IR 05000443/2022011

Design Basis Assurance Inspection (Teams) Inspection Report 05000443/2022011

ML22081A150
Person / Time
Site:	Seabrook
Issue date:	03/22/2022
From:	Mel Gray Division of Operating Reactors
To:	Coffey B Florida Power & Light Co
Gray M
References
IR 2022011
Download: ML22081A150 (10)

Text

March 22, 2022

SUBJECT:

SEABROOK STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS)

INSPECTION REPORT 05000443/2022011

Dear Mr. Coffey:

On February 10, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station and discussed the results of this inspection with Mr. Brian Booth, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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 at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety

Docket No. 05000443 License No. NPF-86

Enclosure:

As stated

Inspection Report

Docket Number:

05000443

License Number:

NPF-86

Report Number:

05000443/2022011

Licensee:

NextEra Energy Seabrook, LLC

Facility:

Seabrook Station

Location:

Seabrook, NH

Inspection Dates:

January 23, 2022 to February 10, 2022

Inspectors:

C. Bickett, Senior Reactor Inspector

P. Cataldo, Senior Reactor Inspector

K. Mangan, Senior Reactor Inspector

B. Pinson, Reactor Inspector

M. Rossi, Resident Inspector

A. Turilin, Reactor Inspector

Approved By:

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Seabrook Station, 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.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were 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 licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams)

The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)

=

(1)480V BUS E62, 1-EDE-US-62

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance records, and corrective action history

• Equipment/environmental controls and qualification

• Adequacy of design (calculations and modifications)

• Surveillance testing and test results

• System and component level performance monitoring

• Equipment protection from fire, flood, steam, water intrusion, or spray

• Control logic

• Contactor and fuse ratings

• Component adequacy for minimum voltage

• Protection coordination (load in-rush and full load current)

• Range, accuracy, and setpoint of installed instrumentation

• Operator actions

• Process medium availability (electrical signal)

• Energy source availability (electricity)

The team used Appendix B guidance for Switchgear and Motor Control Centers.

(2) Start-Up Feed Pump, 1-FW-P-113

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance records, and corrective action history

• Equipment/environmental controls and qualification

• Adequacy of design (calculations and modifications)

• Surveillance testing and test results

• System and component level performance monitoring

• Heat removal cooling water and ventilation

• Operator actions

• Process medium availability (water, air, electrical signal)

• Energy source availability (electricity, steam, fuel, air)

The team used Appendix B guidance for Pumps.

(3) A Service Water Pump, P-41A

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents/procedures

• System health report, maintenance records, and corrective action history

• Adequacy of design (calculations and modifications)

• Surveillance testing and test results

• System and component level performance monitoring

• Equipment protection from fire, flood, steam, water intrusion, or spray

• Heat removal ventilation

• Control logic

• Component adequacy for minimum voltage

• Range, accuracy, and setpoint of installed instrumentation

• Operator actions

• Process medium availability (water)

• Energy source availability (electricity)

The team used Appendix B guidance for Pumps.

(4) PCCW Train B Heat Exchanger, 1-CC-E-17-B

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Consistency among design and licensing bases and other documents/procedures

• Adequacy of design (calculations and modifications)

• System and component level performance monitoring

• Heat removal cooling water and ventilation

• Process medium availability (water, air)

The team used Appendix B guidance for As Built Systems.

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)

(1) RHR ventilation dampers, 1-EAH-FN-31A

• Energy source availability (electricity, steam, fuel, air)

• Operator Actions

• Normal, abnormal, and emergency operating procedures

• Control logic

• Component adequacy for minimum voltage

• Range, accuracy, and setpoint of installed instrumentation

• Adequacy of design (calculations and modifications

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• System health report, maintenance records, and corrective action history

• Consistency among design and licensing bases and other documents/procedures

• System and component level performance monitoring

• Surveillance testing and test results

• Equipment/environmental controls and qualification

• Heat removal cooling water and ventilation

The team used Appendix B guidance for Electrical Motors, Fans, and EQ Splices/Maintenance/Surveillance Requirements.

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) EC 287676, Leading Edge Flowmeter (LEFM) Electronics Package Replacement

(2) EC 287967, Replacement Vital Battery 1B & 1D (Train B)

(3) EC 295498, Containment Analysis Update for Heat Exchanger Calibration

(4) EC 291089, Emergency Feedwater Pump House Water In-Leakage Seal Repair

(5) EC 144952, DG Lube Oil Temperature Control Valve Modification

(6) EC 250048, Steam Generator Feed Pump Turbine Control Digital Upgrade

Review of Operating Experience Issues (IP Section 02.06) (2 Samples)

(1) IN 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2

(2) IN 2015-01, Degraded Ability to Mitigate Flooding Events

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On February 10, 2022, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Brian Booth, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

4.3.08-72F

SW System Steady State Analysis

Rev. 11

737-23

Startup Feedwater Pump NPSHA and Upstream Line Loses

Rev. 2

9763-3-ED-00-

2-F

Voltage Regulation

Rev. 14

9763-3-ED-00-

31-F

480 V Coordination

Rev. 04

C-S-1-20801

Emergency Feedwater System Flow Study

Rev. 1

C-S-1-28002

Containment LOCA Response Using GOTHIC

Rev. 3

C-S-1-28003

Containment MSLB Response Using GOTHIC

Rev. 1

C-S-1-83618

Ocean and Cooling Tower Service Water Pump IST

Acceptance Criteria

Rev. 9

C-X-1-21802

Expansion Joint Rupture in the Circulating Water System

Located in the Turbine Building

Rev. 3

Corrective Action

Documents

2340882

AR02418201

Corrective Action

Documents

Resulting from

Inspection

2418427

2416980

2417001

2417066

2417367

2417533

2417741

2418201

2418259

2418300

2418331

2418515

2418520

2418528

Drawings

1-CC-B20211

Primary Component Cooling Loop B Detail

Rev. 22

1-DG-D20463

Diesel Generator Lube Oil System Train B Detail

Rev. 18

1-FW-D20688

Emergency Feedwater System Details

Rev. 20

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Changes

EC 144952

DG Lube Oil Temperature Control Valve Modification

1-DG-V-29-

A/B, Rev.

004

EC 250048

Steam Generator Feed Pump Turbine Digital Upgrade

Project

Rev. 12

EC 287967

Replacement Vital Battery 1B & 1D (Train B) LTAM SEA 16-

0045

Rev. 004

EC 291089

EFWPH Water In-Leakage Seal Repair

Rev. 2

EC 295498

Containment Analysis Update for Heat Exchanger

Calibration

Rev. 0

Engineering

Evaluations

EE 90-10

Evaluation of Submerged Cables

03/09/1990

EE-04-015

Response to NRC IR2004-003, Apparent Violation: DCR 97-

033 10 CFR 50.59 (Turbine Building Flood Protection)

Rev. 0

EE-98-006

SW Pump Curves

Rev. 000

Miscellaneous

C-S-1-28009

Primary Containment Cooling Water System Heat Loads

and Flow Rates for Various Plant Operating Modes After

SPU

Rev. 0

FP22285

Start-Up Feed Pumps Instructions Manual, Centrifugal Pump Rev. 0

FP57916

PCCW Heat Exchanger Instr Manual

Rev. 000

FP700356

Failure Modes and Effects Analysis of the Seabrook Nuclear

Stations Steam Generator Feed Pump Turbine Digital

Control Upgrade Project - EC 250048

Rev. 0

Procedures

ES1850.017

SW Heat Exchanger Program

Rev. 06

ON1090.13

Response to Natural Phenomena Affecting Plant Operations

Rev. 24

OP-AA-109

Control of Time Critical Operator Actions and Time Sensitive

Actions

Rev. 5

OS1238.02

Turbine Building Flooding

Rev. 6

OS1246.02

Degraded Vital AC Power (Plant Operating)

Rev. 25

OX1412.06

Monthly PCCW Loop B Valve Verification

performed

2/08/22

OX1436.08

Startup Feed Pump Quarterly Surveillance

Performed

10/25/21

OX1456.86

Operability Testing of IST Pumps

Rev. 24

SM 7.20

Control of Time Critical Operator Actions and Time Sensitive

Rev. 15

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Actions

Work Orders

40577309

40405785-01

40405785-02

40405785-03

40508958

01195389

40638933

40725546

40079149-01

40632779-01