IR 05000443/2013008

IR 05000443-13-008; 3/25/2013 to 4/26/2013; NextEra Energy Seabrook, LLC; Seabrook Station, Unit 1; Component Design Bases Inspection

ML13157A343
Person / Time
Site:	Seabrook
Issue date:	06/06/2013
From:	Paul Krohn Engineering Region 1 Branch 2
To:	O'Keefe M, Walsh K NextEra Energy Seabrook
References
IR-13-008
Download: ML13157A343 (48)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 June 6, 2013 Mr. Kevin Walsh Site Vice President, North Region

Seabrook Nuclear Power Plant NextEra Energy Seabrook, LLC

c/o Mr. Michael O'Keefe P.O. Box 300 Seabrook, NH 03874

SUBJECT: SEABROOK STATION, UNIT 1- NRC COMPONENT DESIGN BASES INSPECTION REPORT 05000443/2013008

Dear Mr. Walsh:

On April 26, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Seabrook Station. The enclosed inspection report documents the inspection results, which were discussed on April 26, 2013, with Mr. Kevin Walsh, Site Vice President, and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.

In conducting the inspection, the team examined the adequacy of selected components and operator actions to mitigate postulated transients, initiating events, and design basis accidents. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.

This report documents four NRC-identified findings which were of very low safety significance (Green). Three of the findings were determined to involve violations of NRC. However, because of the very low safety significance of the violations and because they were entered into your correction action program, the NRC is treating these violations as non-cited violations (NCV) consistent with Section 2.3.2.a of the NRC Enforcement Policy. If you contest any of the NCVs in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555-0001, with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001; and the NRC Resident Inspector at the Seabrook Station. In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I; and the NRC Resident Inspector at Seabrook Station. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for the public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRC'

s document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Paul G. Krohn, Chief Engineering Branch 2 Division of Reactor Safety

Docket No. 50-443 License No. NPF-86

Enclosure:

Inspection Report 05000443/2013008 w/Attachment: Supplemental Information

REGION I Docket No.: 50-443

License No.: NPF-86

Report No.: 05000443/2013008

Licensee: NextEra Energy Seabrook, LCC (NextEra)

Facility: Seabrook Station, Unit 1

Location: Seabrook, NH 03874

Dates: March 25 to April 26, 2013

Inspectors: K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader S. Pindale, Senior Reactor Inspector, DRS J. Richmond, Senior Reactor Inspector, DRS J. Schoppy, Senior Reactor Inspector, DRS W. Sherbin, NRC Mechanical Contractor S. Kobylarz, NRC Electrical Contractor

Approved by: Paul G. Krohn, Chief Engineering Branch 2 Division of Reactor Safety

ii Table of Contents

SUMMARY OF FINDINGS

..........................................................................................................

iii

REPORT DETAILS

................................................................................................................

REACTOR SAFETY

.............................................................................................................. 1

OTHER ACTIVITIES

........................................................................................................... 25

4OA6 Meetings, including Exit .......................................................................................... 26

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

.................................................................................................... A-1

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED ........................................................ A-1

LIST OF DOCUMENTS REVIEWED

........................................................................................ A-2