Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 (NUREG-1930, Supplement 2)
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Maunscript Completed: November 2014
Date Published: July 2015
Office of Nuclear Reactor Regulation
This document is the second supplement to NUREG-1930, "Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3," for the license renewal application (LRA) for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3). By letter dated April 23, 2007, as supplemented by letters dated May 3 and June 21, 2007, Entergy Nuclear Operations, Inc., ("Entergy" or "the applicant") submitted an LRA in accordance with Title 10, "Energy," of the Code of Federal Regulations (10 CFR) Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants." Entergy requested renewal of the IP2 and IP3 operating licenses (Facility Operating License Numbers DPR-26 and DPR-64, respectively) for a period of 20 years beyond the expirations of the initial operating licenses at midnight on September 28, 2013, for IP2, and at midnight on December 12, 2015, for IP3. The Commission's regulation in 10 CFR 2.109, "Effect of Timely Renewal Application," implements the "timely renewal" provision of Section 9(b) of the Administrative Procedure Act, Title 5, "Government Organization and Employees," of the United States Code (U.S.C.) Section 558(c). Under this regulation, if a licensee requests a renewed license at least 5 years before expiration of its current license, the request is considered "timely," and the facility is allowed to continue to operate under its existing license until the U.S. Nuclear Regulatory Commission (NRC) completes its review and reaches a decision on the license renewal request. At midnight on September 28, 2013, IP2 entered this period of operation under the above provision.
The staff published its safety evaluation report (SER) in the two volumes of NUREG-1930 in November 2009, which summarized the results of its safety review of the LRA for compliance with the requirements of 10 CFR Part 54. In August 2011, the staff issued Supplement 1 to NUREG-1930 (supplemental safety evaluation report (SSER) 1), which documented the staff's review of supplemental information provided by the applicant since the issuance of the SER as documented in NUREG-1930. This supplement to NUREG-1930 (SSER 2) documents the staff's review of supplemental information provided by the applicant since the issuance of the SSER 1. This information includes information committed to by Entergy as documented in Commitment No. 30 (pertaining to reactor vessel internals), information required by 10 CFR 54.21(b), updated information and commitments, as well as information provided in response to staff requests for additional information. This document discusses only the changes to the SER and SSER 1.
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