Nine Mile Point Nuclear Station, New York
Next Update: October 2009
Nine Mile Point Nuclear Station
Net Generation and Capacity, 2007
Unit |
Net Capacity MW(e) |
Generation (Million Kilowatt Hours) |
Capacity Factor (Percent) |
Type | On Line Date |
License Expiration Date** |
| 1 | 621 | 4,996.296 | 87.6 | BWR | Dec. 1, 1969* | August 22, 2029 |
| 2 | 1,140 | 8,605.240 | 92.1 | BWR | July 2, 1987 | October 31, 2046 |
| 1,761 | 13,601.536 | 90.5 | ||||
| *The Nuclear Regulatory Commission (NRC) reports that the license was issued on December 26, 1974. This resulted from an amendment to the original license at that time. At the time the plant began operation in 1969, it was (as required) fully licensed. **Licenses for both units were renewed by the NRC on October 31, 2006. The original license for unit 1 expires in 2009. For unit 2, the original license expires in 2026. BWR = Boiling Water Reactor Sources |
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Description: The Nine Mile Point Nuclear Station is near Syracuse, New York. It is located on a 900-acre site that is shared by the Fitzpatrick nuclear plant. Nine Mile Point 1 is one of the Nation's two oldest reactors still in service.
Nine Mile Point, Unit 1
Nuclear Steam System Supplier (NSSS Vendor) = General Electric
Architect Engineer = Niagara Mohawk Power Corporation
Owner = Constellation Energy Group
Operator (Licensee) = Constellation Generation
Nine Mile Point, Unit 2
Nuclear Steam System Supplier (NSSS Vendor) = General Electric
Architect Engineer = Stone & Webster
Owner = Constellation Energy Group
Operator (Licensee) = Constellation Generation
Boiling Water Reactor (BWR)
In a typical commercial boiling water reactor (1) the reactor core creates heat, (2) a steam-water mixture is produced when very pure water (reactor coolant) moves upward through the core absorbing heat, (3) the steam-water mixture leaves the top of the core and enters the two stages of moisture separation where water droplets are removed before the steam is allowed to enter the steam line, (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 reactor vessel. The reactor's 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 electric power.
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| © U.S. Nuclear Regulatory Commission |
Containment: According to the U.S. Nuclear Regulatory Commission, both units rely on Boiling Water Reactors (BWR), Mark 2.
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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.