IR 05000443/2012002

IR 05000443-12-002, on 01/01/12 - 03/31/12, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report

ML12129A059
Person / Time
Site:	Seabrook
Issue date:	05/08/2012
From:	Arthur Burritt Reactor Projects Branch 3
To:	Freeman P NextEra Energy Seabrook
BURRITT, AL
References
IR-12-002
Download: ML12129A059 (39)

Text

{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION May 8, 2012

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - NRC INTEGRATED INSPECTION REPORT 05000443/2012002

Dear Mr. Freeman:

On March 31, 2012, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station, Unit No. 1. The enclosed inspection report documents the inspection results, which were discussed on April 9, 2012, with you and other members of your staff.

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

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

No NRC-identified or self-revealing findings were identified during this inspection.

However two licensee-identified violations which were determined to be of very low safety significance is listed in this report. Because of the very low safety significance, and because they are entered into your corrective action program, the NRC is treating these findings as non-cited violations (NCV), consistent with Section 2.3.2 of the NRC Enforcement Policy. If you contest any 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 Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at 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 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely, /RA/ Arthur L. Burritt, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket No. 50-443 License No: NPF-86

Enclosure:

Inspection Report No. 05000443/2012002 w/ Attachment: Supplemental Information

REGION I== Docket No.: 50-443 License No.: NPF-86 Report No.: 05000443/2012002 Licensee: NextEra Energy Seabrook, LLC Facility: Seabrook Station, Unit No.1 Location: Seabrook, New Hampshire 03874 Dates: January 1, 2012 through March 31, 2012 Inspectors: W. Raymond, Senior Resident Inspector J. Johnson, Resident Inspector J. DeBoer, Resident Inspector J. Noggle, Senior Health Physicist T. Moslak, Health Physicist S. Hammann, Senior Health Physicist R. Montgomery, Project Engineer L. Scholl, Senior Reactor Inspector P. Cataldo, Senior Resident Inspector Approved by: Arthur L. Burritt, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

TABLE OF CONTENTS 1. REACTOR SAFETY .............................................................................................................. 4 1R01 Adverse Weather Protection ....................................................................................... 4 1R04 Equipment Alignment .................................................................................................. 4 1R05 Fire Protection ............................................................................................................. 5 1R06 Flood Protection Measures ......................................................................................... 6 1R07 Heat Sink Performance ............................................................................................... 7 1R11 Licensed Operator Requalification Program ............................................................... 7 1R12 Maintenance Effectiveness ......................................................................................... 8 1R13 Maintenance Risk Assessments and Emergent Work Control ................................... 9 1R15 Operability Determinations and Functionality Assessments ....................................... 9 1R18 Plant Modifications .................................................................................................... 10 1R19 Post-Maintenance Testing ........................................................................................ 11 1R22 Surveillance Testing.................................................................................................. 11 1EP4 Emergency Action Level and Emergency Plan Changes ......................................... 12 1EP6 Drill Evaluation .......................................................................................................... 12 2. RADIATION SAFETY .......................................................................................................... 12 2RS1 Radiological Hazard Assessment and Exposure Controls ........................................ 13 2RS2 Occupational ALARA Planning and Controls ............................................................ 15 2RS4 Occupational Dose Assessment ............................................................................... 16 4. OTHER ACTIVITIES ........................................................................................................... 18 4OA1 Performance Indicator Verification ............................................................................ 18 4OA2 Problem Identification and Resolution ...................................................................... 18 4OA3 Follow-Up of Events and Notices of Enforcement Discretion.................................... 22 4OA5 Other Activities .......................................................................................................... 22 4OA6 Meetings, Including Exit ............................................................................................ 24 4OA7 Licensee-Identified Violations ................................................................................... 24 ATTACHMENT: SUPPLEMENTARY INFORMATION................................................................ 25 SUPPLEMENTARY INFORMATION ........................................................................................ A-1 LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED ..................................... A-1 LIST OF DOCUMENTS REVIEWED ........................................................................................ A-2 LIST OF ACRONYMS ............................................................................................................. A-11 Enclosure

SUMMARY OF FINDINGS

IR 05000443/2012002; 01/01/2012-03/31/2012; Seabrook Station, Unit No. 1, Routine

Integrated Inspection Report.

This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

Other Findings

Two violations of very low safety significance identified by NextEra were reviewed by the inspectors. Corrective actions taken or planned by NextEra have been entered into NextEras corrective action program. These violations and corrective action tracking numbers are listed in Section 4OA7 of this report.

REPORT DETAILS

Summary of Plant Status

Seabrook operated at 85% power during the entire inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

.1 Readiness for Impending Extreme Weather Conditions

a. Inspection Scope

The inspectors performed a review of NextEras readiness for the impending adverse weather conditions on February 29 - March 1, 2012. The review focused on the service water system and the emergency diesel generators (EDGs). The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR) and technical specifications to determine what design features would protect these systems, and to ensure NextEra personnel had adequately prepared for adverse weather challenges. The inspectors reviewed station procedures, including NextEras severe weather procedure and applicable operating procedures. The inspectors performed walkdowns of the selected systems to verify that no issues existed that could challenge the operability of the systems during adverse weather. Documents reviewed for each section of this inspection report are listed in the Attachment.

b. Findings

No findings were identified. ==1R04 Equipment Alignment

.1 Partial System Walkdowns

==

a. Inspection Scope

The inspectors performed partial walkdowns of the following system:

• Vital Battery 1-EDE-B-1D cross tie and return to service following maintenance on January 5, 2012
• Diesel Generator (DG) Train A during planned maintenance activities on the DG Train B on January 23, 2012
• Emergency Feedwater System restoration following surveillance testing on 1-FW-P-37-B on February 21, 2012
• B residual heat removal system following return from maintenance on February 28, 2012 The inspectors selected these systems based on their risk-significance for the current plant configuration or following realignment. The inspectors reviewed applicable operating procedures, system diagrams, the UFSAR, technical specifications, work orders, condition reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable.

b. Findings

No findings were identified.

.2 Full System Walkdown

a. Inspection Scope

On January 23 to 25, 2012, the inspectors performed a complete system walkdown of accessible portions of the main steam (MS) system to verify the equipment lineup was correct. The inspectors reviewed operating procedures, surveillance tests, drawings, equipment lineup procedures, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hangar and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether NextEra staff had properly identified equipment issues and entered them into the corrective action program for resolution with the appropriate significance characterization.

Additionally, the inspectors reviewed a sample of related condition reports and work orders to ensure NextEra appropriately evaluated and resolved any deficiencies.

b. Findings

No findings were identified. ==1R05 Fire Protection