2
3
4
Installed
capacity,
MW
1000
1000
1000
1000
Reactor type
Reactor
plant type
Turbine type
Generator
type
Date of
start-up
VVER-1000
VVER-1000
VVER-1000
VVER-1000
V-320
V-320
V-320
V-320
K-1000-60/50
K-1000-60/50
K-1000-60/50
K-1000-60/50
TVV-1000-2
TVV-1000-2
TVV-1000-2
TVV-1000-2
28.12.1985
08.10.1987
24.12.1988
11.04.1993
7
Considering the lessons learnt after the Fukushima-Daiichi accident, the following
has been done:
1. Stress tests of the NPP units with the issue of the 17.11.2011 Report on
Safety Analysis of the Kola NPP under Extreme External Effects;
2. Additional mobile emergency equipment to mitigate design basis
accidents and manage beyond design basis ones was supplied:
- 8 diesel generators;
- 4 high pressure diesel pumps;
- 12 motor pumps;
3. A set of organizational and technical actions to mitigate consequences of
beyond design basis and severe beyond design basis accidents is
implemented as planned and to be completed in 2016 in the following
major areas: seismic stability, power supply, heat removal, explosion
protection, control and management of emergency preparedness.
The scheduled additional emergency actions will increase the survivability and
independence of the plant under beyond design basis accidents for 5 to 10 days, and,
hence, allow safety enhancement of the NPP in general.
Within the industrial "Programme of Increasing Electrical Power Generation at
Operating NPP Units for 2011 to 2015", Balakovo 2 and 4 were put into commercial
operation at 104% of the designed capacity. Balakovo 1 and 3 were put into
experimental commercial operation at 104% of the designed capacity.
Since 2001 Balakovo has seen a number of international peer audits and inspections:
- the IAEA – OSART in 2008, OSART (FU) in 2010;
- WANO peer audits in 2003 and 2006;
- International insurance inspections in 2009 and 2012.
The Balakovo NPP ranked No. 1 among the best Russian nuclear plants in 1995,
1999, 2000, 2003, 2005, 2006, 2007, 2008 and 2011, No. 2 in 2002 and 2010, and
was thrice recognized the winner of the industrial safety culture competition in 2006,
2007 and 2009.
The Balakovo NPP is a prize winner of the 14th International Competition "Gold
Medal for European Quality".
Location: Saratov Region, distance to the satellite town of Balakovo – 12.5 km;
distance to the regional centre of Saratov – 145 km.
Contacts: address: Russia 413866 Saratov Region, Balakovo.
Tel.: +7-8453-49-74-00;
+7- 905- 327- 91- 38.
E-mail: npp@balaes.ru
8
Kalinin
The Kalinin NPP generates 70% of the total electrical energy produced in Tver
Region. The nuclear plant generates power to the Unified Power System of the
Centre of Russia and farther via high voltage lines to Tver, Moscow, St. Petersburg,
Vladimir and Cherepovets.
Owing to its geographical situation, Kalinin carries out high voltage transit of
electrical power. The outdoor switchyard circuit ensures reliable power supply to the
consumers, generating power under all operating modes of the nuclear plant.
Kalinin comprises two stages. The first one includes two units with an installed
capacity of 1,000 MW, each located in two containments of the reactor buildings.
The auxiliary buildings and structures are connected with the main building with a
system of walk bridges and overpasses. Units 1 and 2 were constructed in 1984 and
1986, respectively.
The construction of the second stage within Units 3 and 4 was begun in 1984.
The power start-up of Kalinin 3 took place on December 16, 2004, and the units was
put into commercial operation on November 8, 2005. Unit 3 was constructed as a
separately standing special building with relevant extensions of the first stage
auxiliaries.
Rostechnadzor issued the license in 2007, and construction of Kalinin 4 was resumed
on November 12, 2007. The construction of Unit 4 became the largest investment
project of Tver Region for the last few years. On September 25, 2012, Kalinin 4 was
put into commercial operation.
The sources of circulation water supply of the NPP units are:
- for Units 1, 2 and 3 – Lake Udomlya;
- for Unit 4 – the cooling towers made up from Lake Udomlya.
The installed capacity of the Kalinin NPP is 4,000 MW.
For information on the operating units of the nuclear plant see the table below.
Unit
No.
1
2
3
4
Installed
capacity,
MW
1000
1000
1000
1000
Reactor type
Reactor
plant type
Turbine type
Generator
type
Date of
start-up
VVER-1000
VVER-1000
VVER-1000
VVER-1000
V-338
V-338K
V-320
V-320
K-1000-0/1500
К-1000-0/1500
K-1000-0/3000
K-1000-0/3000
TVV-1000-4
TVV-1000-4
TVV-1000-2
TVV-1000-2
09.05.1984
03.12.1986
16.12.2004
25.09.2012
Considering the lessons learnt after the Fukushima-Daiichi accident, the following
has been done:
1. Stress tests of the NPP units with the issue of the 18.11.2011 Report on
Safety Analysis of the Kola NPP under Extreme External Effects;
2. Additional mobile emergency equipment to mitigate design basis
accidents and manage beyond design basis ones was supplied:
9
- 8 diesel generators;
- 4 high pressure diesel pumps;
- 12 motor pumps;
3. A set of organizational and technical actions to mitigate consequences of
beyond design basis and severe beyond design basis accidents is
implemented as planned and to be completed in 2016 in the following
major areas: seismic stability, power supply, heat removal, explosion
protection, control and management of emergency preparedness.
The scheduled additional emergency actions will increase the survivability and
independence of the plant under beyond design basis accidents for 5 to 10 days, and,
hence, allow safety enhancement of the NPP in general.
Within the industrial "Programme of Increasing Electrical Power Generation at
Operating NPP Units for 2011 to 2015", Kalinin 1, 2 and 3were put into experimental
commercial operation at 104% of the designed capacity.
Since 2001 Kalinin has seen WANO peer audits in 2004, 2008, 2010 and 2012.
The Kalinin NPP ranked No. 1 among the best Russian nuclear plants in 2002 and
No. 2 in 2003, 2004 and 2011.
Location: Tver Region, distance to the satellite town of Udomlya – 4 km;
distance to the regional centre of Tver – 125 kmм.
Contacts: address: Russia 171841 Tver Region, Udomlya.
Tel.: +7-482-55- 6- 72- 74.
E-mail: knpp@knpp.ru
Rostov
The Rostov NPP is one of the largest energy facilities in the south of Russia. It is the
most southern of the Russian NPPs. The plant provides 40% of electrical power in
Rostov Region. Electrical power is supplied via five power transmission lines LEP500 to Volgograd and Rostov regions, Krasnodar and Stavropol territories, and via
two power transmission lines to the city of Volgodonsk.
The Rostov NPP belongs to a series of unified NPP designs with VVER-1000
meeting the requirements of series construction. The entire capacity of the NPP was
intended to cover the demand of the united system of the Northern Caucasus.
The full-scale construction of the Rostov nuclear plant was begun in October 1979. In
1990, it was suspended, and the plant was taken to conservation. By the time of
suspension, Unit 1 was 95% ready, Unit 2 was 30% ready, a foundation slab of Unit 3
was constructed, and a pit was excavated for Unit 4.
In 2000, Gosatomnadzor of Russia issued the construction license, and the
construction of Rostov 1 with VVER-1000 was continued. On March 30, 2001, the
turbine generator of Unit 1 was connected to the Unified Power System of Russia.
10
The construction of Unit 2 with VVER-1000 was resumed in 2002. In 2006, the
activities were put on a wide scale. In 2010, Rostov 2 was put into commercial
operation.
Rostov 3 and 4 are currently under construction and to be started in 2014 and 2017,
respectively.
A cooling pond is a source of circulating water supply of Units 1 and 2. The cooling
pond is made up from the Tsimlyansk reservoir on the Don river.
The installed capacity of the Rostov NPP is 2,000 MW.
For information on the operating NPP units see the table below.
Unit
No.
1
2
Installed
capacity,
MW
1000
1000
Reactor type
Reactor
plant type
Turbine type
Generator
type
Date of
start-up
VVER-1000
VVER-1000
V-320
V-320
K-1000-0/1500
K-1000-0/1500
TVV-1000-4
TVV-1000-4
30.03.2001
16.03.2010
Considering the lessons learnt after the Fukushima-Daiichi accident, the following
has been done:
1. Stress tests of the NPP units with the issue of the 18.11.2011 Report on
Safety Analysis of the Kola NPP under Extreme External Effects;
2. Additional mobile emergency equipment to mitigate design basis
accidents and manage beyond design basis ones was supplied:
- 4 diesel generators;
- 2 high pressure diesel pumps;
- 6 motor pumps;
3. A set of organizational and technical actions to mitigate consequences of
beyond design basis and severe beyond design basis accidents is
implemented as planned and to be completed in 2016 in the following
major areas: seismic stability, power supply, heat removal, explosion
protection, control and management of emergency preparedness.
Within the industrial "Programme of Increasing Electrical Power Generation at
Operating NPP Units for 2011 to 2015", Rostov 1 was put into experimental
commercial operation at 104% of the designed capacity. Now, the documents are
drafted to take the unit to commercial operation at 104% of the designed capacity.
Documents are being prepared for Unit 2 to receive authorization for experimental
commercial operation at 104% of the designed capacity.
Since 2001 Rostov has seen a number of international peer audits, missions and
inspections:
- the IAEA – OSART in 2005, OSART (FU) in 2007;
- WANO peer audits in 2003, 2006. 2010 and 2012;
- International insurance inspection in 2012.
11
The Rostov NPP ranked No. 1 among the best Russian nuclear plants in 2004 and
2011, No. 2 in 2005, and was thrice recognized the winner of the industrial safety
culture competition in 2005, 2008 and 2010.
Location: Rostov Region, distance to the satellite town of Volgodonsk – 16
km; distance to the regional centre of Rostov-on-Don – 205 km.
Contacts: address: Russia 347388 Rostov Region, Volgodonsk-28.
Tel.: +7-863-92-3-06-33;
+7- 903- 403- 29- 52.
E-mail: admin@rosnpp.org.ru
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