IR 05000443/2018010

NRC Biennial Problem Identification and Resolution Inspection Report 05000443/2018010

ML18255A263
Person / Time
Site:	Seabrook
Issue date:	09/12/2018
From:	Fred Bower Reactor Projects Branch 3
To:	Nazar M NextEra Energy Seabrook
References
IR 2018010
Download: ML18255A263 (10)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 12, 2018

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - NRC BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000443/2018010

Dear Mr. Nazar:

On August 9, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station, Unit No. 1. The NRC inspectors discussed the results of this inspection with Mr. Eric McCartney, Vice President - Northern Region and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations corrective action program (CAP) and the stations implementation of the program to evaluate Seabrook stations effectiveness in identifying, prioritizing, evaluating and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for CAPs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed Seabrook station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.

Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Number: 50-443 License Number: NPF-86

Enclosure:

Inspection Report 05000443/2018010

Inspection Report

Docket Number: 50-443 License Number: NPF-86 Report Number: 05000443/2018010 Enterprise Identifier: I-2018-010-0062 Licensee: NextEra Energy Seabrook, LLC (NextEra)

Facility: Seabrook Station, Unit No. 1 (Seabrook)

Location: Seabrook, NH Inspection Dates: July 23, 2018 to August 9, 2018 Inspectors: C. Lally, Project Engineer, Team Lead P. Meier, Seabrook Resident Inspector C. Highley, Millstone Resident Inspector E. Allen, Project Engineer Observer: S. Ghrayeb, Project Engineer Approved By: F. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring NextEras performance at Seabrook by conducting the biennial problem identification and resolution inspection in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

Based on the samples selected for review, the inspection team concluded that NextEra was effective in identifying, evaluating, and resolving problems and that NextEra effectively used operating experience and self-assessments. The inspectors found no evidence of significant challenges to NextEras safety conscious work environment at Seabrook and concluded that NextEra staff are willing to raise nuclear safety concerns through at least one of the several means available.

No findings or more-than-minor violations were identified.

INSPECTION SCOPES

This inspection was conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess NextEras performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71152 - Problem Identification and Resolution Biennial Team Inspection

The inspectors performed a biennial assessment of NextEras corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment. The assessment is documented below.

(1) Corrective Action Program Effectiveness - The inspection team evaluated NextEras effectiveness in identification, prioritization and evaluation, and correcting problems, and verified the station was complied with NRC regulations and NextEras standards for corrective action programs.

(2) Operating Experience - The team evaluated the stations effectiveness in its use of industry and NRC operating experience information and verified the station complied with NextEras standards for the use of operating experience.

(3) Self-Assessments and Audits - The team evaluated the effectiveness of the stations audits and self-assessments and verified the station complied with NextEras standards for the use of self-assessments and audits.

(4) Safety Conscious Work Environment - The team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs.

INSPECTION RESULTS

Evaluation of the Seabrook PI&R Program 71152B The NRC inspection team reviewed Seabrook stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined NextEra staffs performance in each of these areas adequately supported nuclear safety. No findings or more-than-minor violations were identified.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessment.

Based on the samples reviewed, the team determined that NextEras performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed Seabrook station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of those interviews, the team found no evidence of challenges to NextEras safety-conscious work environment. Site employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

Observation and Minor Performance Deficiency 71152B Corrective Action Program: The inspectors noted that out of service analytical chemistry equipment was not being documented in the corrective action program through the initiation of condition reports (CRs). The chemistry equipment deficiencies were being tracked in the chemistry department logs, but were not entered into the corrective action program.

Minor Performance Deficiency: The initiation of CRs for out of service chemistry equipment is required by NextEra procedure CS 0904.04, Laboratory Instrument Control Charts, and occurred multiple times during the period of January 2017 to July 2018. The station has documented this in the corrective action program under CR 2275048.

Screening: The failure to implement a procedural requirement had no safety impact under the given situation. Specifically, no out of service laboratory equipment was used to perform analysis to support technical specification requirements, redundant analytical equipment remained available, and no technical specification required samples were missed. Therefore, this performance deficiency is minor.

EXIT MEETINGS AND DEBRIEFS

On August 9, 2018, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Eric McCartney, Vice President - Northern Region, and other members of the NextEra staff. Inspectors verified no proprietary information was retained or documented in this report.

DOCUMENTS REVIEWED

71152B

Procedures

AD-AA-103, Nuclear Safety Culture Program, Revision 12

CD0913.06, Grab Sample Technique, Revision 10

CS0924.06, Total Particulate Contamination in Emergency Diesel Fuel Oil, Revision 8

CS0904.04, Laboratory Instrument Control Charts, Revision 15

EN-AA-203-1001, Operability Determinations and Functionality Assessment, Revision 30

ER-AA-100-2002, Maintenance Rule Program Administration, Revision 6

ER-AA-101, Equipment Reliability, Revision 8

EX1806.001, RPS and ESF AS Response Time Summation Procedure, Revision 11

LX0563.02, Reactor Coolant Pump Undervoltage Channel Calibration and Relay PM,

Revision 17

MS0535.11, Equipment Hatch Missile Shield Removal and Installation, Revision 5

NA-AA-200-1000, Employee Concerns Program, Revision 1

OS1426.12, Diesel Generator A and B Weekly and Monthly Surveillances,

Revisions 11, 12, and 25

Steam Generator Reference Leg Fill and Transmitter Venting IN1640.920 Revision 0

OX0443.01, Diesel Fire Pump Weekly Test, Revision 16

OX1406.12 18 Month Containment and Containment Spray Recirculation Sump Surveillance,

Revision 9

OX1406.12 18 Month Containment and Containment Spray Recirculation Sump Surveillance,

Revision 14

OX1426.27, DG 1B Semiannual Operability Surveillance, Revision 28

PI-AA-101-1000, Level 2 Independent Assessment, Revision 20

PI-AA-102, Operating Experience Program, Revision 14

PI-AA-104-1000, Condition Reporting, Revision 17

Seabrook Station Administrative Procedure, Classification of Emergencies ER 1.1 Revision 59

Seabrook Station Administrative Procedure, Classification of Emergencies ER 1.1 Revision 56

Seabrook Quality Assurance Topical Report, Revision 21

Seabrook Station Quality Assurance Manual, Revision 54

Condition Reports (*initiated in response to inspection)

1668314 1934562 1942006 1962214 2022462 2026407

2030152 2040165 2044627 2044707 2049737 2063732

2065314 2069062 2069607 2069801 2075739 2076893

2083685 2092608 2097375 2098733 2100147 2100186

2100199 2100232 2100565 2100572 2100742 2100795

2100846 2101155 2102315 2102565 2103817 2105712

2108355 2108372 2109563 2112715 2113205 2115492

2115531 2124899 2124957 2127066 2127145 2129116

29382 2132014 2132503 2133415 2135666 2135775

2135836 2136567 2137152 2138579 2142754 2147795

2147873 2148431 2149225 2150494 2153195 2158282

2158283 2158290 2158291 2168202 2169614 2170509

2172204 2182279 2187577 2191791 2196114 2197408

2199166 2199196 2199340 2199855 2200100 2200254

200705 2201450 2202358 2202648 2207372 2207905

213342 2213584 2215058 2216373 2221606 2222634

27559 2232291 2236176 2239906 2242073 2242592

243460 2245862 2260177 2261891 2266072 2267214

268628 2269068 2272373 2272500 2272682 2273163*

273177* 2273276* 2273387* 2273426* 2273474* 2273521*

273570* 2273594* 2273613* 2273628* 2273656* 2273659*

273670* 2273685* 2273974* 2274830* 2275048* 2275282*

Work Orders/Work Requests

40132620 40228569 40264381 40265516 40287160 40308888

40316168 40322466 40346955 40422993 40427609 40432772

40441339 40451124 40465916 40505649 40533840 40561380

40563191 40563236 40563259 40563265 40563271 40563283

40563350 40586631 40593072 94139510 94143377 94162598

Calculations

ES-4.003, 125 Volt DC Short Circuit and System Voltage Drop Calculation, Revision 10

Evaluations

2019628 2076893 2092608 2097062 2102315 2103429

2105636 2106893 2114495 2115215 2115331 2116669

2119394 2120131 2124898 2124957 2125151 2129382

2137168 2140612 2156562 2158284 2169614 2172204

2197408 2199855 2200623 2200705 2202923 2207011

210450 2239906 2223905 2236037 2242520 2248447

Drawings

211630-B-9532 Sheet 1, No. 1 Unit No. 1A, 1B and 1C Vital Buses Safeguard Equipment

Control System Schematic Controls, Revision 8

Operating Experience

70077135, NRC Information Notice 2007-36 EDG Volt Regulator, dated May 16, 2008

24905 2026947 2065778 2083865 2112715 2132520

2136567 2199219 2222634 2265706

Self-Assessment and Audits

277135, Operability Evaluation Focused Area Self-Assessment, dated May 16, 2010

Operating Experience Summary, Manual Reactor Trip in Response to a Feedwater Isolation

Due to High Level in Steam Generator B Seabrook Station - April 29, 2017 (CR 2202358)

OR16 Steam Generator Tube Inspection Report SBK-L-14190, dated October 14, 2014

OR17 Steam Generator Tube Inspection Report SBK-L-16058, dated April 22, 2016

OR18 Steam Generator Tube Inspection Report SBK-L-17166, dated October 17, 2017

SBK-16-003 SBK-16-005 SBK-17-005 SBK-17-008

Miscellaneous

Chemistry logs from January 2017 to July 2018

Structural Integrity Associates, Inc. Report 1600052.401.R0