IR 05000387/2025010
| ML25265A055 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/22/2025 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Berryman B Susquehanna |
| References | |
| IR 2025010 | |
| Download: ML25265A055 (1) | |
Text
September 22, 2025
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
COMPREHENSIVE ENGINEERING TEAM INSPECTION (CETI) INSPECTION REPORT 05000387/2025010 AND 05000388/2025010
Dear Brad Berryman:
On September 11, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2, and discussed the results of this inspection with Mark Jones, Plant Manager, 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, Erin E. Carfang, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket Nos. 05000387 and 05000388 License Nos. NPF-14 and NPF-22
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000387 and 05000388
License Numbers:
Report Numbers:
05000387/2025010 and 05000388/2025010
Enterprise Identifier: I-2025-010-0024
Licensee:
Susquehanna Nuclear, LLC
Facility:
Susquehanna Steam Electric Station, Units 1 and 2
Location:
769 Salem Blvd., Berwick, PA
Inspection Dates:
August 25, 2025 to September 11, 2025
Inspectors:
A. Patel, Team Leader
P. Boguszewski, Senior Resident Inspector
J. Kulp, Senior Reactor Inspector
E. Miller, Senior Reactor Inspector
A. Turilin, Reactor Inspector
J. Cunningham, Reactor Inspector
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 comprehensive engineering team inspection at Susquehanna Steam Electric 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.
REACTOR SAFETY
===71111.21M - Comprehensive Engineering Team Inspection
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Structures, Systems, and Components (SSCs) (IP section 03.01)===
For each component sample listed below, the team reviewed licensing and design basis documents and a sampling of applicable operator actions, periodic testing results, corrective action program documents, internal and external operating experience, preventive and corrective maintenance work orders, modifications, and aging management programs.
Additionally, the team performed walkdowns of accessible components and conducted interviews with licensee personnel.
The team used the attributes contained in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below as guidance. Specifically, the team evaluated these attributes in the course of applying IP 71111.21M, Appendix B, Component Design Review Considerations and IP 71111.21M, Appendix C, Component Walkdown Considerations.
- (1) Emergency Diesel Generator A (0G501A)
- Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
- Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
- Component controls will be functional and provide desired control during accident/event conditions.
- Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
- Instrumentation and alarms are available to operators for making necessary decisions.
- Installed configuration will support its design basis function under accident/event conditions.
- Component operation and alignments are consistent with design and licensing basis assumptions.
- Design bases and design assumptions have been appropriately translated into design calculations and procedures.
- Performance capability of selected components have not been degraded through modifications.
- Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
- Tests and/or analyses validate component operation under accident/event conditions.
- Potential degradation is monitored or prevented.
- Equipment is adequately protected from environmental hazards.
The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.
- (2) Reactor Core Isolation Cooling Pump (1P203)
- Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
- Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
- Component controls will be functional and provide desired control during accident/event conditions.
- Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
- Instrumentation and alarms are available to operators for making necessary decisions.
- Installed configuration will support its design basis function under accident/event conditions.
- Component operation and alignments are consistent with design and licensing basis assumptions.
- Design bases and design assumptions have been appropriately translated into design calculations and procedures.
- Performance capability of selected components have not been degraded through modifications.
- Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
- Tests and/or analyses validate component operation under accident/event conditions.
- Potential degradation is monitored or prevented.
- Equipment is adequately protected from environmental hazards.
The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.
- (3) Reactor Core Isolation Cooling Injection Valve (HV2491F013)
- Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
- Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
- Component controls will be functional and provide desired control during accident/event conditions.
- Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
- Instrumentation and alarms are available to operators for making necessary decisions.
- Installed configuration will support its design basis function under accident/event conditions.
- Component operation and alignments are consistent with design and licensing basis assumptions.
- Design bases and design assumptions have been appropriately translated into design calculations and procedures.
- Performance capability of selected components have not been degraded through modifications.
- Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
- Tests and/or analyses validate component operation under accident/event conditions.
- Potential degradation is monitored or prevented.
- Equipment is adequately protected from environmental hazards.
The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.
(4)4.16 kV Engineered Safeguard System Auxiliary Bus 1B (1A202)
- Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
- Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
- Component controls will be functional and provide desired control during accident/event conditions.
- Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
- Instrumentation and alarms are available to operators for making necessary decisions.
- Installed configuration will support its design basis function under accident/event conditions.
- Component operation and alignments are consistent with design and licensing basis assumptions.
- Design bases and design assumptions have been appropriately translated into design calculations and procedures.
- Performance capability of selected components have not been degraded through modifications.
- Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
- Tests and/or analyses validate component operation under accident/event conditions.
- Potential degradation is monitored or prevented.
- Equipment is adequately protected from environmental hazards.
The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electrical Loads, and As-Built System.
- (5) Engineered Safeguard System Channel A 125V DC Bus (1D612)
- Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
- Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
- Component controls will be functional and provide desired control during accident/event conditions.
- Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
- Instrumentation and alarms are available to operators for making necessary decisions.
- Installed configuration will support its design basis function under accident/event conditions.
- Component operation and alignments are consistent with design and licensing basis assumptions.
- Design bases and design assumptions have been appropriately translated into design calculations and procedures.
- Performance capability of selected components have not been degraded through modifications.
- Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
- Tests and/or analyses validate component operation under accident/event conditions.
- Potential degradation is monitored or prevented.
- Equipment is adequately protected from environmental hazards.
The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electrical Loads, and As-Built System.
Modifications (IP section 03.02) (2 Samples)
- (1) DCP 1863105, Replace Automatic Transfer Switches 1ATS219, Engineered Safeguard System 480V Motor Control Center
- (2) EC-006-1081, Thermal Overloads for 89-10 MOVs that are Jogged/Throttled
10 CFR 50.59 Evaluations/Screening (IP section 03.03) (7 Samples)
- (1) SD 02643, Revise OP-152-001, Functional Test of High Pressure Coolant Injection Lube Oil System
- (2) SD 02684, Update Residual Heat Removal Pressure Safety Valve Capacities
- (3) SD 02732, Unit 1 Cycle 24 Core Operating Limits Report Revision
- (4) SE 00034, Commercial Load Center Unit 2 500kV Relay and Protection Upgrades and Tie-In
- (5) SE 00035, Decrease in Turbine Valve Testing (Stride 2023-004)
- (6) SE 00037, Turbine Valve Inspection Frequency Change
- (7) SE 00038, Unit Startup with Auxiliary Boilers Unavailable
Operating Experience Samples (IP section 03.04) (1 Sample)
- (1) Information Notice 19-02, Emergency Diesel Generator Excitation System Diode Failures
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On September 11, 2025, the inspectors presented the comprehensive engineering team inspection (CETI) inspection results to Mark Jones, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
CALC EC-002-
0506
25 VDC System 1D610 Master Battery Calculation
Revision 47
EC-023-0508
A-D Diesel-Generator Fuel oil Storage Tank (FOST)
Capacity
Revision 1
EC-023-1012
Evaluate Impact of Use of Biodiesel (85) and Ultra-Low
Sulfur Diesel (ULSD) Fuel on the Diesel Generator Fuel Oil
Storage and Transfer System
Revision 3
EC-024-0503
Diesel Generator Load Calculation
Revision 39
EC-050-0549
Maximum RCIC Pump Discharge Pressure
Revision 1
EC-052-1055
CST Water Level for HPCI Suction Transfer
Revision 1
EC-VALV-0505
Scope of DC Powered Motor Operated Valves Requiring
Stroke Time Evaluations at Degraded Voltages
Revision 1
EC-VALV-1072
Actuator Sizing and Diagnostic Test Acceptance Criteria for
GL 89-10 / Appendix III Rising Stem MOVs (DC)
Revision 42
Corrective Action
Documents
CR-2022-10192
Corrective Action
Documents
Resulting from
Inspection
CR-2025-13452
CR-2025-13454
CR-2025-13456
CR-2025-13457
CR-2025-13525
CR-2025-13716
CR-2025-13788
CR-2025-13950
CR-2025-14019
CR-2025-14023
CR-2025-14035
CR-2025-14095
CR-2025-14097
CR-2025-14125
Drawings
M-155
Unit 1 P&ID, High Pressure Coolant Injection
Revision 60
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
EC-004-1031
Plant AC Loadflow Analysis
Revision 8
EC-006-1081
Thermal Overloads for 89-10 MOVs that are
Jogged/Throttled
Revision 0
Miscellaneous
DBD006
Design Basis Document for Class 1E AC Electrical
Revision 5
DI-2019-07966
Evaluation for NRC Inspection Notice 2019-02
06/11/2019
E8385-01
Replacement DG A Voltage Regulator Bridge Rectifier
Diodes
08/07/2019
EDU-DIO-0008
Dedication Document for General Purpose Silicon Standard
Recovery Diodes
Revision 5
SD 02377
Replace Automatic Transfer Switches 1ATS219, 1ATS229,
2ATS219, & 2ATS229
Revision 0
SE 00034
Commercial Load Center Unit 2 Phase II 500 kV Tie-in
Revision 0
Procedures
SM-104-002
4KV Bus 1A202 2 year undervoltage channel calibration
Revision 18
SO-150-004
Quarterly RCIC Valve Exercising
04/30/2025
SO-150-006
RCIC Comprehensive Flow Verification
01/30/2025
Work Orders
Month Chan A 1D610-125 VDC Battery Discharge Test
and Battery Charger Capability Test SM-102-A03
04/04/2024