ML14245A189

Acceptance of Proposed Licensing Amendment Request Regarding the Increase to the Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement

ML14245A189
Person / Time
Site:	Seabrook
Issue date:	09/09/2014
From:	John Lamb Plant Licensing Branch 1
To:	Dean Curtland, Ossing M NextEra Energy Seabrook
Lamb J
References
TAC MF4578
Download: ML14245A189 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 9, 2014 Mr. Dean Curtland, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT 1 -ACCEPTANCE OF PROPOSED LICENSING AMENDMENT REQUEST REGARDING THE INCREASE TO THE VOLTAGE LIMIT FOR DIESEL GENERATOR LOAD REJECTION SURVEILLANCE REQUIREMENT (TAC NO. MF4578)

Dear Mr. Curtland:

By letter dated July 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14209A918), NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted a license amendment request (LAR) to increase the voltage limit for a full load rejection test of the emergency diesel generator specified in surveillance requirement (SR) 4.8.1.1.2.f.3 of Technical Specification (TS) 3.8.1.1, "A. C. [alternating current] Sources-Operating," at Seabrook Station, Unit 1 (Seabrook). The LAR also revises the TS definition of the terms "Operable- Operability."

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. The acceptance review was 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 Title 10 of the Code of Federal Regulations (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 acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

D. Curtland If you have any questions, please contact me at (301) 415-3100 or via e-mail at John.Lamb@nrc.gov.

Sincerely, amb, Sen~r P~

i ensing Branch 1-2 Divisi n of Operating Reactor Licensing Office Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv

ML14245A189 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME Jlamb ABaxter RSchaaf Jlamb DATE 09/02/14 09/05/14 9/09/14 9/09/14