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Susquehanna Steam Electric Station, Units 1 and 2 - Integrated Inspection Report 05000387/2025001 and 05000388/2025001
	ML25121A252
Person / Time
Site:	Susquehanna
Issue date:	05/12/2025
From:	Sarah Elkhiamy; Division of Operating Reactors
To:	Berryman B; Susquehanna
References
	IR 2025001
	Download: ML25121A252 (1)
	v • d • e

May 12, 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 05000387/2025001 AND 05000388/2025001

Dear Brad Berryman:

On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On April 3, 2025, the NRC inspectors discussed the results of this inspection with Doug LaMarca, Director - Strategic Planning, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Sarah H. Elkhiamy, Chief Operations Branch 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 SARAH ELKHIAMY Digitally signed by SARAH ELKHIAMY Date: 2025.05.12 06:42:29 -04'00'

ML25121A252 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS RI/DORS NAME JEngland SHaney SElkhiamy DATE 4/28/2025 4/30/2025 4/30/2025

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

05000387 and 05000388 License Numbers:

NPF-14 and NPF-22 Report Numbers:

05000387/2025001 and 05000388/2025001 Enterprise Identifier: I-2025-001-0050 Licensee:

Susquehanna Nuclear, LLC Facility:

Susquehanna Steam Electric Station, Units 1 and 2 Location:

769 Salem Blvd., Berwick, PA Inspection Dates:

January 1, 2025 to March 31, 2025 Inspectors:

J. England, Senior Resident Inspector E. Brady, Resident Inspector S. Haney, Senior Project Engineer Approved By:

Sarah H. Elkhiamy, Chief Operations Branch 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 March 6, 2025, the unit down powered to 85 percent for scram time testing. On March 7, 2025, the unit down powered to 60 percent for a rod sequence exchange and returned to rated thermal power on March 9, 2025.

The unit remained at or near rated thermal power for the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power. On January 9, 2025, the unit was down powered to 78 percent for a rod pattern adjustment and returned to rated thermal power on January 10, 2025. On January 16, 2025, the unit was down powered to 77 percent for a rod pattern adjustment and returned to rated thermal power on January 17, 2025. On February 7, 2025, the unit was down powered to 74 percent for a rod pattern adjustment and returned to rated thermal power on February 9, 2025. On February 14, 2025, the unit commenced coast down and shut down for a refueling outage on March 23, 2025, and remained shut down 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, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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 71111.01 - Adverse Weather Protection Seasonal Extreme Weather IP Section 03.01) (1 Sample)

(1)

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of hot weather for offsite power on March 11, 2025.

Impending Severe Weather (IP Section 03.02) (1 Sample)

(1)

The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather on January 16 and 17, 2025.

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:

4 (1)

Unit 1 core spray division 1 on January 21, 2025 (2)

Unit Common standby gas treatment during the week of February 10, 2025 (3)

Unit Common emergency service water during the week of March 3, 2025 71111.05 - Fire Protection Fire Area Walkdown and Inspection (IP Section 03.01) (4 Samples; 1 Partial)

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 1 reactor building, 645-foot elevation, fire areas 1-1A, 1-1B, 1-1C, 1-1D, 1-1E, 1-1F, and 1-1G, on January 7, 2025 (2)

(Partial)

Unit Common control structure, 698-foot elevation, fire areas 0-24A, 0-24B, 0-24C, 0-24D, 0-24E, and 0-24G, on January 15, 2025 (3)

Unit Common FLEX equipment building, emergency service water building, and residual heat removal service water building, 685-foot and 721-foot elevations, fire areas 0-51, 0-52, and 0-FS, on February 11, 2025 (4)

Unit 2 reactor building, 779-foot elevation, fire areas 2-6A, 2-6B, 2-6C, and 2-6D, on February 12, 2025 (5)

Unit 2 turbine building, 676-foot and 699-foot elevations, fire areas 2-32B, 2-32C, 2-32D, 2-32E, 2-32F, 2-32I, 2-33B, 2-33C, 2-33D, 2-33E, 2-33F, and 2-33G, on March 27, 2025 Fire Brigade Drill Performance (IP Section 03.02) (1 Sample)

(1)

The inspectors evaluated the on-site fire brigade training and performance during an unannounced fire drill on January 17, 2025.

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 Unit 2 control room during reactor shutdown on March 23 and 24, 2025.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1)

The inspectors observed and evaluated licensed operator requalification training in the simulator on January 27, 2025.

71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

5 (1)

Unit Common 'B' emergency diesel generator (EDG) mid-cycle outage starting February 3, 2025 Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following structures, systems, and components remain capable of performing their intended function:

(1)

Unit Common 'C' EDG synchronous selector switch on March 10, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management (IP Section 03.01) (5 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 planned maintenance on division 2 core spray during the week of January 13, 2025 (2)

Units 1 and 2 elevated risk due to planned maintenance of the 'A' EDG resulting in the 125-volt direct current battery chargers supplied by an alternate source during the week of February 24, 2025 (3)

Unit 2 elevated risk during planned maintenance on reactor core isolation cooling during the week of March 10, 2025 (4)

Unit 2 elevated risk during planned maintenance on the high-pressure coolant injection system during the week of March 17, 2025 (5)

Unit 2 elevated risk during the refueling outage during the week of March 24, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1)

Unit 1 start up from cycle 24 maintenance outage was not in compliance with EC-FUEL-1973 on January 15, 2025 (CR-2024-13422)

(2)

Unit 2 foreign material in breaker cubicle on January 16, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage (IP Section 03.01) (1 Partial)

(1)

(Partial)

The inspectors evaluated Unit 2 refueling outage 22 activities from March 4 to March 31, 2025. The inspectors completed sections a., b.1, b.2, c.3, c.4, c.6, c.7, c.9, and c.10.

6 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 (IP Section 03.01) (5 Samples)

(1)

Unit 2 reactor water cleanup steam isolation following temperature switch replacement on January 23, 2025 (2)

Unit Common 'C' EDG following synchroscope replacement on January 29, 2025 (3)

Unit Common 'B' EDG post-maintenance test following mid-cycle overhaul on February 11, 2025 (4)

Unit Common 125-volt direct current station batteries monthly and quarterly electrical parameter checks for Unit 2 following planned maintenance during the week of February 24, 2025 (5)

Unit Common measure currents and perform voltage regulator checks after 'A' EDG linear reactor replacement on February 27, 2025 Surveillance Testing (IP Section 03.01) (4 Samples)

(1)

Unit 2 SO-249-007, Residual Heat Removal Logic System Functional Test (Div I),

on February 3, 2025 (2)

Unit 1 SO-193-001, Turbine Valve Cycling, on March 11, 2025 (3)

Unit 2 SO-225-101, Long-Term Nitrogen Supply System Functional Test (A Header), on March 18, 2025 (4)

Unit 2 SO-224-117, Division I Diesel Generator Loss of Coolant Accident Loss of Offsite Power Test (Infrequently Performed Test or Evolution), on March 27, 2025 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1)

Unit 2 SE-259-150, Hydraulic Leak Test of Control Rod Drive Seismic Island Check, on March 31, 2025 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours (IP Section 02.01) (2 Samples)

(1)