ML101830272

at a Glance

ML101830272
Person / Time
Site:	Crystal River, Levy County
Issue date:	07/02/2010
From:	US Dept of Energy, Energy Information Administration (EIA)
To:	Office of New Reactors
References
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Download: ML101830272 (3)

Text

Home > Nuclear > Crystal River 3 Nuclear Power Plant Crystal River Nuclear Power Plant, Florida Update: September 10, 2009 U.S. Nuclear Power Plants by Plants Next Update: September 2010 State Alabama Browns Ferry Farley (Joseph M. Farley)

Crystal River 3 Nuclear Power Plant Arizona Palo Verde Net Generation and Capacity, 2008 Arkansas Arkansas Nuclear One Generatio California Diablo Canyon Net n Capacity Capacit (Million Factor License San Onofre Uni y Kilowatt (Percent Typ On Line Expiratio Connecticut Millstone t MW(e) Hours) ) e Date n Date Florida Crystal River 3 PW 3/13/197 St Lucie 3 838 7,000 95 12/3/2016 R 7 PWR =pressurized light water reactors. Turkey Point Sources Georgia Hatch (Edwin I. Hatch)

Vogtle

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Description:==

The Crystal River Energy Complex is Illinois Braidwood located in Citrus County, Florida. The site consists of Byron approximately 4,700 acres. The single nuclear unit Clinton shares the site with 4 fossil-fueled generators.

Dresden LaSalle County Crystal River, Unit 3 Quad Cities Iowa Duane Arnold Nuclear Steam System Supplier (NSSS Vendor) =

Kansas Wolf Creek Babcock & Wilcox Architect Engineer = Gilbert Associates Louisiana River Bend Owner = Progress Energy Corporation is majority owner. Waterford The distribution of ownership is shown in the table that Maryland Calvert Cliff follows Massachusetts Pilgrim Operator (Licensee) = Progress Energy Corporation. Michigan Donald C. Cook Enrico Fermi (Fermi)

Ownership of Crystal River 3 Palisades Minnesota Monticello Company Percent of Total Prairie Island Progress Energy Florida 91.8 Mississippi Grand Gulf Seminole Electric Cooperative 1.7 Missouri Callaway Orlando Utilities Commission 1.6 Gainesville Regional Utilities 1.4 Nebraska Cooper City of Ocala, Florida 1.3 Fort Calhoun Leesburg Electric Department 0.8 New Hampshire Seabrook Kissimmee Utility Authority 0.7 New Jersey Hope Creek Utilities Commission of New Smyrna Beach 0.6 Oyster Creek City of Alachua, Florida 0.1 Salem Creek City of Bushnell, Florida

• Fitzpatrick (James A.

• Less than 0.1 percent New York Fitzpatrick)

Indian Point Pressurized-Water Reactor (PWR) Nile Mile Point R.E. Ginna (Ginna, or In a typical commercial pressurized light-water reactor (1) Robert E. Ginna) the reactor core generates heat, (2) pressurized-water in North Carolina Brunswick the primary coolant loop carries the heat to the steam McGuire generator, (3) inside the steam generator heat from the Shearon-Harris(Harris) primary coolant loop vaporizes the water in a secondary Ohio Davis-Besse loop producing steam, (4) the steam line directs the steam to the main turbine causing it to turn the turbine Perry generator, which produces electricity. The unused steam Pennsylvania Beaver Valley is exhausted to the condenser where it is condensed into Limerick water. The resulting water is pumped out of the Peach Bottom condenser with a series of pumps, reheated, and Susquehanna pumped back to the steam generator. The reactors core Three Mile Island contains fuel assemblies which are cooled by water, which is force-circulated by electrically powered pumps. South Carolina Catawba Emergency cooling water is supplied by other pumps, H.B. Robinson which can be powered by onsite diesel generators. Other Oconee safety systems, such as the containment cooling system, Virgil C. Summer also need power. (Summer)

Tennessee Sequoyah Watts Bar Texas Comanche Peak South Texas Vermont Vermont Yankee Virginia North Anna Surry Columbia Generating Washington Station Wisconsin Kewaunee Point Beach

© U.S. Nuclear Regulatory Commission Containment: According to the U.S. Nuclear Regulatory Commission, unit 3 is has dry, ambient pressure.1

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1 Dry, Ambient Pressure: a reactor containment design whose safety has been evaluated on the basis of having a dry air atmosphere at ambient pressure (0 psig) prior to the onset of a loss of coolant accident or steam pipe break. The containment design (concrete and steel tendons) must be able to take the full thermal and pressure stresses associated with the rapid energy release (steam) from a major pipe break.

Sources for Data in Table: Capacity, for purposes of this report, is the net summer capability as reported in Energy Information Administration (EIA) Form EIA-860, "Annual Electric Generator Report." Capacity Factor is a percentage calculation in which the maximum possible generation (based on net summer capability) is divided into the actual generation then multiplied by 100. Generation is the net electricity output reported by plant owners on Form EIA-906, Power Plant Report. Type of Unit: All U.S. commercial reactors currently in operation are one of two types: BWR (boiling water reactor) or PWR (pressurized light water reactor). The type, on-line date, and the license expiration date are published annually in Information Digest by the U.S.

Nuclear Regulatory Commission.

see also:

annual nuclear statistics back to 1953 projected electricity capacity to 2030 international electricity statistics