Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plant Units 1 and 2 (NUREG-1960, Initial Report)

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Publication Information

Manuscript Completed: May 2011
Date Published: August 2011

Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Washington, DC 20555-0001

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Abstract

This safety evaluation report (SER) documents the technical review of the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, license renewal application (LRA) by the United States (US) Nuclear Regulatory Commission (NRC) staff (the staff). By letter dated April 11, 2008, Nuclear Management Company, LLC, (NMC or the applicant) submitted the LRA in accordance with Title 10, Part 54, of the Code of Federal Regulations, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants.” NMC requests renewal of the Units 1 and 2 operating licenses (Facility Operating License Numbers DPR-42 and DPR-60, respectively) for a period of 20 years beyond the current expirations at midnight August 9, 2013, for Unit 1, and at midnight October 29, 2014, for Unit 2.

PINGP is located within the city limits of the City of Red Wing, Minnesota on the West bank of the Mississippi River in southeastern Minnesota. The NRC issued the construction permits for Units 1 and 2 on June 25, 1968. The NRC issued the operating licenses for Unit 1 on August 9, 1973, and on October 29, 1974, for Unit 2. Units 1 and 2 employ a two-loop pressurized water reactor design with a dry ambient containment. Westinghouse Electric Corporation supplied the nuclear steam supply system and Pioneer Service & Engineering Company originally designed the balance of the plant, and Northern States Power constructed the plant. The licensed power output of each unit is 1650 megawatt thermal with a gross electrical output of approximately 575 megawatt electric.

On June 4, 2009, the staff issued an SER with Open Items Related to the License Renewal of Prairie Island Nuclear Generating Plant, Units 1 and 2, in which the staff identified three open items necessitating further review. This SER presents the status of the staff’s review of information submitted through August 21, 2009, the cutoff date for consideration in this SER. The three open items that had been identified in the previous SER were resolved before the staff made a final determination on the LRA. SER Section 1.5 summarizes these items and their resolution. Section 6.0 provides the staff’s final conclusion on its review of the PINGP LRA.