ML25113A082
| ML25113A082 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/23/2025 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2025011 | |
| Download: ML25113A082 (1) | |
Text
April 23, 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:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - TITLE 10 OF THE CODE OF FEDERAL REGULATIONS 50.69 RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS INSPECTION REPORT 05000352/2025011 AND 05000353/2025011
Dear David Rhoades:
On March 27, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Limerick Generating Station, Units 1 and 2 and discussed the results of this inspection with Michael Gillin, 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, Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket Nos. 05000352 and 05000353 License Nos. NPF-39 and NPF-85
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV GLENN DENTEL Digitally signed by GLENN DENTEL Date: 2025.04.23 14:44:55 -04'00'
ML25113A082 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS NAME LCline GDentel DATE 4/23/2025 4/21/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000352 and 05000353 License Numbers:
NPF-39 and NPF-85 Report Numbers:
05000352/2025011 and 05000353/2025011 Enterprise Identifier: I-2025-011-0014 Licensee:
Constellation Energy Generation, LLC Facility:
Limerick Generating Station, Units 1 and 2 Location:
Sanatoga, PA 19464 Inspection Dates:
March 24, 2025 to March 27, 2025 Inspectors:
C. Bickett, Senior Reactor Analyst L. Cline, Senior Resident Inspector Approved By:
Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Title 10 of the Code of Federal Regulations (10 CFR) 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components inspection at Limerick Generating Station, Units 1 and 2, 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.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 37060 - 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components (SSCs) Inspection The inspectors reviewed the licensees program and implementation of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, in accordance with the following procedure sections:
Problem Identification and Resolution (IP Section 02.03)
For the five systems listed in Section 02.04 below, the inspectors reviewed the licensees problem identification and resolution system to verify that conditions that would prevent Risk-Informed Safety Class (RISC)-3 SSCs from performing their safety-related function have been corrected and that, as applicable, the licensee performed common cause reviews of RISC-3 SSC deficiencies such that risks are identified and assessed prior to events that could invalidate the licensees SSC categorization process. The inspectors also reviewed the licensees self-assessments performed on the implementation of the 10 CFR 50.69 program.
Review of Licensees Feedback and Process Adjustments (IP Section 02.04) (5 Samples)
The inspectors completed a review of the following five categorized systems to verify that the licensee had implemented the requirements for feedback and process adjustment in accordance with procedures and 10 CFR 50.69(e).
(1)
Unit 1 and 2 Residual Heat Removal System (2)
Unit 1 and 2 Residual Heat Removal Service Water System (3)
Unit 1 and 2 High Pressure Coolant Injection System (4)
Unit 1 and 2 Diesel Generator System (5)
Unit 1 and 2 Primary Containment Instrument Gas System INSPECTION RESULTS No findings were identified.
4 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On March 27, 2025, the inspectors presented the 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components inspection results to Michael Gillin, Site Vice President, and other members of the licensee staff.
5 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 37060 Corrective Action Documents Issue Report IR 04724220 Corrective Action Documents Resulting from Inspection Issue Reports IR 04849130 IR 04849134 IR 04849135 IR 04849173 IR 04849202 IR 04849340 Miscellaneous 05089476 Material Request for 051-2F067B Replace Gear Box and Associated Linkage 02/10/2023 LG-5069-004 Limerick Periodic Review and Model Update Impact on 10 CFR 50.69 Categorization 2
LG-5069-012-003 10 CFR 50.69 Categorization Document - Residual Heat Removal Service Water System (012) 2 LG-5069-012 PE-01 Periodic Review for 50.69 - RHRSW (012) 06/24/2019 -
06/13/2023 LG-5069-020-081-092-003 10 CFR 50.69 Categorization Document -Diesel Generator System (020, 081, 092) 3 LG-5069-020-081-092-23-PE-01 Periodic Review for 50.69 - EDG (020-081-092) 06/24/2019 05/18/2023 LG-5069-051-003 10 CFR 50.69 Categorization Document - Residual Heat Removal System (051) 6 LG-5069-051 IM-01 Immediate Review for 50.69: Residual Heat Removal 07/31/23 LG-5069-051 PE-01 Periodic Review for 50.69 - RHR (051) 06/24/2019 -
06/12/2023 LG-5069-055-056-003 10 CFR 50.69 Categorization Document - HPCI System (055) 3 LG-5069-055-056-23-PE-01 Periodic Review for 50.69 - HPCI (055) 11/5/2019 -
8/30/2023 LG-5069-059-003 10 CFR 50.69 Categorization Document - Primary Containment Instrument Gas System (059) 3 LG-5069-059 Periodic Review for 50.69 - PCIG (059) 04/09/2019 -
6 Inspection Procedure Type Designation Description or Title Revision or Date PE-01 03/17/2023 NEI 00-04 10 CFR 50.69 SSC Categorization Guideline 0
Procedures ER-AA-569-1003 10 CFR 50.69 Risk Informed Categorization for Structures, Systems, and Components 9
ER-AA-569-1006 Requirements for Immediate and Periodic Performance Monitoring Reviews 7
Work Orders 05245856