IR 05000333/2025004

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Integrated Inspection Report 05000333/2025004
ML26033A003
Person / Time
Site: FitzPatrick 
Issue date: 02/02/2026
From: Jason Schussler
Division of Operating Reactors
To: Mudrick C
Constellation Energy Generation, Constellation Nuclear
References
IR 2025004
Download: ML26033A003 (0)


Text

February 2, 2026

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2025004

Dear Christopher Mudrick:

On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant. On January 22, 2026, the NRC inspectors discussed the results of this inspection with Alex Sterio, 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, Jason E. Schussler, Chief Projects Branch 1 Division of Operating Reactor Safety

Docket No. 05000333 License No. DPR-59

Enclosure:

As stated

Inspection Report

Docket Number:

05000333

License Number:

DPR-59

Report Number:

05000333/2025004

Enterprise Identifier: I-2025-004-0043

Licensee:

Constellation Energy Generation, LLC

Facility:

James A. FitzPatrick Nuclear Power Plant

Location:

Oswego, NY

Inspection Dates:

October 1, 2025 to December 31, 2025

Inspectors:

G. Stock, Senior Resident Inspector

V. Fisher, Resident Inspector

H. Anagnostopoulos, Senior Health Physicist

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 James A. FitzPatrick 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.

List of Findings and Violations

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

Additional Tracking Items

None.

PLANT STATUS

FitzPatrick began the inspection period operating at rated thermal power. On November 7, 2025, operators reduced reactor power to 74 percent to perform turbine valve testing and a control rod pattern adjustment. Operators raised reactor power to rated thermal power the next day. FitzPatrick remained at, or near, rated thermal power for the remainder 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

71111.11Q - 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 operations personnel during a down power to 74 percent for a rod pattern adjustment and turbine valve testing on November 7, 2025.

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

(1) The inspectors observed a simulator evaluation that included the loss of both reactor water recirculation pumps, an anticipated transient without scram, and manual injection of standby liquid control on October 21, 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 functions:

(1) Containment hydrogen/oxygen analyzers on October 2, 2025 (2)67UC-16B, east electric bay unit cooler system, on October 8, 2025
(3) Reactor protection system on November 21, 2025

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)

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

(1)

'B' emergency service water pump following foreign material found in basket strainer on October 2, 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) Permanent Modification: Ten-ton carbon dioxide fire suppression testing modification on October 9, 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) (1 Sample)

(1) 'A' residual heat removal system following planned maintenance on October 23, 2025

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) ST-4N, High Pressure Coolant Injection Quick-Start, Inservice, and Transient Monitoring Test, on October 2, 2025
(2) ST-8Q, Testing of the Emergency Service Water System, on November 14,

2025 RADIATION SAFETY

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, and

Transportation

Radioactive Material Storage (IP Section 03.01) (1 Sample)

The inspectors evaluated the licensees performance in controlling, labeling, and securing the following radioactive materials:

(1) Outdoor radioactive material storage area 272', outside of the radioactive waste facility

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) Chemical decontamination bunker 272', torus desludging equipment

Waste Characterization and Classification (IP Section 03.03) (2 Samples)

The inspectors evaluated the following characterization and classification of radioactive waste:

(1) Shipment [[::JAF-2025-1971|JAF-2025-1971]], UN3321 LSA-II, activated carbon filter media
(2) Shipment [[::JAF-2025-1976|JAF-2025-1976]], UN3321 LSA-II, bead resins for disposal

Shipping Records (IP Section 03.05) (3 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) Shipment [[::JAF-2024-023|JAF-2024-023]], UN2911 Instruments, intermediate range monitor and source range monitor to Limerick Clean Energy Center
(2) Shipment [[::JAF-2024-1923|JAF-2024-1923]], UN3321 LSA-II, water to Energy Solutions for processing
(3) Shipment [[::JAF-2025-1976|JAF-2025-1976]], UN3321 LSA-II, bead resins for disposal.

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 to September 30, 2025

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) For the period October 1, 2024 to September 30, 2025

71152S - Semiannual Trend Problem Identification and Resolution

Semiannual Trend Review (Section 03.02) (1 Sample)

(1) The inspectors reviewed the FitzPatrick corrective action program to identify potential trends that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Observation: Semiannual Trend Review 71152S The inspectors evaluated a sample of issues and events that occurred over the third and fourth quarters of 2025 to determine whether issues were appropriately considered as emerging or adverse trends. The inspectors verified issues were appropriately evaluated by Constellation staff for potential trends and addressed within the scope of the corrective action program or through department review. The inspectors did not identify any new trends that could indicate a more significant safety issue. The inspectors determined that Constellation personnel identified trend issues at a low threshold and entered them into the corrective action program for resolution.

The inspectors noted licensee-identified trends in rework evaluation efficiency and engineering technical human performance issues. The inspectors independently evaluated these trends for significance in accordance with the guidance in IMC 0612, Appendix B, "Issue Screening," and Appendix E, "Examples of Minor Issues." The inspectors determined that none of the conditions were deficiencies of greater than minor significance and, therefore, are not subject to enforcement action in accordance with the NRC's Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

  • On January 22, 2026, the inspectors presented the integrated inspection results to Alex Sterio, Site Vice President, and other members of the licensee staff.
  • On December 15, 2025, the inspectors presented the radiation safety inspection results to Garrick Olson, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.11Q Corrective Action

Documents

04913048

Procedures

ST-1E

Main Turbine Stop Valve Limit Switch Instrument Functional

Test

28

ST-1L

Main Turbine Control Valve Instrument Channel and Valve

Operability Check

043

71111.12

Corrective Action

Documents

04824953

04824975

04825048

04863237

04896570

04913048

Engineering

Changes

645531

Procedures

ISP-30-3

Containment Hydrogen/Oxygen Analyzer B Calibration

OP-27

Containment Atmosphere Dilution System

Work Orders

04862365

05571580

05662194

2468475

71111.15

Corrective Action

Documents

04881580

Engineering

Changes

645030

Work Orders

05561579

71111.18

Corrective Action

Documents

04357131

04403462

04555277

04843240

Drawings

FB-56A

Flow Diagram CO2 and Foam Fire Extinguishing System

Engineering

2992

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Changes

71111.24

Procedures

ST-2A

RHR [Residual Heat Removal] Loop A Quarterly Operability

Test (IST)

051

ST-2XA

RHR Service Water Loop A Quarterly Operability Test (IST)

20

ST-4N

HPCI [High Pressure Coolant Injection] Quick-Start,

Inservice, and Transient Monitoring Test (IST)

Work Orders

05552919

05684992