IR 05000352/2023010
| ML24011A010 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/11/2024 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2023010 | |
| Download: ML24011A010 (1) | |
Text
January 11, 2024
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - AGE-RELATED DEGRADATION REPORT 05000352/2023010 AND 05000353/2023010
Dear David Rhoades:
On November 30, 2023, 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, Mel Gray, Chief Engineering Branch 1 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:
05000352/2023010 and 05000353/2023010
Enterprise Identifier: I-2023-010-0024
Licensee:
Constellation Energy Generation, LLC
Facility:
Limerick Generating Station, Units 1 and 2
Location:
Limerick, PA
Inspection Dates:
November 13, 2023 to November 30, 2023
Inspectors:
J. Kulp, Senior Reactor Inspector
K. Mangan, Senior Reactor Inspector
A. Turilin, Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an Age-Related Degradation at Limerick Generating Station, 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 Focused Engineering Inspection (Section 03.01)
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) High Pressure Coolant Injection (HPCI) Pump Lube Oil Cooler Cooling Water Regulating Valve (F035)
- (2) HPCI System Cannon Plug Inspection and Repairs
- (3) Reactor Core Isolation Cooling (RCIC) System Cannon Plug Inspection Repairs
- (4) Spray Pond Pump House Heating Ventilation and Air Conditioning Fans and Motors
- (5) Spray Pond Pump House Heating Ventilation and Air Conditioning Damper and Damper Motors
- (7) Emergency Diesel Generator Lube Oil Hose Commercial Grade Replacement Testing
- (8) Emergency Diesel Generator Service Water Expansion Joint Period Replacement Frequency
- (9) Emergency Diesel Generator Output Breaker Undervoltage Relay Calibration
- (10) Inspection of Fire and Flooding Doors Important to Emergency Operating Procedures
- (11) Emergency Core Cooling System Room Cooler Control Systems
- (12) Emergency Diesel Generator Oil System Pipe Nipple Replacement due to Vibration Induced Fatigue
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 30, 2023, the inspectors presented the Age-Related Degradation 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
71111.21N.04 Corrective Action
Documents
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
E-471
Schematic Diagram RCIC, HPCI, RHR and Core Spray
Unit Coolers -1 and 2 Units
Revision 17
Engineering
Changes
Pressure Indicator PI-GA-202D Instrument Line Repair
Revision 0
Engineering
Evaluations
MPL # E41-C002
Environmental Qualification Report for HPCI Steam
Turbine Assembly
dated
10/13/1983
PMC-04
Reclassify Motor and Deactivate PM for Motor Electrical
Test MA-MA-7171-009
dated
10/24/2008
PMC-18-115429
VBM SOE Phase 2 System 81 (2.1/NDD) Noncritical PM
Reevaluation
dated
2/14/2019
Miscellaneous
LIM-15864
Failure Analysis of Cannon Plug Manufacturer: Cannon
Model: 262A6523G001
dated
11/30/22
Procedures
1037567
SFCP-4KV EDG Undervoltage Relays
Revision 0a
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Div I RHR (LPCI) LSF/SAA-Non-Outage
Revision 12
4KV Emergency D13 Undervoltage Channel/Functional
Test
Revision 28
Work Orders
242163
242164
22782
4854329
4974173
5086082
5087771
5130685
5141409
5146098
5172995
5301803
28600
5359683
5361369
M1769719
M1769719
M2029369
R1101661
R1101663
R1140030
R1174656