ML25265A055

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Susquehanna Steam Electric Station, Units 1 and 2 - Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000387/2025010 and 05000388/2025010
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 Brad Berryman Senior Vice President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603

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 cc w/ encl: Distribution via LISTSERV ERIN CARFANG Digitally signed by ERIN CARFANG Date: 2025.09.22 12:20:02 -04'00'

ML25265A055 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS NAME APatel ECarfang DATE 9/22/2025 9/22/2025

Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:

05000387 and 05000388 License Numbers:

NPF-14 and NPF-22 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

2

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.

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 71111.21M - 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) (5 Samples)

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.

4

  • 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.

5

  • 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.

6 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

7 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.

8 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.21M Calculations CALC EC-002-0506 125 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

9 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 WO 2333456 24 Month Chan A 1D610-125 VDC Battery Discharge Test and Battery Charger Capability Test SM-102-A03 04/04/2024