IR 05000244/2025004

Integrated Inspection Report 05000244/2025004

ML26040A033
Person / Time
Site:	Ginna
Issue date:	02/09/2026
From:	Jason Schussler Division of Operating Reactors
To:	Mudrick C Constellation Energy Generation, Constellation Nuclear
References
IR 2025004
Download: ML26040A033 (0)

Text

February 9, 2026

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000244/2025004

Dear Christopher Mudrick:

On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant. On January 21, 2026, 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.

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 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:

05000244/2025004

Licensee:

Constellation Energy Generation, LLC

Facility:

R.E. Ginna Nuclear Power Plant

Location:

Ontario, New York

Inspection Dates:

October 1, 2025 to December 31, 2025

Inspectors:

C. Swisher, Senior Resident Inspector

K. Poolman, Resident Inspector

C. Borman, Health Physicist

B. Dyke, Senior Operations Engineer

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

One licensee-identified non-cited violation is documented in this report.

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.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk significant systems from impending snow and cold weather on November 10, 2025.

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)

'A' vital battery on November 25, 2025

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

(1) The inspectors evaluated system configurations during a complete walkdown of the spent fuel pool cooling system on December 2, 2025.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)

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)

'B' battery room on October 16, 2025

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the biennial written examinations completed on February 14, 2025, and the requalification annual operating exam completed on November 21, 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 on October 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 November 18, 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) Visual in-service testing of piping and valves for the 'D' standby auxiliary feedwater system on October 30, 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 safety injection accumulators following increased frequency of accumulator level adjustments on October 28, 2025

(2) Operability assessment of the 'B' vital battery train when the 'B' battery charger failed to equalize voltage after card replacement on October 30, 2025

(3) Operability assessment of control room envelope habitability after discovering missing radiation shielding on December 8, 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) (3 Samples)

(1) Functionality testing of the 'B' spent fuel pool cooling pump on October 8, 2025

(2) Operability testing of pressurizer safety relief valves on November 12, 2025

(3) Operability testing of the 'D' standby auxiliary feedwater pump suction relief valve 9709B on November 13, 2025

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) S-29.2, "Charging Reactor Vessel Over-Pressure Protection System," on October 20, 2025

(2) STP-O-16QB, "Auxiliary Feedwater Pump B - Quarterly," on October 20, 2025

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Elevated unidentified leakage on December 2, 2025

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated an emergency drill in the simulator control room and technical support center 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 October 7, 2025.

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (5 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Ludlum Model 177 S/N 0018179 Spent Fuel Pool area

(2) Rad-Pro 5 S/N 0023560 Hot Shop

(3) Ludlum Model 3 S/N 0012088 Hot Shop

(4) Canberra Argos 5-AB Zeus S/N 1012-332 Access Control

(5) Alpha Beta Sample Counter Ludlum 3030P S/N 0023203 Containment Storage Building

Calibration and Testing Program (IP Section 03.02) (10 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Victoreen High Range Detector R-29

(2) Victoreen High Range Detector R-30

(3) Ludlum Model 177 S/N 0022703

(4) Canberra Argos-5AB Zeus S/N 1012-334

(5) Thermo Scientific Small Article Monitor 12 (SAM-12) S/N 12042

(6) Canberra Gem-5 S/N 1012-253

(7) Canberra GP100C2S Radiation Area Monitor R-34 S/N 13000080

(8) Mirion Fastscan S/N 13000021

(9) Fluke Biomedical Radiation Area Monitor R-9 S/N 3603001

(10) Victoreen Model 977-201 Radiation Area Monitor R-4 S/N 318

Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Containment Noble Gas Gaseous Effluent Monitor R-12

(2) Steam Generator Blowdown Liquid Effluent Monitor R-19

OTHER ACTIVITIES - BASELINE

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

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) For the period October 1, 2024 through September 30, 2025 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual

Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) For the period October 1, 2024 through September 30, 2025 71152A - Annual Follow-up Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed the licensees implementation of its corrective action program related to the long term action plan to address increased leakage out of 'B' safety injection back into emergency core cooling system piping and the effects on gas voids.

71152S - Semiannual Trend Problem Identification and Resolution

Semiannual Trend Review (IP Section 03.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential emerging or adverse trends that might be indicative of a more significant safety issue on December 9, 2025.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation:

Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion III, "Design Control," requires, in part, that design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design.

Contrary to the above, from October 15, 2024 to September 18, 2025, Constellation personnel changed the design of containment building shielding material without subjecting the change to design control measures commensurate with those applied to the original design and without approval by the organization that performed the original design. Specifically, on October 15, 2024, Constellation commenced reactor startup following a refueling outage without reinstalling the containment shield blocks normally located at the containment equipment hatch. The blocks were reinstalled on September 18, 2025, shortly after station personnel identified that the blocks were required as part of the facility design basis.

The blocks are relied upon in the facility design basis because they provide for radiation shielding assumptions used in the radiation dose calculations that were performed as part of the Control Room Envelope (CRE) Habitability Program, as required by Ginna Technical Specification 5.5.16. Specifically, the radiation shielding properties of the concrete blocks are relied upon in dose calculations that ensure adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent.

Significance/Severity: Green. The inspectors evaluated the significance of this issue in accordance with IMC 0609, Appendix A, "The Significance Determination Process for Findings At-Power," and determined that the issue was Green because Exhibit 3 question D.1 was answered YES. Specifically, the issue only represented a degradation of the radiological barrier function provided for the control room.

Corrective Action References: 04896959

Minor Performance Deficiency 71152A Gas Intrusion Management Program Monitored through Incorrect Procedures

Minor Performance Deficiency: In response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Constellation developed the gas intrusion management program to mitigate and analyze for voids in the emergency core cooling system. Constellation identified safety injection accumulator leakage in action request 04897753, B Safety Injection Accumulator TSI03B Increased Leakage, dated September 14, 2025. The inspectors subsequently conducted an inspection of the gas intrusion management program and identified two procedures that were performed with incorrect procedure steps, which constituted a performance deficiency.

On September 3, 2025, Constellation performed O-6.11, Attachment 22, SI and RHR System Void Inspections, revision 262. Step 1.6.2 directed the operator to analyze A safety injection accumulator for level change when B safety injection accumulator should have been required to be analyzed.

On October 13, 2024, Constellation performed O-1.1D, Plant Requirement Check List for Heatup Greater than 350F, revision 068. Step 6.5.8 directed the operator to ensure emergency core cooling system piping is sufficiently filled with water per EP-UT-104, Ultrasonic Examination to Determine Water/Liquid Level. EP-UT-104 was cancelled and superseded on January 19, 2016.

Screening:

The inspectors determined the performance deficiency was minor. The inspectors evaluated the performance deficiency in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and determined the issue was minor because, although Constellation executed procedures with errors, it did not represent a failure to meet the mitigating systems cornerstone objective to ensure availability, reliability, and capability of the system to respond to initiating events to prevent undesirable consequences. Specifically, O-6.11, attachment 22, step 1.6 was able to be completed through step 1.6.1, and 1.6.2 was a redundant step and therefore the intent of the procedure was satisfied.

Additionally, procedure ER-AA-335-007, Ultrasonic Inspection for Determination of Sedimentation in Piping Systems of Components and Fluid Level Measurements, superseded EP-UT-104 and, was performed satisfactorily, satisfying the intent of O-1.1D.

EXIT MEETINGS AND DEBRIEFS

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

• On December 4, 2025, the inspectors presented the radiation monitoring instrumentation inspection results to Richard Everett, Site Vice President, and other members of the licensee staff.

• On January 21, 2026, the inspectors presented the integrated inspection results to Richard Everett, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Work Orders

C20803058

Perform VT-3 Exam on Bolting for Valve 8664

C93909276

Repair Broken Reach Rod Assembly for Valve 650J

71111.05

Procedures

FRP-18.0

Battery Room B

Revision 008

71111.12

Corrective Action

Documents

04901741

VT-2 Inspections not Performed with WO 69387315

09/30/2025

Procedures

STP-O-36-COMP-

D

Standby Auxiliary Feedwater Pump D - Comprehensive Test

Revision 027

71111.15

Corrective Action

Documents

04896959

Untimely Restoration of E-Hatch Blocks into Normal

Configuration

09/11/2025

04897753

B SI Accumulator TS103B Increased Leakage

09/14/2025

04909676

BYCB Wouldn't Equalize when the Equalize Button was

Pushed

10/28/2025

71111.24

Corrective Action

Documents

04911406

Removed Pressurizer Safety Valve Spring Rate OOT

11/03/2025

71152A

Calculations

DA-ME-11-009

Gas Void Limits in RHR and SI Systems

DA-ME-12-004

SI Accumulator Off-Gassing Analysis

DA-ME-14-021

Gas Accumulation Technical Specification Surveillance

Requirements

Corrective Action

Documents

04897753

D SI Accumulator TSI03B Increased Leakage

09/14/2025

Corrective Action

Documents

Resulting from

Inspection

04912629

NRC-identified C2P

11/06/2025

04914714

NRC ID: C2P: O-1.1D

11/14/2025

Procedures

GIMP-PROGPLAN Gas Intrusion Management Program

Revision 8

O-6.11

Surveillance Requirements/Routine Operations Check Sheet

2