ML15195A069

Acceptance of Proposed Licensing Amendment Request Regarding the Addition of a Note to Technical Specification Surveillance Requirement 4.4.1.3.4

ML15195A069
Person / Time
Site:	Seabrook
Issue date:	07/27/2015
From:	John Lamb Plant Licensing Branch 1
To:	Dean Curtland NextEra Energy Seabrook
Lamb J, NRR/DORL/LPLI-2, 415-3100
References
TAC MF6478
Download: ML15195A069 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Dean Curtland, Site Vice President c/o Mr. Michael Ossing Seabrook Nuclear Plant NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 0387 4 July 27, 2015

SUBJECT:

SEABROOK STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING THE ADDITION OF A NOTE TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 4.4.1.3.4 (TAC NO. MF6478)

Dear Mr. Curtland:

By letter dated July 13, 2015 (Agencywide Documents Access and Management System Accession No. ML15198A027), NextEra Energy Seabrook, LLC, et al. submitted a license amendment request (LAR) to the Technical Specifications (TSs) at Seabrook Station, Unit No. 1. The LAR proposes to add a note to TS Surveillance Requirement 4.4.1.3.4, which requires verification that residual heat removal loop locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program. The proposed note states the following: "Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4."

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 TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 1 O 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.

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

Docket No. 50-443 cc: Distribution via Listserv John

. amb, Senior Project Manager Plant Li ensing Branch 1-2 Divis of Operating Reactor Licensing Offic of Nuclear Reactor Regulation

ML15195A069 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME JLamb LRonewicz DBroaddus JLamb DATE 7/20/15 7/14/15 7/24/15 7/27/15