IR 05000333/2025040
| ML25168A001 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/17/2025 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2025040 | |
| Download: ML25168A001 (1) | |
Text
June 17, 2025
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) - AGE-RELATED DEGRADATION INSPECTION REPORT 05000333/2025040
Dear David Rhoades:
On May 15, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. Fitzpatrick Nuclear Power Plant and discussed the results of this inspection with Garrick Olson, Plant General Manager, and other members of your staff.
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, Erin E. Carfang, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket No. 05000333 License No. DPR-59
Enclosure:
As stated
Inspection Report
Docket Number:
05000333
License Number:
Report Number:
Enterprise Identifier: I-2025-040-0000
Licensee:
Constellation Nuclear
Facility:
James A. Fitzpatrick Nuclear Power Plant
Location:
Oswego, NY
Inspection Dates:
April 28, 2025 to May 15, 2025
Inspectors:
P. Cataldo, Senior Reactor Inspector
A. Patel, Senior Reactor Inspector
G. Stock, Reactor Operations Engineer
Approved By:
Erin E. Carfang, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.
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 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
71111.21N.04 - Age-Related Degradation Age-Related Degradation
The inspectors selected a sample of components and structures to verify that engineering performance and maintenance activities addressed age-related degradation and that problems were appropriately identified, addressed, and corrected.
Samples were selected considering risk insights and the potential for degradation.
Specifically, the inspectors selected samples that were risk-significant and either had indications of age-related degradation or were exposed to environments that could cause age-related degradation. The inspectors considered site-specific and industry-wide operating experience to identify samples and included both active and passive sub-components within each component or structure.
For each selected sample listed below, the inspectors reviewed the licensees engineering and maintenance activities credited to address age-related degradation to assess whether they were being performed using applicable standards and procedures, evaluated against appropriate acceptance criteria, and that maintenance and condition monitoring was completed at an appropriate interval. The inspectors also assessed whether issues identified during licensee activities were being entered into and addressed by the applicable station processes including the corrective action program, and whether periodic assessments of maintenance effectiveness and operating experience were being completed, including feedback and process adjustments.
- (1) Emergency diesel generator fuel oil storage tank 93TK-6A
- (2) Condensate drain cooler 33DC-7A
- (3) Fire protection piping
- (4) Reactor core isolation cooling pump 13P-1
- (5) Low pressure coolant injection pump power supplies (6)
'C' Residual heat removal pump motor and cables
- (7) Low pressure coolant injection valves (10MOV-25A&B) and associated logic relays (8)
'B' Residual heat removal pump and motor (10P-3B)
(9)
'D' Emergency diesel generator 93EDG-D (10)
'B' Core spray pump 14P-1B
- (11) Automatic depressurization system valve 02RV-5 (RV-71E)
(12)
'A' Residual heat removal service water pump 10P-1A
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 15, 2025, the inspectors presented the design basis assurance inspection (programs) results to Garrick Olson, Plant General Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.04 Corrective Action
Documents
J1R26 FAC/EPC Non-Compliance
09/16/2024
Corrective Action
Documents
Resulting from
Inspection
Oil level below standstill line
ARDI walkdown inspection identified issues
Fire door 76FDR-DG-272-3 bracket loose
Fire door 76FDR-DG-272-3 bracket loose
93TK-6A remaining service life evaluation needed
Crack in reactor building east crescent
ARDI generate WO to paint 4-WF-151-133
Structures monitoring report lacking detail
Model WO for cable testing not comprehensive
ST-76KA performance
Drawings
Elementary Diagram 600V CKTS-MOV RHR Inboard VVs
Manhole and Duct Line Detail
Engineering
Changes
76-4-WF-151-133 Minimum Wall Thickness Evaluation
000
Install Enhanced Safety Motor Guards to Fully Enclose
Rotating Equipment on Several SR Components
Emergency Diesel Generator A, B, C, D Circulating Lube
Oil Pump Mount Reconfiguration
001
93TK-6A Bulge Tech Eval (Ref. IR 04772624)
000
Miscellaneous
Constellation Preventative Maintenance Control Relay
Template
Procedures
Equipment Classification
Core Spray Pump Low Pressure and Low Flow Bypass
Valve Instrument Calibration
007
PMID 00344088
PM - Calibrate EDG Relay Tachometer Loop
ADS Logic System Functional Test
Integrity Inspection of FP CO2 System and SGT Filter
Tran B FP System
09/14/2023
Work Orders
05116995-01
PM - Perform Eddy Current Inspection on 33DC-7A
09/08/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
05417087
LR - Review Service Water Piping per ER-AA-5400