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

September 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

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

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 (1 Sample)

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

22462

26407

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

24899

24957

27066

27145

29116

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

200100

200254

200705

201450

202358

202648

207372

207905

213342

213584

215058

216373

21606

22634

27559

232291

236176

239906

242073

242592

243460

245862

260177

261891

266072

267214

268628

269068

272373

272500

272682

273163*

273177*

273276*

273387*

273426*

273474*

273521*

273570*

273594*

273613*

273628*

273656*

273659*

273670*

273685*

273974*

274830*

275048*

275282*

Work Orders/Work Requests

40132620

228569

264381

265516

287160

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

20131

24898

24957

25151

29382

2137168

2140612

2156562

2158284

2169614

2172204

2197408

2199855

200623

200705

202923

207011

210450

239906

23905

236037

242520

248447

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

26947

2065778

2083865

2112715

2132520

2136567

2199219

22634

265706

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