Nuclear Power Plants World Wide

Tihange

Nuclear Street News — Mon, 14 May 2012 13:44:11 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 5/14/2012 9:44:11 AM

Tihange

Reactor: PWR

Location: On the right bank of the Meuse River in the Belgian district of Tihange, part of Huy Municipality.

1975 Units 1 became operational

1982 Unit 2 became operational

1985 Unit 3 became operational

Tags: belgium

Bushehr Unit 1

Cam Abernethy — Tue, 08 May 2012 16:34:00 GMT

Current Revision posted to Nuclear Power Plants World Wide by Cam Abernethy on 5/8/2012 12:34:00 PM

Reactor: PWR

Output: 915 MWe

Location: Bushehr, Iran

In the News: Bushehr

- 1975 - Construction of the plant was started

- 1979 - Construction stopped after Islamic revolution of Iran

- 1995 - Contract for finishing the plant was signed between Iran and the Russian Ministry for Atomic Energy

- 2007 - Construction almost ground to a halt but a renewed agreement was reached

- 2010 - Official launch ceremony was held

- September 2011 - Connected to the grid

- February 2012 Reached 75 percent of its power generation capacity

- 2nd QTR 2012 - Expected to reach full operating capacity

Tags: bushehr

CANDU

Nuclear Street News — Mon, 07 May 2012 16:18:40 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 5/7/2012 12:18:40 PM

CANDU stands for "CANada Deuterium Uranium".

It's a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel.

Use of natural uranium as a fuel

CANDU is the most efficient of all reactors in using uranium: it uses about 15% less uranium than a pressurized water reactor for each megawatt of electricity produced
Use of natural uranium widens the source of supply and makes fuel fabrication easier. Most countries can manufacture the relatively inexpensive fuel
There is no need for uranium enrichment facility
Fuel reprocessing is not needed, so costs, facilities and waste disposal associated with reprocessing are avoided
CANDU reactors can be fuelled with a number of other low-fissile content fuels, including spent fuel from light water reactors. This reduces dependency on uranium in the event of future supply shortages and price increases

Use of heavy water as a moderator

Heavy water (deuterium oxide) is highly efficient because of its low neutron absorption and affords the highest neutron economy of all commercial reactor systems. As a result chain reaction in the reactor is possible with natural uranium fuel
Heavy water used in CANDU reactors is readily available. It can be produced locally, using proven technology. Heavy water lasts beyond the life of the plant and can be re-used

CANDU reactor core design

Reactor core comprising small diameter fuel channels rather that one large pressure vessel
Allows on-power refueling - extremely high capability factors are possible
The moveable fuel bundles in the pressure tubes allow maximum burn-up of all the fuel in the reactor core
Extends life expectancy of the reactor because major core components like fuel channels are accessible for repairs when needed

CANDU 6

The CANDU 6 power reactor offers a combination of proven and superior state-of-the-art technology. It was designed specifically for electricity production, unlike other major reactor types that evolved from other uses. This focused development is one of the reasons that CANDU has such high fuel efficiency.

CANDU 6 is our 700 MWe class nuclear power reactor. The first CANDU 6 plants went into service in the early 1980s as leading-edge technology, and the design has continuously evolved since to maintain superior technology and performance.

It was licensed in the early 1980s in Canada, Argentina and the Republic of Korea. In 1996, Cernavoda Unit 1 was licensed in Romania, and Wolsong Unit 2 was licensed in Korea. Wolsong Units 3 and 4 were licensed in Korea in 1997 and 1999 respectively. Qinshan Units 1 and 2 were licensed in China in 2002 and 2003 respectively. In 2007, Cernavoda Unit 2 was licensed in Romania. These units came into service ahead of schedule and on budget. There are 11 CANDU 6 units in operation.

Enhanced CANDU 6

The Enhanced CANDU 6 (EC6) Generation III reactor design is the only reactor that offers:

natural uranium fuelling
a design based on our highly successful CANDU 6 reactors
superior safety performance and economics
very high localization
suitability for small and medium electric grids

The EC6 is a 700 MWe class heavy-water moderated and heavy-water cooled pressure tube reactor. Heavy water is a natural form of water used as a moderator to slow down the fission chain reaction neutrons in the reactor. It is one of the most efficient moderators and enables the CANDU design to use natural uranium as fuel, which is unique to CANDU reactors. The use of natural uranium increases a country’s energy independence as fuel can be manufactured locally, and reprocessing and associated issues can be avoided.

Heavy water coolant passes through the reactor core and removes the heat generated by the fission chain reactions. This heated reactor coolant heats light (ordinary) water and converts it to steam, which drives a turbine-generator to produce electricity.

The EC6 reactor is the evolution of the proven CANDU 6 design. It is based on the Qinshan Phase III CANDU 6 plant in China, designed to meet industry and public expectations of nuclear power generation that is safe, reliable and environmentally friendly.

It has been enhanced by using the experience and feedback that AECL gained in the development, design, construction and operation of 11 CANDU 6 units operating in five countries. CANDU 6 reactors are performing well on four continents with over 150 reactor-years of excellent and safe operation.

While retaining the basic features of the CANDU 6 design, the EC6 reactor incorporates innovative features and state-of-the-art technologies that enhance safety, operation and performance.

The latest CADDS tools and innovative integrated systems linking material management, documentation, safety analysis and project execution databases are used to ensure that accurate and complete configuration management can be readily maintained by the plant owner.

The EC6 reactor has projected an average annual operational performance factor of 94% and 92% lifetime including mid-life retubing. The performance factor is the ratio of available capacity to the theoretically possible capacity, and this characterizes the reliability of the plant. In recent years, the global CANDU 6 fleet achieved an average lifetime performance factor of 89%, which ranked the fleet in the world’s top reactor performance echelons. In the last decade, three of the CANDU units in South Korea ranked in the top 10 list for world reactors.

The EC6 reactor design benefits from the proven principles and characteristics of the CANDU 6 design and decades of operation.

Proven CANDU strengths include:

Two independent safety shutdown systems
Refuelling during on-power operation
Passive water tank located in the containment
Modular, horizontal fuel channel core
Separate low-temperature, low-pressure moderator that provides inherently passive heat sinks by permitting heat to be removed from the reactor core under abnormal conditions
Reactor vault that is filled with cool light water that surrounds the reactor core and provides an additional passive heat sink for mitigation of severe accidents
Reactor building access for maintenance activities during on-power operation

Tags: CANDU

CANDU

Nuclear Street News — Mon, 07 May 2012 16:04:22 GMT

Revision 2 posted to Nuclear Power Plants World Wide by Nuclear Street News on 5/7/2012 12:04:22 PM

CANDU stands for "CANada Deuterium Uranium".

It's a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel.

Use of natural uranium as a fuel

CANDU is the most efficient of all reactors in using uranium: it uses about 15% less uranium than a pressurized water reactor for each megawatt of electricity produced
Use of natural uranium widens the source of supply and makes fuel fabrication easier. Most countries can manufacture the relatively inexpensive fuel
There is no need for uranium enrichment facility
Fuel reprocessing is not needed, so costs, facilities and waste disposal associated with reprocessing are avoided
CANDU reactors can be fuelled with a number of other low-fissile content fuels, including spent fuel from light water reactors. This reduces dependency on uranium in the event of future supply shortages and price increases

Use of heavy water as a moderator

Heavy water (deuterium oxide) is highly efficient because of its low neutron absorption and affords the highest neutron economy of all commercial reactor systems. As a result chain reaction in the reactor is possible with natural uranium fuel
Heavy water used in CANDU reactors is readily available. It can be produced locally, using proven technology. Heavy water lasts beyond the life of the plant and can be re-used

CANDU reactor core design

Reactor core comprising small diameter fuel channels rather that one large pressure vessel
Allows on-power refueling - extremely high capability factors are possible
The moveable fuel bundles in the pressure tubes allow maximum burn-up of all the fuel in the reactor core
Extends life expectancy of the reactor because major core components like fuel channels are accessible for repairs when needed

Tags: CANDU, PHWR, heavy water reactors

CANDU

Nuclear Street News — Mon, 07 May 2012 16:04:01 GMT

Revision 1 posted to Nuclear Power Plants World Wide by Nuclear Street News on 5/7/2012 12:04:01 PM

CANDU stands for "CANada Deuterium Uranium".

It's a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel.

Use of natural uranium as a fuel

CANDU is the most efficient of all reactors in using uranium: it uses about 15% less uranium than a pressurized water reactor for each megawatt of electricity produced
Use of natural uranium widens the source of supply and makes fuel fabrication easier. Most countries can manufacture the relatively inexpensive fuel
There is no need for uranium enrichment facility
Fuel reprocessing is not needed, so costs, facilities and waste disposal associated with reprocessing are avoided
CANDU reactors can be fuelled with a number of other low-fissile content fuels, including spent fuel from light water reactors. This reduces dependency on uranium in the event of future supply shortages and price increases

Use of heavy water as a moderator

Heavy water (deuterium oxide) is highly efficient because of its low neutron absorption and affords the highest neutron economy of all commercial reactor systems. As a result chain reaction in the reactor is possible with natural uranium fuel
Heavy water used in CANDU reactors is readily available. It can be produced locally, using proven technology. Heavy water lasts beyond the life of the plant and can be re-used

CANDU reactor core design

Reactor core comprising small diameter fuel channels rather that one large pressure vessel
Allows on-power refueling - extremely high capability factors are possible
The moveable fuel bundles in the pressure tubes allow maximum burn-up of all the fuel in the reactor core
Extends life expectancy of the reactor because major core components like fuel channels are accessible for repairs when needed

Tags: CANDU, PHWR, heavy water reactors

Pressurized Heavy Water Reactor (PHWR)

Nuclear Street News — Fri, 27 Apr 2012 16:29:02 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/27/2012 12:29:02 PM

A pressurized heavy water reactor (PHWR) is a nuclear power reactor, commonly using unenriched natural uranium as its fuel, that uses heavy water (deuterium oxide D₂O) as its coolant and moderator. The heavy water coolant is kept under pressure, allowing it to be heated to higher temperatures without boiling, much as in a typical pressurized water reactor. While heavy water is significantly more expensive than ordinary light water, it yields greatly enhanced neutron economy, allowing the reactor to operate without fuel enrichment facilities (mitigating the additional capital cost of the heavy water) and generally enhancing the ability of the reactor to efficiently make use of alternate fuel cycles.

Below is a diagram of a typical Pressurized Heavy Water Reactor:

List of PHWRs by country:

Argentina

- Atucha 1 & 2

- Embalse

India

- Tarapur 3 & 4

- Rajasthan 1-6 (with 2 more under construction)

- Madras 1 & 2

- Narora 1 & 2

- Kakrapar 1 & 2 (3 & 4 under construction)

- Kaiga 1-4

Pakistan

- Kanupp 1

Romania

- Cernavoda 1 & 2

South Korea

- Wolsong 1-4

Tags: nuclear plants

Gen4 Power Module (Hyperion Power Generator)

Nuclear Street News — Wed, 25 Apr 2012 16:22:08 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/25/2012 12:22:08 PM

A New Paradigm for Power Generation

Nuclear Power is a Key Element of Our Energy Mix

In order to meet the planet’s ever expanding need for affordable energy, a number of different types of clean, emission-free technologies must be developed and employed. Nuclear power, with its ability to provide robust, continuous, and reliable energy – regardless of weather conditions – must be part of this diverse mix. However, conventional large nuclear power plants, due to construction expense and the time required to build them, must be augmented with a smaller solution.

Small & Modular Nuclear Power Reactors (SMRs)

That “smaller solution” is the category of power reactors known as Small & Modular nuclear power Reactors (SMRs). The history of SMRs is about as long as the commercial use of large nuclear power plants. The fuels and technology included in today’s SMR designs have been studied for over 50 years, and some units went online decades ago. SMRs provide the benefits of larger nuclear power plants – clean, continuous, reliable energy with no greenhouse gas emissions – yet they require very little space in which to operate. SMRs can be transported to sites and engaged without the transportation and construction costs of big nuclear power plants. Sealed and self-contained, they offer a safe energy solution for areas of the globe where nuclear proliferation is a concern. But unlike any other clean energy generation, SMRs operate when the wind doesn’t blow and the sun doesn’t shine.

The Gen4 Power Module (formerly the Hyperion Power Generator)

The Gen4 Module is a next generation design that uses a liquid metal cooled, uranium nitride fueled, fast-spectrum reactor that employs control rods for reactivity control. The reactor has been designed to deliver 70 MW of heat (25 MW of electricity) for a 10-year lifetime, without refueling.

Key advantages of the Gen4 Module design are:

Advanced reactor design – Use of advanced reactor concepts provides for a safer and simpler reactor, elimination of many potential accident scenarios that affect LWRs, and elimination of complex reactor systems.
Small reactor – A smaller reactor is more appropriately sized for smaller generation requirements, can directly replace existing diesel fueled generators, and requires no upgrade to existing small electricity distribution systems.
10-year power module replacement – The Gen4 Module provides 25 MWe continuously for 10 years on its initial fuel load (compared to an 18 to 24 month cycle for current light water reactors). No on-site refueling is required. After 10 years the entire reactor module is replaced.
Underground containment vault – The reactor is sited in an underground containment vault to provide isolation from the environment, prevent intrusion or tampering, and avoid harm from natural disasters.
Factory-assembled transportable power modules – Factory assembly allows for standard designs, superior quality control, and faster construction and on-site deployment.

A standardized design will offer several advantages:

Manufacturing process controls will be uniform and will not vary between units.
Nuclear fabrication and assembly will be completed at the factory before the unit is shipped, minimizing the nuclear construction capabilities that are necessary on site.
On site construction activities will be limited to the reactor vault, the non-nuclear systems, placement of the Gen4 Module in the vault, and connection to the Gen4 Module to non-nuclear systems and controls. This will significantly reduce the on-site construction complexity and result in a faster construction schedule.
Gen4 Energy will provide standard operating procedures, operator training, licensing support, technical support, in-service engineering, and safety analysis, significantly reducing the nuclear expertise and staffing that is required of the owner/operator.

Key material selections include:

Lead Bismuth Eutectic (LBE) coolant -The core coolant is LBE, which is non-reactive to air and water, with a mixed mean exit temperature of 500C. A solid phase oxygen control system is used to control the oxygen level in the coolant to maintain a protective coating on structural surfaces, limiting corrosion.
Uranium Nitride (UN) fuel- The fuel consists of 19.75% enriched (non weapons grade) UN pellets contained in clad tubes made of HT-9. These high-temperature ceramic material pellets deter the ability to separate plutonium from spent fuel.
Stainless Steel structural materials (HT-9 and T-91)
Quartz radial reflector
B₄C control rods for reactivity control -There are three independent reactivity shut-down systems in the core: a shutdown rod system composed of six boron carbide (B₄C) rods, a control rod system comprising 12 boron carbide (B₄C) rods and a reserve shutdown system consisting of a central cavity into which B₄C balls may be inserted. Each of the three systems can independently take the core to long-term cold shutdown. The rod shutdown and the ball shutdown systems perform this safety function automatically and instantaneously when triggered.

Tags: gen4

Gen4 Power Module (Hyperion Power Generator)

Nuclear Street News — Wed, 25 Apr 2012 16:21:58 GMT

Revision 8 posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/25/2012 12:21:58 PM

A New Paradigm for Power Generation

Nuclear Power is a Key Element of Our Energy Mix

Small & Modular Nuclear Power Reactors (SMRs)

The Gen4 Power Module (formerly the Hyperion Power Generator)

Key advantages of the Gen4 Module design are:

Advanced reactor design – Use of advanced reactor concepts provides for a safer and simpler reactor, elimination of many potential accident scenarios that affect LWRs, and elimination of complex reactor systems.
Small reactor – A smaller reactor is more appropriately sized for smaller generation requirements, can directly replace existing diesel fueled generators, and requires no upgrade to existing small electricity distribution systems.
10-year power module replacement – The Gen4 Module provides 25 MWe continuously for 10 years on its initial fuel load (compared to an 18 to 24 month cycle for current light water reactors). No on-site refueling is required. After 10 years the entire reactor module is replaced.
Underground containment vault – The reactor is sited in an underground containment vault to provide isolation from the environment, prevent intrusion or tampering, and avoid harm from natural disasters.
Factory-assembled transportable power modules – Factory assembly allows for standard designs, superior quality control, and faster construction and on-site deployment.

A standardized design will offer several advantages:

Manufacturing process controls will be uniform and will not vary between units.
Nuclear fabrication and assembly will be completed at the factory before the unit is shipped, minimizing the nuclear construction capabilities that are necessary on site.
On site construction activities will be limited to the reactor vault, the non-nuclear systems, placement of the Gen4 Module in the vault, and connection to the Gen4 Module to non-nuclear systems and controls. This will significantly reduce the on-site construction complexity and result in a faster construction schedule.
Gen4 Energy will provide standard operating procedures, operator training, licensing support, technical support, in-service engineering, and safety analysis, significantly reducing the nuclear expertise and staffing that is required of the owner/operator.

Key material selections include:

Lead Bismuth Eutectic (LBE) coolant -The core coolant is LBE, which is non-reactive to air and water, with a mixed mean exit temperature of 500C. A solid phase oxygen control system is used to control the oxygen level in the coolant to maintain a protective coating on structural surfaces, limiting corrosion.
Uranium Nitride (UN) fuel- The fuel consists of 19.75% enriched (non weapons grade) UN pellets contained in clad tubes made of HT-9. These high-temperature ceramic material pellets deter the ability to separate plutonium from spent fuel.
Stainless Steel structural materials (HT-9 and T-91)
Quartz radial reflector
B₄C control rods for reactivity control -There are three independent reactivity shut-down systems in the core: a shutdown rod system composed of six boron carbide (B₄C) rods, a control rod system comprising 12 boron carbide (B₄C) rods and a reserve shutdown system consisting of a central cavity into which B₄C balls may be inserted. Each of the three systems can independently take the core to long-term cold shutdown. The rod shutdown and the ball shutdown systems perform this safety function automatically and instantaneously when triggered.

Tags: small modular reactors, hyperion

Small Modular Reactors

Nuclear Street News — Wed, 25 Apr 2012 16:08:31 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/25/2012 12:08:31 PM

Below is a list of the Small Modular Reactor Designs:

Babcock & Wilcox mPower Reactor

Holtec HI-SMUR 140

Gen4 Power Module (Hyperion Power Generation)

NuScale Power

Westinghouse

Tags: babcock wilcox

Gen4 Power Module (Hyperion Power Generator)

Cam Abernethy — Wed, 25 Apr 2012 12:25:36 GMT

Revision 7 posted to Nuclear Power Plants World Wide by Cam Abernethy on 4/25/2012 8:25:36 AM

A New Paradigm for Power Generation

Nuclear Power is a Key Element of Our Energy Mix

Small & Modular Nuclear Power Reactors (SMRs)

The GEN4 Power Module (Hyperion Power Module)

The Hyperion Power Module (HPM) is the frontrunner in the SMR industry. The HPM is one of the smallest, safest, and simplest designs. Hyperion Power is deeply concerned about the state of the environment, needless human suffering, and the search for energy independence – vital not just to the U.S., but to every nation on the planet. Hyperion Power believes that these concerns can be met through the safe deployment of SMRs and so is dedicated to realizing the full potential of this small but mighty power module – the HPM. Clean, safe, affordable energy should be available to everyone – even in the most remote locations.

Industry & Community Benefits
The Hyperion Power Module (HPM) offers a perfect “distributed” independent energy solution for remote locations that are too difficult or expensive to reach with traditional electrical grid systems from one large, centrally-located power plant. Each HPM-based electric plant generates 25MW of electricity and can be configured for steam only, co-generation, or electricity only.

An HPM-based power plant can supply enough power for:

20,000+ American-style homes, or a …
Large hospital complex
Entire government complex
Irrigation systems
Water treatment & distribution site
Waste – sewage facility
Heavy oil recovery
Refugee community
Emergency – disaster response center
Military installation
University or college
Mining or drilling operation
Industrial center or factory
Corporate data centers
And more …

HPM power plants can also be “teamed” in groups of two or more to provide additional power. By teaming multiple units, a medium to large-size power plant can be constructed years faster than a plant constructed on site in the traditional manner.

Hyperion Power Module Product Characteristics
1. Transportable

Unit will measure approximately 1.5m wide x 2.5m tall
Fits into a standard fuel transport container
Transported via ship, rail, or truck
Modular design for easy and safe transport

2. Sealed Core – Safe and Secure

Factory sealed; no in-field refueling, closed fuel cycle
Returned to the factory for fuel and waste disposition

3. Safety

System will handle any accident through a combination of inherent and engineered features
Inherent negative feedback keeps the reactor stable and operating at a constant temperature
Sited underground, out of sight
Proliferation-resistant; never opened once installed

4. Operational Simplicity

Operation limited to reactivity adjustments to maintain constant temperature output of 500C
Produces power for 8 to 10 years depending on use

5. Minimal In-Core Mechanical Components

Operational reliability is greatly enhanced by the reduction of moving mechanical parts

6. Isolated Power Production

Electric generation components requiring maintenance are completely separated from the reactor
Allows existing generation facilities to be retrofitted
The Hyperion Power Module will be licensed by national and international regulatory authorities.

Reactor Power                        70MW thermal
Electrical Output                     25MW electric
Lifetime                                  8 -10 years
Size                                       1.5w x 2.5h
Weight (ton)                            Less than 50
Structure Material                    Stainless Steel
Coolant                                   PbBi
Fuel                                        Stainless clad, uranium nitride
Enrichment (% U-235)              <20%
Refuel on Site                          No
Sealed Core                            Yes
License                                   Design Certification
Passive Shutdown                   Yes
Active Shutdown                      Yes
Transportable                          Yes – intact core
Factory Fueled                        Yes
Safety & Control Elements       Two redundant shutdown systems & reactivity control rods

Tags: small modular reactors, hyperion

Fukushima Nuclear Crisis Video 3/17 - 3/19

Nuclear Street News — Wed, 04 Apr 2012 13:57:25 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/4/2012 9:57:25 AM

March 17, 2011 - Water Cooling of Reactors

(Please visit the site to view this video)

March 18, 2011 - WNA Director General John Ritch

(Please visit the site to view this video)

Tags: Fukushima

Fukushima Nuclear Crisis Video 3/14 - 3/16

Nuclear Street News — Wed, 04 Apr 2012 13:57:04 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/4/2012 9:57:04 AM

March 14, 2011 - Explosion Explained

(Please visit the site to view this video)

March 16 - Unit 1, 2, 3 Explosion

(Please visit the site to view this video)

Tags: Fukushima

Harris Units 2 & 3

Nuclear Street News — Wed, 04 Apr 2012 13:06:58 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/4/2012 9:06:58 AM

Harris Units 2 & 3

Licensing Status: Scheduled

Site: Existing Site Shearon Harris

Reactor: Westinghouse Advanced Passive 1000 (AP1000)
Pressurized Water Reactors (PWRs)

Projected Online: 2019 - 2020

In the News: Shearon Harris Units 2 & 3

NRC Application Review Schedule

Key Milestones	Completion Date Actual - A Target - T
Application Tendered	02/19/08 - A
Acceptance Review
Acceptance Review Start	02/20/08 - A
Docketing Decision Letter Issued/Acceptance Review Complete	04/17/08 - A
Review Schedule Established/Schedule Letter Issued to Applicant	05/16/08 - A
Safety Review
Phase A - Requests for Additional Information (RAIs) Issued to Applicant (Formerly Phases 1, 2, and 3)	04/20/10 - A
Phase B - Advanced Final Safety Evaluation Report (SER) without Open Items (Formerly Phase 4)	04/13 - T*
Phase C - ACRS Review of Advanced Final SER (Formerly Phase 5)	07/13 - T*
Phase D - Final SER (Formerly Phase 6)	09/13 - T*
Environmental Review
Phase 1 - Environmental impact statement (EIS) summary report issued	11/18/08 - A
Phase 2 - Draft EIS issued to EPA	01/2013 - T
Phase 3 - Response to public comments on draft EIS completed	06/2013 - T
Phase 4 - Final EIS issued to EPA	01/2014 - T
Hearing
Commission or ASLB hold mandatory hearing
License
Commission decision on issuance of COL application

*Dates do not yet reflect the recent changes to the Westinghouse and Vogtle (reference COL) review schedules.

Additional information can be found at http://www.nrc.gov/reactors/new-reactors/col/harris.html

Tags: harris

Comanche Peak

Nuclear Street News — Wed, 04 Apr 2012 13:04:04 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/4/2012 9:04:04 AM

Comanche Peak Units 3 & 4

Licensing Status: Scheduled Dependent on DC Review

Site: Existing Site Comanche Peak

Reactor: United States Advanced Pressurized Water Reactor (US-APWR)

Projected Online: May 2018

In the News: Comanche Peak

NRC Application Review Schedule

Key Milestones	Completion Date Actual - A Target - T
Application Tendered	09/19/08 - A
Acceptance Review
Acceptance Review Start	09/22/08 - A
Docketing Decision Letter Issued/Acceptance Review Complete	12/02/08 - A
Review Schedule Established/Schedule Letter Issued to Applicant	03/16/09 - A
Safety Review
Phase 1 - Requests for Additional Information (RAIs) Issued to Applicant	10/09/09 - A
Phase 2 - SER with Open Items issued	03/12-T
Phase 3 - ACRS Review of SER with Open Items Complete	07/12-T
Phase 4 - Advanced SER with no Open Items Issued	12/12-T
Phase 5 - ACRS Review of SER with no Open Items Complete	03/13-T
Phase 6 - Final SER Issued	06/13-T
Environmental Review
Phase 1 - Environmental impact statement (EIS) summary report issued	07/02/09 - A
Phase 2 - Draft EIS Complete	08/06/10 - A
Phase 3 - Public Comment Period for DEIS ends	10/27/10 - A
Phase 4 - Final EIS issued	05/13/11 - A
Hearing
Commission or ASLB hold mandatory hearing	12/14 - T
License
Commission decision on issuance of COL application	12/14 - T

On December 7, 2011, the NRC staff revised the review schedule for the Comanche Peak Nuclear Power Plant, Units 3 and 4 Combined License Application.

Additional information can be found at http://www.nrc.gov/reactors/new-reactors/col/comanche-peak.html

Tags: comanche peak

Bellefonte Units 3 & 4

Nuclear Street News — Wed, 04 Apr 2012 13:00:53 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/4/2012 9:00:53 AM

Bellefonte Units 3 & 4

Licensing Status: Review Suspended 9/29/2010

Site: TVA's Bellefonte site near Scottsboro in Jackson County, Alabama

Reactor: Westinghouse Advanced Passive 1000 (AP1000)
Pressurized Water Reactors (PWRs)

Projected Online: Unit 3 - 2017
Unit 4 – 2019

In the News: Bellefonte Units 3 & 4

NRC Application Review Schedule

Key Milestones	Completion Date Actual - A Target - T
Application Tendered	10/30/07 - A
Acceptance Review
Acceptance Review Start	11/07/07 - A
Docketing Decision Letter Issued/Acceptance Review Complete	01/18/08 - A
Review Schedule Established/Schedule Letter Issued to Applicant	02/15/08 - A
Safety Review
Phase 1 - Requests for Additional Information (RAIs) Issued to Applicant	01/16/09 - A
Phase 2 - SER with Open Items issued (without hydrology and Chapter 6)	02/10 - A
Phase 3 - ACRS Review of SER with Open Items Complete (without hydrology)	04/10 - A
Phase 4 - Advanced SER with no Open Items Issued	09/10 - Deferred
Phase 5 - ACRS Review of SER with no Open Items Complete	01/11 - Deferred
Phase 6 - Final SER Issued	03/11 - Deferred
Environmental Review
Phase 1 - Environmental impact statement (EIS) summary report issued	08/15/08 - A
Phase 2 - Draft EIS issued to EPA	03/06/09 - Deferred
Phase 3 - Response to public comments on draft EIS issued	08/10/09 - Deferred
Phase 4 - Final EIS issued to EPA	01/10 - Deferred
Hearing
Commission or ASLB hold mandatory hearing
License
Commission decision on issuance of COL application

The TVA letter dated December 19, 2011 reaffirms that the Bellefonte Units 3 and 4 COLA continues to be deferred indefinitely. No activity has been performed by TVA with regards to Unit 3 and 4 since the last annual update of the Safety Analysis and Departure Reports submitted to NRC on December 22, 2010.

Additional information can be found at http://www.nrc.gov/reactors/new-reactors/col/bellefonte.html

Tags: bellefonte

Virgil C Summer Units 2 & 3

Nuclear Street News — Tue, 03 Apr 2012 16:08:33 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/3/2012 12:08:33 PM

Virgil C Summer Units 2 & 3

Licensing Status: Scheduled

Site: Existing Site Virgil C Summer

Reactor: Westinghouse Advanced Passive 1000 (AP1000)
Pressurized Water Reactors (PWRs)

Projected Online: Unit 3 - 2016
Unit 4 – 2019

In the News: Virgil C Summer Units 2 & 3

NRC Application Review Schedule

Key Milestones	Completion Date Actual - A Target - T
Application Tendered	03/27/08 - A
Acceptance Review
Acceptance Review Start	06/02/08 - A
Docketing Decision Letter Issued/Acceptance Review Complete	07/31/08 - A
Review Schedule Established/Schedule Letter Issued to Applicant	09/26/08 - A
Safety Review
Phase A - Requests for Additional Information (RAIs) and Supplemental RAIs (Formerly Phase 1 and 2)	09/10/09 - A
Phase B - Advanced Final safety evaluation report (SER) without Open Items (Formerly Phase 4)	12/10/10 – A
Phase C - ACRS Review of Advanced Final SER (Formerly Phase 5)	03/26/11 - A
Phase D - Final SER (Formerly Phase 6)	08/17/11 - A
Environmental Review
Phase 1 - Scoping	07/15/09 - A
Phase 2 - Draft Environmental Impact Statement (DEIS)	04/16/10 - A
Phase 3 - Response to Public Comments on DEIS completed	08/10 - A
Phase 4 - Final Environmental Impact Statement	04/11 - A
Hearing
Commission or ASLB hold mandatory hearing	01/12 - A
License
Commission decision on issuance of COL application	03/20 - A

Additional information can be found at http://www.nrc.gov/reactors/new-reactors/col/summer.html

Tags: new nuclear plant

Kursk Unit 5

Nuclear Street News — Tue, 03 Apr 2012 16:01:35 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/3/2012 12:01:35 PM

Reactor: RBMK-1000

Output: 925 Mwe

Location: Western Russia on the bank of the Seym River

In the News: Kursk Unit 5

1985 Start of project

2010 No official announcement that the project has been cancelled, but it is "unlikely to be completed" according to World Nuclear Association

Tags: kursk

Kursk Unit 5

Nuclear Street News — Tue, 03 Apr 2012 16:01:19 GMT

Revision 3 posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/3/2012 12:01:19 PM

Reactor: RBMK-1000

Output: 925 Mwe

Location: Western Russia on the bank of the Seym River

In the News: Kursk Unit 5

1985 Start of project

2010 No official announcement that the project has been cancelled, but is "unlikely to be completed" according to World Nuclear Association

Tags: new nuclear plant, russia, kursk

Kalinin Unit 4

Nuclear Street News — Tue, 03 Apr 2012 15:53:48 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/3/2012 11:53:48 AM

Reactor: PWR

Output: 1950 Mwe

Location: 120 miles northwest of Moscow, in Tver Oblast near the town of Udomlya

In the News: Kalinin Unit 4

1986 Start of project

2011 Connected to electricity grid

Tags: kalinin

Beloyarsk Unit 4

Nuclear Street News — Tue, 03 Apr 2012 15:51:54 GMT

Current Revision posted to Nuclear Power Plants World Wide by Nuclear Street News on 4/3/2012 11:51:54 AM

Reactor: FBR

Output: 804 Mwe

Location: Sverdlovsk Oblast, Russia

1987 Start of project

2013 Expected commercial use

Tags: Beloyarsk