IR 05000387/2025002
| 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
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
Inspection Report
Docket Numbers:
05000387 and 05000388
License Numbers:
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
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.
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.
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)
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)
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
- (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
- (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,
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 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)
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
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
Calculations
EC-013-1913
PGCC Halon Systems for the Units 1 and 2 Upper & Lower
Relay Rooms
Revision 0
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
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
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
Drywell (II 400, II 516, II 607) Fire Zone 2 4F, Elev. 704'
through 807'
Revision 4
Unit 2 Reactor Building Prefire Plan
Revision 2
Miscellaneous
Halon Concentration Test Report 1U706
05/27/1982
2A5931
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
Corrective Action
Documents
CR-2025-07497
CR-2025-09186
Miscellaneous30-001
CREOASS 'A' Train - 9/9/24
Revision 0
54-009-ESW DIV 1 Emergency Service Water Division 1
Revision 0
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
Work Orders
RACT 2655184
RTPM 2655446
RTSV 2418113
RTSV 2425512
RTSV 2633020
RTSV 2701544
RTSV 2749527
Corrective Action
Documents
CR-2025-06503
Engineering
Changes
Replace HV251F009 Actuator Motor
Revision 0
Procedures
IP-ENG-001
Nuclear Standard Process
Revision 3
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
Corrective Action
Documents
CR-2025-03171
CR-2025-03911
Corrective Action
Documents
Resulting from
Inspection
CR-2025-04019
CR-2025-06004
Miscellaneous
2-001-U2 HPCI
SOW Week of
3/17/25
Revision 0
Procedures
DC-B5B-100
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
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
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
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