ML14232A622

Seabrook Station, Unit 1 - Acceptance of Requested Licensing Amendment Request and Exemption Regarding Revised Reactor Coolant System Pressure-Temperature Limits (TAC Nos. MF4576 and MF4577)

ML14232A622
Person / Time
Site:	Seabrook
Issue date:	09/09/2014
From:	Lamb J G Plant Licensing Branch 1
To:	Dean Curtland, Ossing M NextEra Energy Seabrook
Lamb J G
References
TAC MF4576, TAC MF4577
Download: ML14232A622 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Dean Curtland, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 September 9, 2014 SUBJECT: SEABROOK STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING AMENDMENT AND EXEMPTION REGARDING REVISED 1 REACTOR COOL NT SYSTEM PRESSURE-TEMPERATURE LIMITS {TAC NO. MF457 AND MF4577) Dear Mr. Curtland: By letter dated July 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14216A404) NextEra Energy Seabrook, LLC (NextEra or the licensee) requested a license amendment request to revise the Seabrook Station Technical Specification (TS) and an exemption from the requirements of Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, Appendix G. The proposed change is a request to revise the reactor coolant system (RCS) pressure-temperature limits applicable for 55 effective full-power years, provide new overpressure protection setpoints, and lowering the RCS temperature at which the TS is applicable. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request following the email sent on August 21, 2014 (ADAMS No. ML 14239A589). The acceptance review was i performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its! characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate D. Curtland -2-acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-3100 or via e-mail at John .Lamb@ nrc.gov. Docket No. 50-443 cc: Distribution via Listserv Jo G. Lamb, Senior Project Manager PI t Licensing Branch 1-2 Di ision of Operating Reactor LicensinQ Office of Nuclear Reactor Regulation 1 D. Curtland -2-acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov. Docket No. 50-443 cc: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNRRDorllpl1-2 Resource RidsNrrDoriDpr Resource RidsAcrsAcnw_MaiiCTR Resource Sincerely, IRA/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPLI-2 RIF RidsNrrLAABaxter Resource RidsNrrPMSeabrook Resource RidsRgn1 MaiiCenter Resource RidsNrrDoriResource ADAMS Accession No: ML 14232A622 *via e-mail OFFICE LPL 1-2/PM LPL 1-2/PM LPL 1-2/LA* LPL 1-2/BC LPL 1-2/PM NAME Tlamb Jlamb ABaxter RSchaaf Jlamb DATE 8/19/14 8/19/14 08/29/14 9/09/14 9/09/14 OFFICIAL RECORD COPY