Browns Ferry Nuclear Plant

The Browns Ferry Nuclear Plant is located on the Tennessee River near Decatur and Athens, Alabama, on the north side (right bank) of Wheeler Lake. The site has three General Electric boiling water reactor (BWR) nuclear generating units and is owned entirely by the Tennessee Valley Authority (TVA). With a generating capacity of nearly 3.8 gigawatts, it is the second most powerful nuclear plant in the United States, behind the Palo Verde Nuclear Generating Station in Arizona, and the most powerful generating station operated by TVA.
History.
The nuclear power plant is named after a ferry that operated at the site until the middle of the 20th century.
Browns Ferry was TVA's first nuclear power plant; its approval occurred on June 17, 1966 and construction began in September 1966. In 1974, the time of its initial operation, it was the largest nuclear plant in the world. It was the first nuclear plant in the world to generate more than 1 gigawatt of power. The lake provides main cooling, and 7 small fan towers assist during limitations on water temperature. The 600 ft concrete chimney vents gases.
In 2006, the Nuclear Regulatory Commission (NRC) renewed the licenses for all three reactors, extending their operation for an additional twenty years past their original 40-year licensing period.
TVA employs 1500 people at the plant, making it the largest employer in Limestone County, Alabama . A planned Toyota-Mazda north of the unincorporated town of Greenbrier factory will employ 4000 when completed.
Power Uprates.
On August 16, 2017, the NRC approved TVA's request for a 14.3% uprate of each reactor's output. Each unit's gross electrical output was 1,155 MWe (1,101 MWe net), but after power uprates during refueling outages in Fall 2018 for Unit 1, Spring 2019 for Unit 2, and Spring 2018 for Unit 3, the gross electrical output for each unit was increased to 1,310 MWe (1,256 MWe net). The uprate for Unit 3 was completed in July 2018, and in January 2019 for Unit 1. The final uprate, for Unit 2, was completed in August 2019, completing the $475 million project.
The electrical power increase of each unit was facilitated by the maximum operating thermal output of each reactor being increased from 3,458 MWth to 3,952 MWth.
Unit 1.
Unit 1 is a 1,256 MWe net BWR/4 built by General Electric. Construction started on Unit 1 on September 12, 1966 and originally came online on December 20, 1973. Commercial operation began on August 1, 1974. It was licensed to operate through December 20, 2013. Unit 1 was shut down for a year after a fire in 1975 damaged the unit. The unit was subsequently repaired and operated from 1976 through March 3, 1985, when all three Browns Ferry units were shut down for operational and management issues.
Starting in 2002, TVA undertook an effort to restore Unit 1 to operational status, spending $1.8 billion USD to do so. The NRC approved the restart of Unit 1 on May 15, 2007 and the reactor was brought up to criticality on May 22. During initial testing after restart, on May 24, 2007, a leaky hydraulic control pipe in the turbine hall burst, spilling about of non-radioactive fluid, and the newly restarted reactor was temporarily powered down. Reactor power-up and tests resumed on May 27 and the unit started supplying power to the electricity supply grid on June 2, 2007, reaching full power on June 8. The Browns Ferry restart was estimated to pay for itself in five years.
On May 4, 2006, NRC issued a renewed license, adding twenty years to operate through December 20, 2033.
Unit 1 generated 9,801 GWh of electricity in 2017, achieving a capacity factor of 101.62%.
Unit 1 fire.
On March 22, 1975 a fire started when a worker using a candle to search for air leaks accidentally set a temporary cable seal on fire. At Browns Ferry, foamed plastic, covered on both sides with two coats of a flame retardant paint, was used as a firestop. The fire spread from the temporary seal into the foamed plastic, causing significant damage to the reactor control cabling in the station.
An NRC bulletin explained the circumstances of the fire.
The fire started in the cable spreading room at a cable penetration through the wall between the cable spreading room and the reactor building for Unit 1. A slight differential pressure is maintained (by design) across this wall, with the higher pressure being on the cable spreading room side. The penetration seal originally present had been breached to install additional cables required by a design modification. Site personnel were resealing the penetration after cable installation and were checking the airflow through a temporary seal with a candle flame prior to installing the permanent sealing material. The temporary sealing material was highly combustible, and caught fire. Efforts were made by the workers to extinguish the fire at its origin, but they apparently did not recognize that the fire, under the influence of the draft through the penetration, was spreading on the reactor building side of the wall. The extent of the fire in the cable spreading room was limited to a few feet from the penetration; nonetheless, the presence of the fire on the other side of the wall from the point of ignition was not recognized until significant damage to cables related to the control of Units 1 and 2 had occurred.
This later resulted in the Nuclear Regulatory Commission making significant additions to the standards for fire protection through the publication of 10CFR50.48 and Appendix R. According to the Nuclear Information and Resource Service, the newly restarted Unit 1 does not comply with these standards. Unit 3 was not affected by the accident. This event was pivotal not just for firestopping in the nuclear field, but also in commercial and industrial construction. While the nuclear field went to installations of silicone foam, a wider array of firestops became prevalent in non-nuclear construction.
Unit 2.
Unit 2 is a 1,259 MWe net BWR/4 built by General Electric that originally came online on August 2, 1974, and is licensed to operate through June 28, 2034. Unit 2 generated 8,396 GWh of electricity in 2017, achieving a capacity factor of 86.81%.
Unit 2 returned to service in 1991, after all three reactors were shut down in 1985. During a drought in August 2007, Unit 2 was shut down for one day because water temperature in the Tennessee River rose too high for the water to be used for cooling and then discharged back into the river.
Beginning in 2005 Unit 2 was loaded with BLEU (Blended Low Enriched Uranium) recovered by the DOE from weapons programs. This fuel contains quantities of U-236 and other contaminants because it was made from reprocessed fuel from weapons program reactors and therefore has slightly different characteristics when used in a reactor as compared to fresh uranium fuel. By making use of this fuel, which would otherwise have been disposed of as waste, the TVA is saving millions of dollars in fuel costs and accumulating a database of recycled uranium reactions in LWR use.
Unit 3.
Unit 3 is a 1,260 MWe net BWR/4 built by General Electric that originally came online on August 18, 1976 with a capacity of 1,105 MWe net, and is licensed to operate through July 2, 2036. Unit 3 returned to service in 1995 after all three units were shut down in 1985 for maintenance and repairs. Unit 3 generated 9,651 GWh in 2017, achieving a capacity factor of 99.70%. The power update of 155 MWe was completed in July 2018.
Additional incidents.
March 19, 1985.
TVA decided to shut the entire plant down and keep it shut down indefinitely in order to focus on making improvements to all three units in order to bring it back into regulatory compliance following extremely negative assessments from the NRC.<ref name="GAO/RCED-87-141"></ref> Unit 2 finally resumed operation on May 24, 1991, with Unit 3 following it on November 1, 1995, although Unit 1 did not resume operation until June 2, 2007.
May 10, 1986.
Cooling tower #4 (which was wide, long, and four stories tall) was destroyed in a fire caused by sparks from the electrical cooling fans in the tower hitting the abnormally dry redwood slats within the tower on May 10, 1986. During normal operation, water was kept flowing near-continuously over the redwood slats within the tower, but after close to two months of inactivity, the slats were very dry and extremely flammable. $5 million of damage was done.
May 23, 1996.
Cooling tower #3 (which was in the process of being refurbished at the time) was heavily damaged in a fire on May 23, 1996, with about 80% of the tower destroyed.
April 27, 2011.
At 5:01 PM on April 27, 2011, all three reactors scrammed due to loss of external power caused by a tornado in the vicinity of the plant. Control rod insertion and cooling procedures operated as designed with no physical damage or release of radiation. Diesel backup generators provided power after a brief period of outage. An NRC Unusual Event, the lowest level of emergency classification, was declared due to loss of power exceeding 15 minutes. Additionally, a small oil leak was found on one generator. Due to widespread transmission grid damage from the storms, Browns Ferry was unable to produce power for the grid and significant blackouts occurred throughout the Southeastern United States.
January 2015.
A drain line leaked 100-200 gallons of water containing tritium levels above acceptable EPA drinking water standards. The leak was fixed within three hours of when it was discovered and was largely contained within the plant area.
May 2015.
The Nuclear Regulatory Commission found that 5 contract workers failed to conduct roving fire watch patrols as required by NRC. As a result, Tennessee Valley Authority was fined $140,000 for failing to maintain adequate fire watches in 2015 at Browns Ferry.
Surrounding population.
The 2010 U.S. population within of Browns Ferry was 39,930, an increase of 12.3 percent in a decade, according to an analysis of U.S. Census data for msnbc.com. The 2010 U.S. population within was 977,942, an increase of 11.0 percent since 2000. Cities within 50 miles include Huntsville (28 miles to city center).
Seismic risk.
According to an NRC study published in August 2010, the estimated risk of an earthquake intense enough to cause core damage to reactor one was 1 in 270,270, and for reactors two and three, the risk was 1 in 185,185.