ML101830272

Crystal River Nuclear Power Plant 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)

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Home > Nuclear > Crystal River 3 Nuclear Power Plan t Crystal River Nuclear Power Plant, Flor ida Update: September 10, 200 9 Next Update:

September 2010 Crystal River 3 Nuclear Power Plan t Net Generation and Capacity, 2008 Uni t Net Capacit y MW(e) Generatio n (Million Kilowatt Hours) Capacity Factor (Percent) Typ e On Line Date License Expiration Dat e 3 838 7,000 95 PW R 3/13/197 7 12/3/201 6 PWR =pressurized light water reactors.

Sources

Description:

The Crystal River Energy Complex is located in Citrus County, Florida. The site consists of approximately 4,700 acres. The single nuclear unit shares the site with 4 fossil

-fueled generators

. Crystal River, Unit 3 Nuclear Steam System Supplier (NSSS Vendor) = Babcock & Wilcox Architect Engineer = Gilbert Associates Owner = Progress Energy Corporation is majority owner. The distribution of ownership is shown in the table that follows Operator (Licensee) = Progress Energy Corporation.

Ownership of Crystal River 3 Company Percent of Total Progress Energy Florida 91.8 Seminole Electric Cooperative

1.7 Orlando

Utilities Commission

1.6 Gainesville

Regional Utilities 1.4 City of Ocala, Florida

1.3 Leesburg

Electric Department

0.8 Kissimmee

Utility Authority

0.7 Utilities

Commission of New Smyrna Beach 0.6 City of Alachua, Florida 0.1 City of Bushnell, Florida

• Less than 0.1 percent U.S. Nuclear Power Plants by State Plants Alabama Browns Ferry Farley (Joseph M. Farley)

Arizona Palo Verde Arkansas Arkansas Nuclear One California Diablo Canyon San Onofre Connecticut Millstone Florida Crystal River 3 St Lucie Turkey Point Georgia Hatch (Edwin I. Hatch)

Vogtle Illinois Braidwood Byron Clinton Dresden LaSalle County Quad Cities Iowa Duane Arnold Kansas Wolf Creek Louisiana River Bend Waterford Maryland Calvert Cliff Massachusetts Pilgrim Michigan Donald C. Cook Enrico Fermi (Fermi)

Palisades Minnesota Monticello Prairie Island Mississippi Grand Gulf Missouri Callaway Nebraska Cooper Fort Calhoun New Hampshire Seabrook New Jersey Hope Creek Oyster Creek Salem Creek New York Fitzpatrick (James A. Fitzpatrick)

Pressurized

-Water Reactor (PWR)

In a typical commercial pressurized light

-water reactor (1) the reactor core generates heat, (2) pressurized

-water in the primary coolant loop carries the heat to the steam generator, (3) inside the steam generator heat from the primary coolant loop vaporizes the water in a secondary loop producing steam, (4) the steam line directs the steam to the main turbine causing it to turn the turbine generator, which produces electricity. The unused steam is exhausted to the condenser where it is condensed into water. The resulting water is pumped out of the condenser with a series of pumps, reheated, and pumped back to the steam generator. The reactors core contains fuel assemblies which are cooled by water, which is force

-circulated by electrically powered pumps. Emergency cooling water is supplied by other pumps, which can be powered by onsite diesel generators. Other safety systems, such as the containment cooling system, also need power.

© U.S. Nuclear Regulatory Commission Containment:

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

.1 Indian Point Nile Mile Point R.E. Ginna (Ginna, or Robert E. Ginna)

North Carolina Brunswick McGuire Shearon-Harris(Harris)

Ohio Davis-Besse Perry Pennsylvania Beaver Valley Limerick Peach Bottom Susquehanna Three Mile Island South Carolina Catawba H.B. Robinson Oconee Virgil C. Summer (Summer) Tennessee Sequoy ah Watts Bar Texas Comanche Peak South Texas Vermont Vermont Yankee Virginia North Anna Surry Washington Columbia Generating Station Wisconsin Kewaunee Point Beach

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1Dry, 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