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Integrated Inspection Report 05000387/2024001 and 05000388/2024001
	ML24134A093
Person / Time
Site:	Susquehanna
Issue date:	05/13/2024
From:	Jon Greives; NRC/RGN-I/DORS
To:	Berryman B; Susquehanna
References
	IR 2024001
	Download: ML24134A093 (1)
	v • d • e

May 13, 2024

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -

INTEGRATED INSPECTION REPORT 05000387/2024001 AND 05000388/2024001

Dear Brad Berryman:

On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On April 29, 2024, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Jonathan E. Greives, Chief Projects Branch 4 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: NPF-14 and NPF-22

Report Numbers: 05000387/2024001 and 05000388/2024001

Enterprise Identifier: I-2024-001- 0053

Licensee: Susquehanna Nuclear, LLC

Facility: Susquehanna Steam Electric Station, Units 1 and 2

Location: 769 Salem Blvd., Berwick PA

Inspection Dates: January 1, 2024 to March 31, 2024

Inspectors: J. England, Senior Resident Inspector E. Brady, Resident Inspector H. Anagnostopoulos, Senior Health Physicist A. Kostick, Health Physicist

Approved By: Jonathan E. Greives, Chief Projects Branch 4 Division of Operating Reactor Safety

Enclosure

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 and was at or near full rated thermal power with the following exceptions. On January 19, 2024, the unit was down powered to percent for a rod pattern adjustment and returned to rated thermal power. On February 2, 2024, the unit was down powered to approximately 81 percent for a rod pattern adjustment and channel distortion testing and returned to rated thermal power. On February 9, 2024, the unit was down powered to approximately 83 percent for a rod pattern adjustment and returned to rated thermal power. On February 23, 2024, the unit was down powered to approximately 92 percent for a rod pattern adjustment and returned to rated thermal power. On February 24, 2024, the unit commenced coast down and shut down for the refueling outage on March 25, 2024, and remained shut down for the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power and was at or near full rated thermal power with the following exception. On March 22, 2024, the unit was down powered to approximately 59 percent for a rod sequence exchange. The unit was returned to rated thermal power on March 23, 2024, and 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 (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identific ation 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

71111.04 - 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 1 residual heat removal on January 4, 2024

(2) Unit 2 'A' core spray during 'B' core spray surveillance testing on January 11, 2024

(3) Unit 1 standby gas treatment during 'C' essential service supply bus work and fuel moves (Yellow risk) on March 31, 2024

71111.05 - Fire Protection

Fire Area Walkdown and Inspection (IP Section 03.01) (5 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 Common control structure, 806-foot elevation, standby gas treatment room, fire zone (FZ) 0-30A, on January 3, 2024

(2) Unit 1 reactor building, 749-foot elevation, FZ 1-5A-N, 1-5A-S, and 1-5A-W, on January 8, 2024

(3) Units 1 and 2 reactor building, 818-foot elevation, refueling bay, FZ 0-8A, on January 24, 2024

(4) Unit 2 reactor building, 645-foot elevation, high-pressure coolant injection pump room, FZ 2-1C, on February 21, 2024

(5) Unit 1 turbine building, 656, 676, and 699-foot elevations, condenser gallery, mezzanine, pad 1 and 2, FZ 1-31D, 1-32D, and 1-33C on March 27, 2024

Fire Brigade Drill Performance (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated fire brigade performance during an unannounced fire drill on February 28, 2024.

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 1 'A' residual heat removal heat exchanger

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 shutdown and cooldown for the Unit 1 planned refueling outage on March 24 and 25, 2024.

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

(1) The inspectors observed Unit 1 simulator and classroom training for plant shutdown and cooldown on March 20, 2024.

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:

(1) Unit Common 'E' emergency diesel generator on January 22, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management (IP Section 03.01) (4 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 1 division 1 planned work on core spray system on January 9, 2024

(2) Unit 2 division 1 planned work on residual heat removal heat exchanger bypass valve during the week of January 29, 2024

(3) Unit 1 elevated risk during reactor vessel disassembly during the week of March 25, 2024

(4) Unit 1 bus outage on 1A203 on March 30 and 31, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

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

(1) Unit 1 high-pressure coolant injection with water in lube oil system on January 11, 2024

(2) Unit 2 'B' core spray pump due to breaker instantaneous overcurrent flag on January 12, 2024

(3) Unit Common loss of 1D240 due to failure of uninterruptable power supply battery bank on March 28, 2024

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated Unit 1 refueling outage U123RIO activities from March 25 to 31, 2024. The inspectors completed sections a., b.1, b.2, c.3, c.4, c.6, c.7, and c.8.

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) (2 Samples)

(1) Unit Common 'C' emergency diesel generator planned maintenance and unplanned fuel line replacement on January 25, 2024

(2) Unit Common emergency service water pipe replacement on February 15, 2024

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) Unit 1 SO-150-016, Reactor Core Isolation Cooling Functional Test at Remote Shutdown Panel (1C201A), on February 20, 2024

(2) Unit 1 SI-180- 305, Quarterly Calibration of Reactor Vessel Water Level Channels LIS-B21-1N024 A, B, C, D, on February 27, 2024

(3) Unit 1 SO-124-117, Division I Diesel Generator Loss-of-Coolant Accident Loss of Offsite Power Test (Infrequently Performed Test or Evolution), on March 27 and 28, 2024

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 2 SO-250-002, Quarterly Reactor Core Isolation Cooling Flow Verification, on January 25, 2024

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 SE-159-023, Local Leak-Rate Test of Main Steam Line Isolation Valves Penetration Number X-7C, on March 25, 2024

71114.06 - Drill Evaluation

Required Emergency Preparedness Drill (1 Sample)

(1) The inspectors evaluated the conduct of an emergency preparedness drill including a dropped fuel rod and a leak in the spent fuel pool on February 21,

RADIATION SAFETY

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Unit 1 reactor building, zone 3, high-efficiency particulate air and charcoal filter units 1F216A, 1F217A, and 1F218A

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) High-efficiency particulate air ventilation unit servicing the down-draft step off pad system on the 818-foot elevation of the refueling floor

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Internal dose calculation for employee Kxxxxx6 for an event on April 15, 2023

(2) Internal dose calculation for employee Jxxxxxxxxxx2 for an event on April 15, 2023

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Licensee procedures for limiting exposures for declared pregnant workers, including a review of completed declarations

(2) Shallow dose equivalent evaluation for a personnel contamination event on March 31,

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)===

Main article: IP 71151