IR 05000280/2025003

Integrated Inspection Report 05000280/2025003 and 05000281/2025003

ML25330A009
Person / Time
Site:	Surry
Issue date:	12/02/2025
From:	Shawn Smith NRC/RGN-II/DORS/PB6
To:	Carr E Dominion Energy
References
IR 2025003
Download: ML25330A009 (0)

Text

SUBJECT:

SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2025003 AND 05000281/2025003

Dear Eric S. Carr:

On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station. On November 21, 2025, the NRC inspectors discussed the results of this inspection with James Shell, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.

However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.

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

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Surry Power Station.

December 2, 2025 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, Steven P. Smith, Chief Projects Branch 6 Division of Operating Reactor Safety Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000280 and 05000281

License Numbers:

DPR-32 and DPR-37

Report Numbers:

05000280/2025003 and 05000281/2025003

Enterprise Identifier:

I-2025-003-0031

Licensee:

Dominion Energy

Facility:

Surry Power Station

Location:

Surry, VA

Inspection Dates:

July 1, 2025, to September 30, 2025

Inspectors:

S. Battenfield, Operations Engineer

W. Deschaine, Senior Project Engineer

C. Even, Senior Project Engineer

K. Henry, Regional Governmental Liaison Officer

D. Jung, Senior Resident Inspector

A. Nielsen, Senior Health Physicist

D. Orr, Senior Project Engineer

M. Read, Senior Resident Inspector

D. Restrepo, Resident Inspector

M. Rich, Emergency Preparedness Inspector

J. Rivera, Health Physicist

J. Walker, Senior Emergency Preparedness Inspector

Approved By:

Steven P. Smith, Chief

Projects Branch 6

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Surry Power 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. A licensee-identified non-cited violation is documented in report section: 71124.0

List of Findings and Violations

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

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. On August 6, 2025, the unit experienced a reactor trip due to a spurious actuation of high consequence limiting safeguards (CLS) train B' due to a failed Hi CLS 1B relay. Following correction of the cause of the reactor trip, the unit was returned to rated thermal power on August 11, 2025.

Unit 2 operated at or near rated thermal power for the entire 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 (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1)

'A' emergency service water pump (ESWP) during 'B' ESWP performance testing on July 17, 2025

(2) Unit 1 turbine driven auxiliary feedwater pump (TDAFWP) following Unit 1 startup on August 13, 2025

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 TDAFWP system on September 4, 2025.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) Number 3 emergency diesel generator (EDG) room, fire area 8, elevation 27 feet - 6 inches, on July 16, 2025

(2) Charging pumps, Unit 1 auxiliary building, fire area 17, elevation 13 feet and elevation 2 feet, on July 18, 2025

(3) Unit 2 safeguards complex, fire area 20, elevations 27 feet - 6 inches and 11 feet - 6 inches, on August 1, 2025

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on August 19, 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 main control room (MCR) during Unit 1 reactor trip due to spurious train B Hi CLS system actuation on August 6, 2025.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the simulator during a licensed operator requalification training involving vital bus offsite power lost due to reserve station service transformer lockout, and large break loss of coolant accident (LOCA) inside containment on July 29, 2025.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Partial)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1)

(Partial) Unit 1 heat trace panel that supports hydrogen analyzer found not energized on August 19, 2025 (Condition Report [CR] 1298739)

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 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) Medium risk plan review during train B of spent fuel pool cooling on July 30, 2025

(2) Medium risk plan review prior to the input/output (I/O) amplifier card replacement in Unit 2 rod control cabinet on July 31, 2025

(3) High risk plan review during train B Hi CLS relay replacement in Unit 1 CLS cabinet number 1 on August 7, 2025

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) CR1295193, 1-FW-P-2, Unit 1 TDAFWP, outboard bearing low oil pressure during surveillance testing on July 1, 2025

(2) CR1295657, 2-SW-P-10B, Unit 2 charging pump service water (CPSW) pump, flow transient during CPSW check valve (1-SW-108) maintenance on July 8, 2025

(3) CR1296765, 2-EE-PI-227, number 2 EDG fuel system number 1 outlet pressure, reads incorrectly on July 21, 2025

(4) CR1298780, corrosion on stud/nuts for inlet flange to self-cleaning strainer that supports main control room chillers on August 22, 2025

(5) CR1301871, letdown ion exchanger differential pressure exceeded 80 pounds with 1-CH-I-3B, 3B deborating demineralizer, in service on September 26, 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 (PMT) (IP Section 03.01) (6 Samples)

(1)1-IPT-CLS-HIHI-LGC-8.5B, Consequence Limiting Safeguards Logic Train B (Hi-Hi CLS), following Hi-Hi CLS relay replacement on July 2, 2025 (Work Order [WO]

===38204373574)

(2) PMT-CMP-OP-01, Component In-Service Visual Leak Test, following number 2 EDG fuel filter pressure gauge replacement on July 21, 2025 (WO 38204374933)

(3)0-OP-SW-002, Emergency Service Water Pump 1-SW-P-1B, following 1B ESWP maintenance package on July 21, 2025 (WO 38204356516)

(4)0-OPT-EG-009, Number 3 Emergency Diesel Generator Major Maintenance Operability, following 6-year and 18-month planned maintenance on August 15, 2025 (WO 38204341144)

(5)2-OPT-RX-005, Control Rod Assembly Partial Movement, following Unit 2 rod control cabinet I/O amplifier card reseating on August 19. 2025 (WO 38204375428)

(6)2-PT-18.8, Charging Pump Service Water Performance, following Unit 2 B CPSW pump preventative maintenance on August 21, 2025 (WO 38204328385)

Surveillance Testing (IP Section 03.01)===

(1)0-OSP-AAC-001, Quarterly Test of 0-AAC-DG-OM, Alternate Alternating Current Diesel Generator, on July 7, 2025 (2)1-OPT-EG-001, Number 1 Emergency Diesel Generator Quarterly Performance Test, on July 28, 2025 (3)1-OPT-CH-003, Charging Pump Operability and Performance Test for 1-CH-P-1C, on July 11, 2025 (4)2-IPT-CLS-HI-LGC-8.4A, Consequence Limiting Safeguards (Hi-Train A), on September 16, 2025

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level (EALs), Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of July 21, 2025. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) The inspectors observed a licensed operator training evolution in the MCR simulator that contributed to the Emergency Response Organization Performance Indicators on August 26, 2025. Events included vital bus offsite power lost due to reserve station service transformer lockout, and large break LOCA inside containment requiring containment spray manual start.

71114.07 - Exercise Evaluation - Hostile Action (HA) Event

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of July 22, 2025. The scenario began with a simulated report from the field that a hostile action was occurring outside the protected area, thus meeting the criteria for declaration of an Alert. Subsequently, simulated adversaries breached the protected area and engaged site security, and a Site Area Emergency was declared. As the scenario progressed, a simulated explosion occurred near low-head safety injection piping. The percussive force caused check valves to fail, allowing reactor coolant system leakage and causing fuel damage, which resulted in increasing radiation levels. When effluent radiation levels reached a prescribed threshold, conditions for a General Emergency were met, and the Offsite Response Organizations demonstrated their ability to implement emergency actions.

71114.08 - Exercise Evaluation - Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (3 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Ventilation vent 1, particulate, iodine, noble gas, tritium, weekly sample collection

(2) Liquid radwaste discharge pathway, through effluent monitor 1-RRM-RE-131

(3) Ventilation vent 2, particulate, iodine, noble gas, tritium, weekly sample collection

Sampling and Analysis (IP Section 03.02) (3 Samples)

Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:

(1)1-GW-RM-130B, Process vent noble gas monitor, compensatory sampling, July 31, 2023 (2)1-SW-RM-120, Circulating water discharge monitor, compensatory sampling, September 19 - September 20, 2024 (3)1-VG-RM-131B, Ventilation vent 2 gaseous effluent monitor, sample line configuration

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) L-20250604-118-B, liquid waste release permit

(2) G-20250601-142-C, Gaseous release permit

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===

(1) Unit 1 (October 1, 2023, through December 31, 2024)

(2) Unit 2 (October 1, 2023, through December 31, 2024)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (October 1, 2023, through December 31, 2024)

(2) Unit 2 (October 1, 2023, through December 31, 2024)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (October 1, 2023, through December 31, 2024)

(2) Unit 2 (October 1, 2023, through December 31, 2024)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) May 10, 2024, through July 15, 2025

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) July 1, 2024, through March 31, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)

(1) July 1, 2024, through March 31, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)

(1) July 1, 2024, through March 31, 2025

===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Partial)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1)

(Partial) Units 1 and 2 TDAFWP surveillance test failures (CR1284152, 1280548, and 1283327)71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)===

(1) The inspectors evaluated Unit 1 reactor trip due to the spurious Hi CLS actuation and licensees response on August 6, 2025. Per IMC 0309, Reactive Inspection Decision Basis for Power Reactors, the NRC considered whether this inspection sample should be the subject of a reactive inspection and determined that a reactive inspection was not necessary, as documented in ML25237A179.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71124.06 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Technical Specification 6.4 N(1) requires effluent monitor surveillance to be performed in accordance with the methodology in the ODCM. Attachment 2 of the ODCM requires that 1-SW-RM-120, Unit 1 circulating water discharge monitor, be calibrated on an 18-month frequency. Contrary to this, on June 24, 2024, the grace period for the most recent 18-month cycle expired without calibration being performed. The delays were due to a calibration source that had decayed below the point of usability, and a technical evaluation (TE) that incorrectly determined it was acceptable to extend the calibration out for an additional 6 months. Licensee staff identified the error in September of 2024, initiated compensatory sampling, and performed a causal evaluation. With assistance from the radiation monitor vendor, the licensee was able to perform a calibration on September 19, 2024, however the detector was found to be out of tolerance and had to be replaced.

Significance/Severity: Green. The finding was part of the licensee's effluent release program, but it did not represent a failure to implement the program and did not involve any release of radioactive material into the environment.

Corrective Action References: CR 1261927 and CR

EXIT MEETINGS AND DEBRIEFS

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

• On November 21, 2025, the inspectors presented the integrated inspection results to James Shell, Plant Manager, and other members of the licensee staff.

• On July 17, 2025, the inspectors presented the radiation protection inspection results to James Shell, Plant Manager, and other members of the licensee staff.

• On July 24, 2025, the inspectors presented the emergency preparedness inspection results to David Wilson, 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

Resulting from

Inspection

CR 1300045

NRC questions regarding auxiliary feedwater system

09/05/2025

11548-FM-064A -

Sheet 4 of 6

Flow/Valve Operating Numbers Diagram Main Steam

System Surry Power Station Unit 2

Revision 59

Drawings

11548-FM-068A -

Sheet 3 of 4

Flow/Valve Operating Numbers Diagram Feedwater System

Surry Power Station Unit 2

Revision 73

0-OPT-SW-001

Emergency Service Water Pump 1-SW-P-1A

2-OP-28A

Main Steam System Valve Alignment

Revision 24

2-OP-FW-001A

Auxiliary Feedwater System Valve Alignment

Revision 8

2-OP-FW-008

Resetting Turbine Driven AFW Pump Overspeed Trip and

Throttle Valve

Revision 5

71111.04

Procedures

SDBD-SPS-AFW

System Design Basis Document for Auxiliary Feedwater

System

Revision 32

CR 1296626

NRC identified - Fire Strategy Discrepancy

07/18/2025

CR 1296631

NRC questioned charging pump seal area posting

07/18/2025

Corrective Action

Documents

Resulting from

Inspection

CR 1299492

NRC identified fire drill critique item

08/28/2025

0-FS-FP-123

Diesel Generator Room Number 3 Elevation 27 Feet - 6

Inches

Revision 2

1-FS-FP-157

Charging Pumps - Unit 1 Auxiliary Building Elevation 13 Feet

- 0 Inches and 2 Feet - 0 Inches

Revision 3

2-FS-FP-140

Safeguards Basement - Unit 2 Elevation 11 Feet - 6 inches

Revision 3

71111.05

Fire Plans

2-FS-FP-141

Safeguards Spray Side - Unit 2 Elevation 27 Feet - 6 Inches

Revision 2

71111.11Q

Procedures

RQ-25.6-SP-1

25 Cycle 25.6 Sim Exam

Revision 0

71111.13

Procedures

WM-AA-301

Operational Risk Assessment

Revision 27

71111.24

Corrective Action

Documents

Resulting from

Inspection

CR 1298587

NRC identified mark number typo in 0-OPT-EG-009

08/17/2025

71114.04

Procedures

Surry Emergency

Surry Emergency Action Level Matrix

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Action Level

Matrix

Surry Emergency

Action Level

Technical Basis

Document

Surry Emergency Action Level Technical Basis Document

Surry Emergency

Plan

Surry Emergency Plan

VPAP-2802

Notifications and Reports

71114.06

Procedures

RQ-25.6-SP-1

25 Cycle 25.6 Sim Exam

Revision 0

71114.07

Procedures

EP-AA-CSD-311

Interface with Off-site Incident Command

Rev 2

CA 1261927

Level of Effort Evaluation

10/25/2024

CR 1261927

Calibration source (Ba-133, SN 339A) strength below reqd

for calibration of the 01-SW-RM-120

06/13/2024

CR 1269294

1-SW-RM-120 Calibration not IAW the ODCM requirements

09/19/2024

Corrective Action

Documents

CR 1273152

Alarm setpoint for 2-SW-RM-220 needs evaluated IAW 0-

HPS-RMSS-001

10/21/2024

71124.06

Procedures

EP-AA-303

Surry Power Station - Equipment Important to Emergency

Response

Revision 31

CR 1218540

22 Meteorological Data recovery rate < 90%

2/01/2023

CR 1224716

Entered AP-35.01 Radioactive liquid release control

04/16/2023

CR 1233055

Leak of contaminated water near 2-CS-36 (B RWST cooler

inlet isolation)

07/13/2023

Corrective Action

Documents

CR 1295308

24 Meteorological Data recovery rate < 90%

07/02/2025

Corrective Action

Documents

Resulting from

Inspection

CR 1296565

Non-functional groundwater monitoring well

07/17/2025

Procedures

0-IPM-MM-PR0-

001

Primary Meteorological Tower Instrumentation Calibration

Rev. 10

204236171

Piping Repair / Replacement, Water Table extraction Well

(Deep), 01-PL-PIEZ-P51-PIPE

05/15/2025

71124.07

Work Orders

204358683

PM/CAL Primary Met Tower Instrumentation

03/19/2025

71151

Corrective Action

CR1239515

TSC Full Staff ERO position below preferred depth (EPC)

10/02/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR1241484

Quarterly TSC Battery Checks Unacceptable

10/23/2023

CR1252705

TSC missing and tampered with items

03/06/2024

CR1257470

TSC video wall not working properly

04/23/2024

CR1265011

Five (5) ERO members did not attend nor have

replacements for SJUL24 TD on 7/23/24

07/24/2024

CR1265066

Surry NRC ENS line had no dial tone during SJUL24TD

07/25/2024

CR1267462

Primary Met tower upper wind direction point unavailable

08/27/2024

CR1273137

Differences between NAPS and SPS target power levels for

secondary plant issues.

10/21/2024

Documents

CR1293950

Backup MET tower wind direction indication is responding

differently than the primary MET tower.

06/12/2025