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Integrated Inspection Report 05000244/2025003
	ML25351A172
Person / Time
Site:	Ginna
Issue date:	12/18/2025
From:	Jason Schussler; Division of Operating Reactors
To:	Mudrick C; Constellation Energy Generation, Constellation Nuclear
References
	IR 2025003
	Download: ML25351A172 (0)
	v • d • e

December 18, 2025

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000244/2025003

Dear Christopher Mudrick:

On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant. On December 4, 2025, the NRC inspectors discussed the results of this inspection with Richard Everett, Site Vice President, 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 1, 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, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 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 I; the Director, Office of Enforcement; and the NRC Resident Inspector at R.E. Ginna Nuclear Power Plant.

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, Jason E. Schussler, Chief Projects Branch 1 Division of Operating Reactor Safety

Docket No. 05000244 License No. DPR-18

Enclosure:

As stated

Inspection Report

Docket Number:

05000244

License Number:

DPR-18

Report Number:

05000244/2025003

Enterprise Identifier: I-2025-003-0044

Licensee:

Constellation Energy Generation, LLC

Facility:

R.E. Ginna Nuclear Power Plant

Location:

Ontario, New York

Inspection Dates:

July 1, 2025 to September 30, 2025

Inspectors:

C. Borman, Health Physicist

M. Fadden, Project Engineer

K. Poolman, Resident Inspector

C. Swisher, Senior Resident Inspector

Approved By:

Jason E. Schussler, Chief

Projects Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at R.E. Ginna Nuclear Power Plant, 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: 71111.1

List of Findings and Violations

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

Additional Tracking Items

None.

PLANT STATUS

Ginna began the inspection period operating at 100 percent rated thermal power and remained at, or near, rated thermal 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 (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.

REACTOR SAFETY

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

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

(1) Control room emergency air treatment system on August 21, 2025

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Auxiliary building upper level on August 12, 2025

(2) Auxiliary building lower level on August 20, 2025

(3) Intermediate building clean side middle level on September 18, 2025

(4) Intermediate building clean side lower level on September 28, 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 turnover activities on September 24, 2025, and September 28, 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 licensed operator training on September 9, 2025.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

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

(1)

'D' service water pump discharge check valve on July 15, 2025

(2) Fuel transfer tube gate isolation valve on July 30, 2025 (3)

'B' residual heat removal pump on August 6, 2025

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1)

'A' component cooling water system valve 4653B replacement on August 5, 2025

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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) Evaluation of plant risk (Green) of fire zones S05 and S06 after hourly fire tours were not performed on August 25, 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) Operability assessment of the fuel transfer tube gate isolation valve after discovering scaffolding attached to the valve reach rod on July 30, 2025

(2) Operability assessment of the microprocessor rod position indication system when main control board alarm C29, "Microprocessor Rod Position Indication System Failure," was received and locked in on July 31, 2025

(3) Operability assessment of the 'B' component cooling water pump motor after noted indications of elevated bearing vibrations on September 10, 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) (7 Samples)

(1) Functional testing of the 'C' charging pump following planned maintenance on July 8, 2025

(2) Operability testing of the 'A' residual heat removal pump cooler following cooler flush due to elevated differential pressure on July 14, 2025

(3) Operability testing of the 'B' auxiliary feedwater pump following a planned system outage window on July 15, 2025

(4) Functional testing of the 'A' instrument air compressor after identified increased differential pressure across the service water filter on July 15, 2025

(5) Operability testing of the reactor makeup water system following pressure control valve replacement on August 18, 2025

(6) Functional testing of 'A' instrument air compressor after completion of routine annual maintenance on September 8, 2025

(7) Operability testing of the motor driven fire pump following system outage window and motor replacement on September 19, 2025

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) STP-O-12.7B, "B Diesel Generator Starting Air Compressor Discharge Check Valve - Quarterly Requirements," on August 1, 2025

(2) STP-O-R-2.3A, "Diesel Generator A Trip Testing," on August 13, 2025

(3) STP-O-16QT-RECIRC, "Auxiliary Feedwater Turbine Pump - Quarterly (Recirculation Alignment)," on September 9, 2025

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) STP-O-2.2QA, "Residual Heat Removal Pump A Inservice Test," on July 17, 2025

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) The inspectors evaluated a training evolution in the simulator control room involving an Alert, Site Area Emergency, and General Emergency declaration due to a scenario which contained, but was not limited to, a simulated loss of coolant accident which later combined a loss of containment and fuel failure on July 29,

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, identifies the concentrations and quantities of radioactive materials, and 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) Observed personnel exiting the radiologically controlled area

(2) Observed the licensee surveys of potentially contaminated material leaving 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) Waste holdup tank piping modification (radiation work permit 25-00399)

(2) Loading shield sealant container with high radiation waste (radiation work permit 25-00202)

(3) Radiation protection job coverage on preventative maintenance (radiation work permit 25-00304)

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) Non-regenerative heat exchanger room

(2) Spent resin storage tank room

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.

71124.07 - 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 program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05)===

Main article: IP 71151