IR 05000352/2025011
| 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
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
Inspection Report
Docket Numbers:
05000352 and 05000353
License Numbers:
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
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.
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)===
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.
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
37060
Corrective Action
Documents
Issue Report
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
2/10/2023
LG-5069-004
Limerick Periodic Review and Model Update Impact on 10 CFR 50.69 Categorization
LG-5069-012-003
CFR 50.69 Categorization Document - Residual Heat
Removal Service Water System (012)
LG-5069-012-23-
PE-01
Periodic Review for 50.69 - RHRSW (012)
06/24/2019 -
06/13/2023
LG-5069-020-
081-092-003
CFR 50.69 Categorization Document -Diesel Generator
System (020, 081, 092)
LG-5069-020-
081-092-23-PE-
Periodic Review for 50.69 - EDG (020-081-092)
06/24/2019
05/18/2023
LG-5069-051-003
CFR 50.69 Categorization Document - Residual Heat
Removal System (051)
LG-5069-051-23-
IM-01
Immediate Review for 50.69: Residual Heat Removal
07/31/23
LG-5069-051-23-
PE-01
Periodic Review for 50.69 - RHR (051)
06/24/2019 -
06/12/2023
LG-5069-055-
056-003
CFR 50.69 Categorization Document - HPCI System
(055)
LG-5069-055-
056-23-PE-01
Periodic Review for 50.69 - HPCI (055)
11/5/2019 -
8/30/2023
LG-5069-059-003
CFR 50.69 Categorization Document - Primary
Containment Instrument Gas System (059)
LG-5069-059-23-
Periodic Review for 50.69 - PCIG (059)
04/09/2019 -
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PE-01
03/17/2023
CFR 50.69 SSC Categorization Guideline
Procedures
CFR 50.69 Risk Informed Categorization for Structures,
Systems, and Components
Requirements for Immediate and Periodic Performance
Monitoring Reviews
Work Orders
245856