IR 05000443/2025002
| ML25210A005 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/29/2025 |
| From: | Matt Young Division of Operating Reactors |
| To: | Coffey B NextEra Energy |
| References | |
| IR 2025002 | |
| Download: ML25210A005 (1) | |
Text
July 29, 2025
SUBJECT:
SEABROOK STATION - INTEGRATED INSPECTION REPORT 05000443/2025002
Dear Bob Coffey:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station. On July 9, 2025, the NRC inspectors discussed the results of this inspection with David Sluszka, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety
Docket No. 05000443 License No. NPF-86
Enclosure:
As stated
Inspection Report
Docket Number:
05000443
License Number:
Report Number:
Enterprise Identifier: I-2025-002-0047
Licensee:
NextEra Energy Seabrook, LLC
Facility:
Seabrook Station
Location:
Seabrook, New Hampshire
Inspection Dates:
April 1, 2025 to June 30, 2025
Inspectors:
T. Daun, Senior Resident Inspector
S. Flanagan, Resident Inspector
N. Eckhoff, Health Physicist
E. Miller, Senior Reactor Inspector
Approved By:
Matt R. Young, Chief
Projects Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. NRC continued monitoring the licensees performance by conducting an integrated 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.
PLANT STATUS
Seabrook Station began the inspection period operating at 100 percent rated thermal power and remained at or near full power for the duration of the inspection period.
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 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in Inspection Manual Chapter 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the following systems from May 5, 2025 through June 12, 2025:
- Off-site alternating current power
- On-site alternating current power
- Ventilation systems for safety-related areas
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'A' cooling tower service water during 'B' cooling tower electrical outage on May 6, 2025
- (2) Turbine driven emergency feedwater pump during surveillance of the motor-driven emergency feedwater pump on May 22, 2025
- (3) Emergency feedwater system during 'B' emergency diesel generator maintenance on June 3, 2025 (4)
'A' emergency diesel generator and supplemental electrical power systems during 'B' emergency diesel generator maintenance on June 6, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Primary auxiliary building primary component cooling water pump area (PAB-F-2A,B,C-Z) on April 30, 2025
- (2) Mechanical piping penetration areas (PP-F-1A-Z) on May 27, 2025 (3)
'C' electrical tunnel (PAB-F-1G-A) on June 10, 2025
- (4) West pipe chase stairs (MS-F-1B-Z) on June 10, 2025
- (5) Service water pump house (SW-F-1B,1C,1D,1E-Z) on June 30, 2025
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the cable spreading room.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1) 'B' emergency diesel generator jacket water heat exchanger on June 6, 2025
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during routine operability surveillance of control rods on May 19, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator training conducted in the plant reference simulator on June 2, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Service water cooling tower fan failure on May 30, 2025
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Quality control storage and issuance of safety-related reactor coolant system flow transmitter 2-RC-FT-426 on June 23, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Risk management actions associated with turbine control system control pack failure on April 1, 2025
- (2) Risk management actions associated with unit substation 64 outage on May 6, 2025
- (3) Risk management actions with the 'B' emergency diesel generator maintenance outage from June 2-6, 2025
- (4) Risk management actions with the 'A' main feed pump power pack replacement on June 26, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Emergency feedwater system following loss of control power to the 'B' train flow control value for the 'D' steam generator on April 7, 2025 (2)
'A' gamma metrics (NI-N-6690) abnormal indications on May 5, 2023 (3)
'B' emergency diesel generator jacket cooling water outlet temperature controller on June 6, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Temporary modification to block cable spreading room floor drain on June 20, 2025
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (IP Section 03.01) (5 Samples)
(1)
'A' residual heat removal isolation valve retest following diagnostic calibration on April 15, 2025
- (2) Control rod retest following replacement of oscillator card for rod control on April 23, 2025 (3)
'B' diesel generator emergency power sequencer following replacement of power supplies on June 4, 2025 (4)
'B' emergency diesel generator following component maintenance window on June 6, 2025 (5)
'B' diesel generator switchgear breaker trip checks following replacement of 'C' phase bus overcurrent relay on June 6, 2025
Surveillance Testing (IP Section 03.01) (5 Samples)
(1)
'A' emergency feedwater pump surveillance on April 24, 2025 (2)
'B' cooling tower surveillance on April 29, 2025
- (3) Electric driven emergency feedwater pump quarterly surveillance on May 22, 2025
- (4) Supplemental emergency power system diesels surveillance on June 4, 2025 (5)
'A' emergency diesel generator semiannual fast start operability surveillance on June 17, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Operations out of the box evaluation which included emergency classifications and notifications on June 2,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving a radiologically controlled area
- (2) Workers exiting the radiologically controlled area
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Diving operations in the spent fuel pool to replace the spent fuel transfer gate
- (2) Valve manipulation in the demineralizer alley which is a contamination area and a locked high radiation area
- (3) Surveys in the radioactive materials support building to evaluate for radiological changes
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:
- (1) Volume control tank room
- (2) Waste processing building processing skid demineralizers
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) South side wall, trailer, and sea-van storage location
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Spent resin processing system
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)2024 reactor coolant system filter #L108395-1 (2)2024 liquid waste filter #L108395-3
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed the preparation of radioactive shipment 25-017 of dry active waste on June 24, 2025.
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment #24-025, UN2912, dry active waste, low specific activity (LSA-I)
- (2) Shipment #25-003, UN2915, refuel equipment, type A
- (3) Shipment #25-012, UN3321, resin, low specific activity (LSA-II)
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures Sample (IP Section 02.04)===
- (1) For the period April 1, 2024 through March 31, 2025
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) For the period April 1, 2024 through March 31, 2025
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) For the period April 1, 2024 through March 31, 2025
===71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03)===
The inspectors reviewed the licensees implementation of its corrective action program related to the following:
- (1) Main steam isolation valve connector issues
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in control room/panel deficiencies that might be indicative of a more significant safety issue.
71153 - Follow-up of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) Event Notification 57652, Auxiliary Feedwater System Inoperable, on April 8, 2025, and subsequent retraction on April 9, 2025. The inspection conclusions associated with this event notification are documented in this report under Inspection Results Section
INSPECTION RESULTS
Observation: Semiannual Trend Review 71152S The inspectors reviewed Seabrooks corrective action program for trends that might be indicative of more significant safety issues. The inspectors reviewed condition reports, level one assessments, system health reports, and control room/panel deficiencies. In particular, the inspectors evaluated the operator challenges program including an audit of control room deficiencies, control board notifications, and operator workarounds.
Based on the overall results of the semiannual trend review, the inspectors determined that issues were appropriately evaluated by Seabrook staff for potential trends and resolved within the scope of the corrective action program and other requisite procedures.
Observation: Event Notification 57652, Auxiliary Feedwater System Inoperable 71153 Event Notification 57652, Auxiliary Feedwater System Inoperable, on April 8, 2025 and subsequent retraction on April 9, 2025. This event resulted from the loss of control power to the 'B' train emergency feedwater flow control valve to the 'D' steam generator (FW-FV-4244-B). The in-line 'A' train emergency feedwater flow control valve (FW-FV-4244-A) remained functional, as did the capability of the auxiliary feedwater system to supply all steam generators with condensate flow. With an inoperable valve in the auxiliary feedwater flow path, the emergency feedwater flow system is no longer single failure tolerant and Technical Specification 3.7.1.2, action D was entered at 20:00 on April 7, 2025.
The safety functions associated with the emergency feedwater flow system are:
1. Supply feedwater to the steam generators to remove decay heat in the event of a loss
of main feedwater;
2. Provide an auto close feature to isolate the affected steam generator in the event of a
high flow condition to prevent inadvertently draining the condensate storage tank.
With FW-FV-4244-B failed in the open position, the emergency feedwater flow system was still able to perform both safety functions. In the open position, FW-FV-4244-B does not present an obstruction to feeding the D steam generator. The auto isolation safety function is still able to be performed by FW-FV-4244-A, a fully redundant valve.
Inspectors reviewed the reasons behind the initial submittal and subsequent retraction and did not identify any concerns based on the ability of the 'A' emergency feedwater train remaining capable of fulfilling the emergency feedwater safety functions.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 3, 2025, the inspectors presented the radiological hazard assessment and exposure control inspection results to David Sluszka, Site Vice President, and other members of the licensee staff.
- On July 9, 2025, the inspectors presented the integrated inspection results to David Sluszka, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2464528
2464957
2470656
2476962
Procedures
Seasonal Readiness
Revision 43
OS1246.02
Degraded Vital AC Power (Plant Operating)
Revision 26
Work Orders
40826007
40988087
40988096
41002674
Drawings
1-MS-B20582
Main Steam Emergency Feedwater Pump Supply
Revision 21
Work Orders
41014419
Corrective Action
Documents
Resulting from
Inspection
2517438
Drawings
1-NHY-BD-2006
Control Building - Cable Spreading Room and Mechanical
Rooms
Revision 3
Moderate Energy Line Break Study
Revision 5
Engineering
Changes
Structural Modification of the Control and Diesel Generator
Building Walls
Corrective Action
Documents
2516641
2516642
2516643
2516644
Engineering
Changes
Channel Head Erosion Coatings for 'A' and 'B' EDG Heat
Exchangers
Procedures
MS0517.12
Application and Repair of Protective Coatings
Revision 22
Work Orders
41020665
41020666
274990
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
274991
71111.11Q Procedures
OX1410.02
Rod Operability Surveillance
Revision 32
Corrective Action
Documents
2404429
2516392
2516507
2516512
2516548
07-09770
Miscellaneous
EVT-SW-2021-
2170
Maintenance Rule Functional Failure Determination
EVT-SW-2025-
2123
Maintenance Rule Functional Failure Determination
NCR 07-010
Nonconformance Report for Unit 2 Components
Revision 1
Request 2025-
2
Material Request, Issue, Transfer Form for 2-RC-FT-426
RIR 13434
Receipt Inspection Report for 2-RC-FT-426
Procedures
EQ 2.6
Engineering Design Standards for Shelf Life
Revision 5
MPM 6.10
Obtaining Unit 2 Materials: Retags, Transfers and Issues
Revision 3
QI-4-NSC-11
Obtaining Seabrook Unit 2 Materials
Revision 3
QI-7-NSC-1
Warehouse Receipt, Storage, Issuance and Maintenance
Revision 16
Work Orders
41002591
Corrective Action
Documents
2516639
2516647
2517850
Work Orders
40869167
40869169
40890675
40987705
41000730
41022405
Corrective Action
Documents
2512795
2514753
2517781
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
1-NHY-310844
Emergency FW Valve 1-FV-4244-B Schematic Diagram
Revision 10
Engineering
Changes
Design Change
Procedures
DBD-EFW-01
Design Basis Document Emergency Feedwater System
Revision 10
IX1656.970
NI-N-6690 Excore Neutron Flux Monitoring Train A
Calibration
Revision 11
Work Orders
40956047
40981602
41014491
41017918
41022388
Corrective Action
Documents
Resulting from
Inspection
2517438
Engineering
Changes
EC-UCR300346
UFSAR Update to Support CSR Floor Drain removal Per
EC294654
Structural Modification of the Control and Diesel Generator
Building Walls
Corrective Action
Documents
2492315
2493601
2494320
2503759
2507434
2507485
2507486
2509611
2511964
2513953
2516392
2517026
Drawings
1-NHY-509024
Rod Control Demand Control
Revision 3
Procedures
1-DG-OT024
Aligning DG 1B Controls for Auto Start
Revision 7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DG-CP-80-MAN-
1-DG-CP-80; DG B EPS Power Supplies PS-1 and PS-2
Replacement
N/A
LS0563.58
Trip Check Procedure for the Diesel Generator Switchgear
Breakers
Revision 6
OS1007.01
Automatic and Manual Rod Control
Revision 17
OS1026.09
DG 1B Semiannual Operability Surveillance
Revision 35
OX1413.01
A Train RHR Quarterly Flow and Valve Stroke Observation
Revision 33
OX1416.05
Service Water Discharge Valves Quarterly Test and 18
Month Position Verification
Revision 14
OX1416.06
Service Water Cooling Tower Pumps Quarterly Test
Revision 32
OX1426.03
Emergency Power Sequencer 18 Month Operability Test
Revision 11
OX1426.26
DG 1A Semiannual Operability Surveillance
Revision 36
OX1436.02
Turbine Driven Emergency Feedwater Pump Quarterly Valve
Alignment
Revision 38
OX1436.03
Electric EFW Pump Quarterly Surveillance
Revision 30
OX1461.04
SEPS Monthly Availability Surveillance
Revision 17
Work Orders
40669834
40743816
40743820
40818989
40826674
40861100
40873559
40885456
40888008
40890175
40890178
40894086
40894431
40894432
40894706
40894732
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40895006
40971681
40981602
40981603
40981799
40986025
40986712
40986713
40987703
40993207
41002981
41003246
41004050
41013045
41013745
41016103
41020757
41020758
41020972
271505
272646
Miscellaneous
CFD 24-01
Seabrook Emergency Preparedness
1/31/24
Procedures
EPDP-03
Emergency Preparedness Performance Indicators
Revision 27
Corrective Action
Documents
2498822
2500862
Drawings
1-NHY-300219
Service Environment Chart
Revision 35
Procedures
DBD-EQ-01
Environmental Qualification of Electrical Equipment
Important to Safety
Revision 4
Condition Reporting
Revision 47