ML25217A109
| ML25217A109 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/05/2025 |
| From: | Sherlyn Haney Division of Operating Reactors |
| To: | Berryman B Susquehanna |
| References | |
| IR 2025002 | |
| Download: ML25217A109 (1) | |
Text
August 5, 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 -
INTEGRATED INSPECTION REPORT 05000387/2025002 AND 05000388/2025002
Dear Brad Berryman:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On July 28, 2025, the NRC inspectors discussed the results of this inspection with Edward Casulli, 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, Sherlyn Haney, Acting Chief Projects 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 SHERLYN HANEY Digitally signed by SHERLYN HANEY Date: 2025.08.05 10:25:33 -04'00'
ML25217A109 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS RI/DORS NAME DAntonangeli DBeacon SHaney DATE 8/4/2025 8/4/2025 8/5/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000387 and 05000388 License Numbers:
NPF-14 and NPF-22 Report Numbers:
05000387/2025002 and 05000388/2025002 Enterprise Identifier: I-2025-002-0042 Licensee:
Susquehanna Nuclear, LLC Facility:
Susquehanna Steam Electric Station, Units 1 and 2 Location:
769 Salem Blvd., Berwick, PA Inspection Dates:
April 1, 2025 to June 30, 2025 Inspectors:
D. Antonangeli, Senior Resident Inspector J. England, Senior Resident Inspector E. Brady, Resident Inspector D. Beacon, Senior Project Engineer N. Mentzer, Senior Project Engineer E. Miller, Senior Reactor Inspector R. Rolph, Senior Health Physicist J. Tifft, Senior Reactor Inspector Approved By:
Sherlyn Haney, Acting Chief Projects Branch 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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 PLANT STATUS Unit 1 began the inspection period at rated thermal power. On June 6, 2025, the unit down powered to 75 percent for a control rod sequence exchange and returned to rated thermal power on June 7, 2025. The unit remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period shut down for the refueling outage U222RIO. On June 2, 2025, the unit was started up and achieved rated thermal power on June 3, 2025. On June 16, 2025, the unit down powered to 63 percent for a control rod pattern adjustment and returned to rated thermal power on June 18, 2025. The unit remained at or near rated thermal power for the remainder of the inspection period.
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 2515, Light-Water Reactor Inspection Program -
Operations Phase. The inspectors performed activities described in Inspection Manual Chapter 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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 71111.04 - Equipment Alignment Partial Walkdown (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Unit 2, major components in the drywell for standby liquid control, containment instrument gas, core spray, and residual heat removal on April 16, 2025 (2)
Unit Common, standby gas treatment on May 13, 2025 (3)
Unit 2, reactor building chiller following maintenance on May 22, 2025 Complete Walkdown (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the
'A' emergency diesel generator support systems on June 12, 2025.
4 71111.05 - Fire Protection Fire Area Walkdown and Inspection (IP Section 03.01) (7 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Unit 2, turbine building, 656' and 729' elevations, fire areas 0-31H, 2-31B, 2-31L, and 2-35B, on April 2, 2025 (2)
Unit Common, refueling floor, 818' elevation, fire area 0-8A, on April 7, 2025 (3)
Unit 2, drywell, 704' to 779' elevations, fire area 2-4F, on April 14, 2025 (4)
Unit 2, reactor building, 719' and 683' elevations, fires areas 2-3A, 2-3B-N, 2-3B-S, 2-4A-N, and 2-4A-S, on April 17, 2025 (5)
Unit Common, control structure, 676', 754', and 771' elevations, fire areas 0-27A, 0-27B, 0-27C, 0-27E, 0-28A-I, 0-28A-II, 0-28B-I, 0-28B-II, 0-28C, 0-28D, 0-28E, 0-28-F, 0-28G, 0-28H, 0-28-I, 0-28J, 0-28K, 0-28L, 0-28M, 0-28N, and 0-28T, on May 29, 2025 (6)
Unit Common, control structure, 698' elevation, fire areas 0-24A, 0-24B, 0-24C, 0-24D, 0-24E, and 0-24G, on June 10, 2025 (7)
Unit 2, reactor building, 719' elevation, fire areas 2-4C and 2-4D, on June 23, 2025 Fire Brigade Drill Performance (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the on-site fire brigade performance during their response to a fire in the 'B' condenser on April 21, 2025.
71111.08G - Inservice Inspection Activities Boiling-Water Reactor (BWR)
BWR Inservice Inspection Activities - Nondestructive Examination (NDE) and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors evaluated BWR NDE testing by reviewing the following examinations from March 31 to April 3, 2025:
(1)
Liquid penetrant surface examination of reactor recirculation piping welded attachments RWS200-HW-10AA through -10AD (NDE Report PT-25-001 through PT-25-004)
American Society of Mechanical Engineers (ASME),Section XI, Article IWE, general visual examination of drywell liner on 704', 719' and 738' elevations (CISI-VT-25-007)
ASME,Section XI, Article IWL, general visual examination of containment concrete on 670', 683', 704' and 719' elevations (CISI-VT-25-093, -094, -067, and -071)
Ultrasonic testing volumetric examinations of a sample of core shroud welds in quadrant 'A' and 'D' (work order 26787633-0)
5 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 start up on June 2, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated just-in-time training for an ASME Class 1 boundary leakage test on April 14, 2025.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
(1)
Unit 2, residual heat removal pump 2B breaker replacement on May 28, 2025 (2)
Unit Common, 'A' emergency diesel generator lube oil pressure switches replacements on June 30, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)
Unit 2, elevated risk during common residual heat removal work window during the week of April 14, 2025 (2)
Unit Common, during 'B' control structure chiller work the week of May 12, 2025 (3)
Unit Common, elevated risk during emergency service water division 1 maintenance on June 26, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
Unit 2, emergency safety system transfer bus supply breaker, 2A20301, did not close during restoration after annual loss-of-coolant accident/loss of off-site power test on March 28, 2025 (2)
Unit 2, 'B' and 'D' main steam isolation valves failed local leak rate testing on April 4, 2025
6 (3)
Unit 2, control rod blade 46-07 identified as coupled during blade exchange activities on April 9, 2025 (4)
Unit 2, seismic monitor functional test failure on April 9, 2025 (5)
Unit 2, division 2 'A' and 'B' 250-volt battery charger not sharing charging loads on June 18, 2025 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Unit 2, engineering change 2803696 for residual heat removal shutdown cooling isolation valve, HV251F009, permanent actuator motor replacement following failure on April 13, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated Unit 2 refueling outage 22RIO activities from April 1 to June 3, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
(1)
Unit 2, SM-283-004, Main Steam Isolation Valve Fail Safe Testing, following main steam isolation valve spring replacement on April 8, 2025 (2)
Unit 2, SO-200-023, ASME Class I Boundary Leak Test, following reactor vessel disassembly and reassembly on April 20, 2025 (3)
Unit 1, SO-170-011, Secondary Containment Drawdown and In-Leakage Surveillance Test Zones I and III, on April 22, 2025 (4)
Unit Common, SI-024-301, 5-Year Calibration of 'A' Diesel Generator Lube Oil Low Pressure Switches, PSL-03481A1, A2, A3, and A4 following replacement of PSL-03481A1 and A2 on April 29, 2025 (5)
Unit 2, SO-252-005, 48-Month High-Pressure Coolant Injection Flow Verification, high-pressure coolant injection system post-maintenance testing during startup on June 3, 2025 Surveillance Testing (IP Section 03.01) (4 Samples)
(1)
Unit 2, SM-288-104, 48-Month Division I-2D650-250 Volts Direct Current Battery Discharge Modified Performance Test and Battery Charger Capability Test, on April 3, 2025 (2)
Unit 2, SO-259-200, 24-Month Logic System Functional Test of the Primary and Secondary Containment Isolation System, on April 4, 2025
7 (3)
Unit 2, SO-283-001, 24-Month Division 1 Automatic Depressurization System Logic System Functional Test, on April 9, 2025 (4)
Unit Common, SO-054-001, B Logic System Functional Test of the Emergency Service Water System Pump 'B' Start and Reset Logic, on May 20, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Unit 2, SO-253-00A, 24-Month Standby Liquid Control Operability (Loop A), on April 5, 2025 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
Unit Common, DC-B5B-100, Attachment B, Operations of the B.5.b Portable Generators, on May 29, 2025 RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)
The inspectors observed workers exiting the radiologically controlled area at Unit 2 during the refueling outage in Unit 2.
(2)
The inspectors observed workers exiting the radiologically controlled area at Unit 1 during the refueling outage in Unit 2.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)
Personnel de-staging high contamination robotic equipment on the refueling floor (2)
Electricians working under the vessel during the Unit 2 refueling outage (3)
Carpenters removing scaffold in the drywell during the Unit 2 refueling outage (4)
Operators loading fuel in the reactor vessel during the Unit 2 refueling outage
8 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:
(1)
Heat exchanger cell in the Unit 2 reactor building on the 749' elevation (2)
Fuel pool pump room in the Unit 2 reactor building on the 749' elevation (3)
Clean-up holding pump room in the Unit 2 reactor building on the 779' elevation Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1)
The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
OTHER ACTIVITIES - BASELINE 71152A - Annual Follow-up of Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
Review of corrective actions for condition report (CR)-2024-13422, Startup from Unit 1 Cycle 24 Maintenance Outage Not in Compliance with Control Rod Drop Analysis (2)
Review of corrective actions associated with 4 kilovolt breaker failure (CR-2024-13462)
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 April 3, 2025, the inspectors presented the inservice inspection results to Doug LaMarca, Director - Strategic Planning, and other members of the licensee staff.
On April 10, 2025, the inspectors presented the radiological hazard assessment and exposure control inspection results to Doug Lamarca, Director - Strategic Planning, and other members of the licensee staff.
On July 28, 2025, the inspectors presented the integrated inspection results to Edward Casulli, Site Vice President, and other members of the licensee staff.
9 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.04 Corrective Action Documents Resulting from Inspection CR-2025-06799 CR-2025-06802 CR-2025-06803 CR-2025-08540 CR-2025-08549 Miscellaneous CL-024-0012 Diesel Generator A Revision 13 CL-259-0719 Unit 2 719' Containment Close-Out Revision 12 CL-259-0738 Unit 2 738' Containment Close-Out Revision 2 CL-259-0752 Unit 2 752' Containment Close-Out Revision 3 CL-259-0767 Unit 2 767' Containment Close-Out Revision 2 71111.05 Calculations EC-013-1913 PGCC Halon Systems for the Units 1 and 2 Upper & Lower Relay Rooms Revision 0 NEDO-10466-A Licensing Topical Report Power Generation Control Complex Design Criteria and Safety Evaluation February 1979 Corrective Action Documents CR-2025-07150 Corrective Action Documents Resulting from Inspection AR-2025-06036 AR-2025-06329 AR-2025-06894 AR-2025-06897 AR-2025-06902 AR-2025-06904 AR-2025-08195 AR-2025-09289 CR-2025-06030 CR-2025-06039 CR-2025-09248 CR-2025-09251 Fire Plans FP-013-CS Control Structure Digital Prefire Plan Revision 2 FP-1-CS-754 Susquehanna S.E.S. Prefire Plan Units 1 & 2, El. 754 Revision 0 FP-1-CS-771 Susquehanna S.E.S. Prefire Plan Units 1 & 2, El. 771 Revision 0 FP-2-RB-683 Susquehanna S.E.S. Prefire Plan Unit 2, El. 683 Revision 0
10 Inspection Procedure Type Designation Description or Title Revision or Date 71111.05 Fire Plans FP-2-RB-719 Susquehanna S.E.S. Prefire Plan Unit 2, El. 719 Revision 0 FP-2-TB-656 Susquehanna S.E.S. Prefire Plan Unit 2, El. 656 Revision 0 FP-2-TB-729 Susquehanna S.E.S. Prefire Plan Unit 2, El. 729 Revision 0 FP-213-100 Drywell (II 400, II 516, II 607) Fire Zone 2 4F, Elev. 704' through 807' Revision 4 FP-213-RB2 Unit 2 Reactor Building Prefire Plan Revision 2 Miscellaneous Halon Concentration Test Report 1U706 05/27/1982 22A5931 PGCC Fire Protection System Revision 0 Procedures SM-113-015 3-Year Inspection, Level/Weight Measurement, and Pressure/Flow Verification of Halon Cylinders Revision 8 71111.08G Corrective Action Documents Resulting from Inspection CR-2025-05353 CR-2025-05456 CR-2025-05574 71111.11Q Procedures SO-100-023 ASME Class I Boundary Leakage Test (Infrequently Performed Test or Evolution)
Revision 15 71111.12 Corrective Action Documents CR-2025-07497 CR-2025-09186 71111.13 Miscellaneous30-001 CREOASS 'A' Train - 9/9/24 Revision 0 54-009-ESW DIV 1 Emergency Service Water Division 1 Revision 0 71111.15 Corrective Action Documents CR-2024-11300 CR-2025-04411 CR-2025-04793 CR-2025-04802 CR-2025-05033 CR-2025-05430 CR-2025-10230 Procedures NDAP-QA-0004 Procedure Change Process Revision 40
11 71111.15 Work Orders RACT 2655184 RTPM 2655446 RTSV 2418113 RTSV 2425512 RTSV 2633020 RTSV 2701544 RTSV 2749527 71111.18 Corrective Action Documents CR-2025-06503 Engineering Changes EC 2803696 Replace HV251F009 Actuator Motor Revision 0 Procedures IP-ENG-001 Nuclear Standard Process Revision 3 71111.20 Corrective Action Documents Resulting from Inspection CR-2025-07296 CR-2025-07298 CR-2025-07301 CR-2025-07378 Procedures OP-2RF-001 RX Vessel/Cavity Flood-Up and Let Down During Refueling Outages Revision 41 Work Orders RACT 2655156 71111.24 Corrective Action Documents CR-2025-03171 CR-2025-03911 Corrective Action Documents Resulting from Inspection CR-2025-04019 CR-2025-06004 Miscellaneous 52-001-U2 HPCI SOW Week of 3/17/25 Protected for Unit 2 HPCI SOW Revision 0 Procedures DC-B5B-100 Attachment B Operations of the B.5.b Portable Generators Revision 14 SI-024-301 5-Year Calibration of 'A' Diesel Generator Lube Oil Low Pressure Switches PSL-03481A1, A2, A3, A4 Revision 11 SM-288-104 48-Month Division 1 2D650 - 250VDC Battery Discharge Modified Performance Test and Battery Charger Capability Test Revision 24
12 71111.24 Procedures SO-054-001B Logic System Functional Test of the ESW System Pump B Start and Reset Logic Revision 5 SO-170-011 Unit 1 Secondary Containment Drawdown and In-Leakage Surveillance Test Zones I and III Revision 9 SO-200-023 ASME Class I Boundary Leak Test Revision 11 SO-252-005 48-Month HPCI Flow Verification Revision 29 SO-253-003A 24-Month SBLC Operability (Loop A)
Revision 10 SO-259-200 24-Month Logic System Functional Test of the Primary and Secondary Containment Isolation System Revision 6 SO-283-001 24-Month Division 1 ADS Logic System Functional Test Revision 2 Work Orders PCWO 2345661-0 PCWO 2807421-0 RTPM 2655412 RTPM 2655414 RTPM 2655415 RTSV 2633037 RTSV 2635026 RTSV 2635027 RTSV 2639600 RTSV 2639601 RTSV 2639612 RTSV 2639613 RTSV 2639631 RTSV 2807650 WO 2685630-0 71124.01 Corrective Action Documents Resulting from Inspection CR-2025-05991 Potential for Individuals to Enter a LHRA from Platforms Next to the Reactor Feed Pump Turbines 04/07/2025 CR-2025-06077 Identified Metal Filings on the Valve Body of 251F060A Residual Heat Removal (RHR) Injection to Recirculating Loop A 04/08/2025 CR-2025-06160 Follow-up Actions for Contamination Incidents That Are
<100 ccpm 04/09/2025
13 71152A Corrective Action Documents CR-2024-13462 Procedures LS-120 Issue Identification and Screening Process Revision 16 LS-125 Corrective Action Program Revision 17 MT-GE-048 Cutler-Hammer Type DHP-VR 4.16 kV Circuit Breaker and Switchgear Inspection and Maintenance Revision 35