ML25168A001
| 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 David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
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 cc w/ encl: Distribution via LISTSERV ERIN CARFANG Digitally signed by ERIN CARFANG Date: 2025.06.17 13:45:05 -04'00'
ML25168A001 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS NAME PCataldo ECarfang DATE 6/17/2025 6/16/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000333 License Number:
DPR-59 Report Number:
05000333/2025040 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
2
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.
3 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 (12 Samples)
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
4 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.
5 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.21N.04 Corrective Action Documents AR 04802093 J1R26 FAC/EPC Non-Compliance 09/16/2024 Corrective Action Documents Resulting from Inspection IR 4861447 Oil level below standstill line IR 4861509 ARDI walkdown inspection identified issues IR 4861529 Fire door 76FDR-DG-272-3 bracket loose IR 4861529 Fire door 76FDR-DG-272-3 bracket loose 1
IR 4861541 93TK-6A remaining service life evaluation needed IR 4864389 Crack in reactor building east crescent IR 4865806 ARDI generate WO to paint 4-WF-151-133 IR 4865807 Structures monitoring report lacking detail IR 4865828 Model WO for cable testing not comprehensive IR 4866029 ST-76KA performance Drawings ESK-6MP Elementary Diagram 600V CKTS-MOV RHR Inboard VVs 10MOV-25A&B 23 FE-32C Manhole and Duct Line Detail 16 Engineering Changes EC 633292 76-4-WF-151-133 Minimum Wall Thickness Evaluation 000 EC 635673 Install Enhanced Safety Motor Guards to Fully Enclose Rotating Equipment on Several SR Components 0
EC 638245 Emergency Diesel Generator A, B, C, D Circulating Lube Oil Pump Mount Reconfiguration 001 EC 641494 93TK-6A Bulge Tech Eval (Ref. IR 04772624) 000 Miscellaneous Constellation Preventative Maintenance Control Relay Template Procedures ER-AA-200-1001 Equipment Classification 8
ISP-8-2B Core Spray Pump Low Pressure and Low Flow Bypass Valve Instrument Calibration 007 PMID 00344088 PM - Calibrate EDG Relay Tachometer Loop 1
ST-22C ADS Logic System Functional Test 50 ST-76KB 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
6 Inspection Procedure Type Designation Description or Title Revision or Date 05417087 LR - Review Service Water Piping per ER-AA-5400