IR 05000387/2025003
| ML25356A002 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/22/2025 |
| From: | Jason Schussler Division of Operating Reactors |
| To: | Berryman B Susquehanna |
| References | |
| EAF-NMSS-2025-0223 IR 2025003, IR 2024001 | |
| Download: ML25356A002 (0) | |
Text
December 22, 2025
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
INTEGRATED INSPECTION REPORT 05000387/2025003 AND 05000388/2025003, INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200028/2024001 AND 07200028/2025001, AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Brad Berryman:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On December 1, 2025, the NRC inspectors discussed the results of this inspection with Melisa Krick, Regulatory Affairs/Performance Improvement Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and made progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025, third quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, fourth quarter integrated inspection reports, which will be issued 45 days after the fourth quarter ends on December 31, 2025.
The NRC identified a violation of Title 10 of the Code of Federal Regulations (10 CFR) 72.48, paragraphs (c)(1), (c)(2), and (d)(1), and provisions of 10 CFR 72.212 that resulted from a certificate of compliance (CoC) holders failure to comply with 10 CFR 72.48 for a CoC holder-generated change for the Holtec continuous basket shim multi-purpose canister variant design.
However, an Interim Enforcement Policy issued in August 2025 is applicable to this violation. Specifically, Enforcement Policy, Section 9.4, Enforcement Discretion for General Licensee Adoption of CoC Holder-Generated Modifications under 10 CFR 72.48, provides enforcement discretion to not issue an enforcement action for this violation. The licensee will be expected to comply with 10 CFR 72.212 provisions after the NRC dispositions the noncompliance for a CoC holder-generated change that affects the general licensee.
No other findings or violations of more than minor significance were identified during this inspection.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Susquehanna Steam Electric Station.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Jason E. Schussler, Chief Projects Branch 1 Division of Operating Reactor Safety
Docket Nos. 05000387, 05000388, and 07200028 License Nos. NPF-14 and NPF-22
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000387, 05000388, and 07200028
License Numbers:
Report Numbers:
05000387/2025003, 05000388/2025003, 07200028/2024001,
and 07200028/2025001
Enterprise Identifier: I-2025-003-0042, I-2024-001-0106, and I-2025-001-0106
Licensee:
Susquehanna Nuclear, LLC
Facility:
Susquehanna Steam Electric Station, Units 1 and 2
Location:
769 Salem Blvd., Berwick, PA
Inspection Dates:
July 1, 2025 to September 30, 2025
Inspectors:
D. Antonangeli, Senior Resident Inspector
E. Brady, Resident Inspector
D. Beacon, Senior Project Engineer
B. Dyke, Senior Operations Engineer
B. Edwards, Health Physicist
N. Harmon, Health Physicist
A. Kostick, Health Physicist
S. Mercurio, Emergency Preparedness Inspector
L. Sinclair, Senior Operations Engineer
K. Smetana, Resident Inspector
Approved By:
Jason E. Schussler, 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 of more than minor significance were identified. One violation was identified for which enforcement discretion was granted.
Additional Tracking Items
Type Issue Number Title Report Section Status Enforcement Discretion Granted EAF-NMSS-2025-0223 Noncompliance Related to a General Licensees Use of Non-Qualified Spent Fuel Casks (IEP 9.4)60855 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On July 22, 2025, the unit had an unplanned scram due to a loss of cooling to a main power transformer. On July 24, 2025, the unit started up and achieved rated thermal power on July 28, 2025. On September 5, 2025, the unit was down powered to 70 percent for a sequence exchange and rod pattern adjustment and returned to rated thermal power on September 6, 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 July 10, 2025, the unit was down powered to 15 percent due to an electrohydraulic control oil leak. The unit started raising power on July 12, 2025. On July 16, 2025, the unit returned to rated thermal power. On August 24, 2025, the unit down powered to 58 percent for a rod sequence exchange and returned to rated thermal power on August 25, 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) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, reactor core isolation cooling on July 31, 2025
- (2) Unit 1, high-pressure coolant injection on August 21, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (IP Section 03.01) (3 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) Units 1 and 2, turbine building, oil conditioner room, fire zones 1-31E and 2-31E, on August 1, 2025
- (2) Unit Common, control structure, fire zones 0-25A, 0-25E, and 0-26K, on August 11, 2025
- (3) Unit Common, SO-013-020, Deluge Test, fire zone 0-00, on September 3, 2025
71111.06 - Flood Protection Measures
Flooding (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in Unit 1, 683 -foot elevation, on August 24, 2025
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit Common, 'D' emergency diesel generator (EDG) on August 1, 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 a down power due to an electrohydraulic control fluid oil leak on July 10, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification training in the Unit 1 simulator on August 14, 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:
- (1) Unit 2, emergency service water leaks in the loop 'B' return header from the 'B' reactor building closed cooling water system on September 4, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (2 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, high-risk evolution replacement of the 5A feedwater normal level control drain valve controller on August 6, 2025
- (2) Unit 1, division 2 core spray during division 1 core spray system outage window on September 30, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2, residual heat removal service water pump discharge pressure in alert range on June 28, 2025
- (2) Unit 2, drywell unidentified leakage source determination on July 17, 2025
- (3) Unit Common, 'D' EDG turbocharger found failed during 5-year overhaul on July 30, 2025
- (4) Unit 1, diverse indication of unidentified leakage increase into the drywell on July 31, 2025
- (5) Unit Common, 'D' EDG, PSL-03483D2, was found out of tolerance on August 6, 2025
- (6) Unit 2, control rod drive scram discharge volume vent valve closure time outside of acceptance criteria on September 4, 2025
- (7) Unit Common, seismic qualifications for electrical cable trays to emergency service water pumphouse, MH031 and MH032, on September 10, 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) Permanent modification to address reactor vessel water level procedure revisions implemented before NRC approval on September 30, 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 (IP Section 03.01) (6 Samples)
- (1) Unit Common, ultimate heat sink spray pond nozzle inspections, cleaning and subsequent test on July 9, 2025
- (2) Unit 1, main transformer cooling system controller replacement on July 23, 2025
- (4) Unit Common, 'D' EDG turbocharger replacement on August 12, 2025
- (5) Unit Common, 'A' EDG Agastat relay replacements on August 26, 2025
- (6) Unit Common, engineered safeguards transformer 0X211 following maintenance outage on September 10, 2025
Surveillance Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, reactor core isolation cooling flow verification on July 31, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1, residual heat removal service water comprehensive flow test and baseline establishment following pump replacement on September 18, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) The inspectors observed a drill scenario that included a natural weather hazard event that impacted safety related equipment, an anticipated transient without a scram, a loss-of-coolant accident, and a subsequent radiological release in the Unit 1 simulator on August 19,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
Groundwater Protection Initiative Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the groundwater protection initiative program.
OTHER ACTIVITIES - BASELINE
71152A - Annual Follow-Up 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) Unit Common, clarified water storage tank (fire protection water source) through-wall leaks on September 2, 2025
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in procedure use and adherence during the procedure revision change process that might be indicative of a more significant safety issue. No adverse trend was identified.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) The inspectors evaluated a Unit 2 rapid down power due to an electrohydraulic control fluid leak in the turbine system and the licensees performance on July 11, 2025.
- (2) The inspectors evaluated a Unit 1 manual reactor scram due to a loss of main transformer cooling and the licensees performance on July 22,
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===60855 - Operation of an Independent Spent Fuel Storage Installation (ISFSI)
The inspectors evaluated the licensees ISFSI operations from September 22 to 26, 2025, including observations of routine ISFSI activities and compliance with NRC requirements, license conditions, and technical specifications as required under Title 10 of the Code of Federal Regulations (10 CFR) Part 72.
Operation of an ISFSI===
- (1) The following activities were observed and/or reviewed via document review and through personnel interviews to assess compliance with NRC requirements, license conditions, and technical specifications:
- Walkdowns of the ISFSI pad and assessment of loaded cask material conditions
- Review of radiation protection procedures and radiological monitoring programs
- Review of surveillance activities, including thermal monitoring and structural integrity inspections
- Interviews with site personnel regarding periodic surveillances of loaded casks
- Review of 10 CFR 72.48 screenings and evaluations for ISFSI modifications
- Assessment of corrective action program reports and licensee -identified issues
- Assessment of the quality assurance program and controls associated with ISFSI operations
===60859 - ISFSI License Renewal Inspection
The inspectors evaluated the licensees ISFSI license renewal program from August 4 to September 26, 2025, including observation of the licensees baseline canister inspection and review of licensee compliance with NRC regulations, license conditions, and technical specifications as required under 10 CFR Part 72 and the Certificate of Compliance 1004, License Amendment 14, and Final Safety Analysis Report (FSAR),
Revision 18.
ISFSI License Renewal Inspection===
- (1) The inspectors conducted the following activities and interviewed site personnel to assess compliance with NRC regulations, license conditions, and technical specifications:
- Observation of the sites first tollgate aging management inspection
- Review of the licensee's aging management basis documentation to include identification and evaluation of site-specific time limited aging analyses and lead canister selection criteria, aging management inspection acceptance criteria, and aging management corrective action procedures
- Review of the licensee's scoping, planning, and subsequent implementation of ISFSI aging management programs (AMPs) required for the various structures, systems, and components which required an AMP per licensing requirements
- Review of 10 CFR 72.48 screenings and evaluations related to ISFSI license renewal and aging management activities
- Assessment of the licensee's acceptance criteria and corrective action program for the AMPs, with a focus on assessing the licensees planned measures in the event of an aging management acceptance criterion not being met
- Review of the licensee's method(s) to collect and assess the effectiveness of the operating experience associated with the ISFSI license renewal and aging management activities throughout the period of extended operation or identify the need for AMP modifications, as warranted
- Review of the licensee's administrative controls (i.e., aging management procedures and preventive/corrective action procedures) associated with ISFSI license renewal and aging management activities
92709 - Licensee Strike Contingency Plans Licensee Strike Contingency Plans
- (1) On September 25, 2025, at midnight, the contract between International Brotherhood of Electrical Workers Local 1600 and Susquehanna was set to expire. In preparation for a potential strike, the NRC inspectors evaluated the adequacy of the licensees contingency plan. The inspectors assessed the adequacy of the plan's post-strike staffing levels, staff qualifications, safety conscious working environment, and site access in meeting operational and security requirements.
INSPECTION RESULTS
Enforcement Discretion Enforcement Action EAF-NMSS-2025-0223: Noncompliance Related to a General Licensees Use of Non-Qualified Spent Fuel Casks (IEP 9.4)60855
Description:
Holtec International (also referred to as the CoC holder) implemented a design change to its multi-purpose canister fuel basket, known as the continuous basket shim (CBS)variant, which altered the structural configuration from welded to bolted shims. This change resulted in a departure from the method of evaluation (MOE) described in the FSAR used to establish the design basis for tip-over events. Holtec did not fully evaluate the cumulative impact of the MOE changes or apply them consistently with the licensing basis. As a result, the NRC issued three Severity Level IV violations to Holtec for noncompliance with 10 CFR 72.48 requirements (see U.S. Nuclear Regulatory Commission Inspection Report 07201014/2022-201, Holtec International, Agencywide Documents Access and Management System (ADAMS) Accession No. ML23145A175, and Holtec International Inc. - Notice of Violation; The U.S. Nuclear Regulatory Commission Inspection Report No. 07201014/2022-201, ML24016A190).
When the licensee (also referred to as a general licensee) chooses to adopt a change to the CoC holder made pursuant to a CoC holder's change authority under 10 CFR 72.48 (referred to herein as a CoC holder-generated change), the licensee must perform a separate review using the requirements of 10 CFR 72.48(c). Accordingly, when the licensee chooses to adopt a CoC holder-generated change, and that change results in a non-conforming cask, there is a violation of 10 CFR 72.48 and certain provisions of 10 CFR 72.212 by the licensee, in addition to a CoC holder violation of 10 CFR 72.48. As it relates to the adoption of the CBS variant casks, the licensee failed to recognize the noncompliance with 10 CFR 72.48 requirements made by the CoC holders design change and subsequently loaded the CBS variant casks.
Corrective Actions: The licensee entered this into their corrective action program with actions to restore compliance with the 10 CFR 72.212 provisions that require each cask to conform to the terms, conditions, and specifications of a CoC or an amended CoC listed in 72.214.
Corrective Action References: 72.48 SE 00003, Revision 0, CR-2024-02396, LDCN 5864
Enforcement:
Significance/Severity: This violation was dispositioned in accordance with Section 9.4, Enforcement Discretion for General Licensee Adoption of CoC Holder-Generated Changes Under 10 CFR 72.48, of the NRCs Enforcement Policy.
Specifically, as stated in the policy, the NRC will exercise enforcement discretion and not issue an enforcement action to a general licensee, for a noncompliance with the requirements of paragraphs (c)(1) and
- (2) and (d)(1) of 10 CFR 72.48 and with provisions of 10 CFR 72.212 that require general licensees to ensure use of casks that conform to the terms, conditions, and specifications of a CoC listed in 10 CFR 72.214, when the noncompliance results from a CoC holders failure to comply with 10 CFR 72.48 for a CoC holder-generated change.
Violation: 10 CFR 72.48 (c)(1) requires, in part, that the licensee or certificate holder may make changes in the facility or spent fuel storage cask design as described in the FSAR (as updated), without obtaining:
- (ii) CoC amendment submitted by the certificate holder pursuant to § 72.244 if
- (c) the change, test, or experiment does not meet any of the criteria in paragraph (c)(2) of this section.
10 CFR 72.48(c)(2) requires, in part, that a general licensee shall request that the certificate holder obtain a CoC amendment, prior to implementing a proposed change, if the change would: (viii) result in a departure from an MOE described in the FSAR used in establishing the design bases or in the safety analyses.
10 CFR 72.48(d)(1) requires, in part, that the licensee shall have a written evaluation which provides the basis for the determination that the change does not require a CoC amendment pursuant to 72.48(c)(2).
10 CFR 72.212(b)(3) requires, in part, that a general licensee must ensure that each cask used by the general licensee conforms to the terms, conditions, and specifications of a CoC or an amended CoC listed in 72.214.
Contrary to the above, in October 2022, the licensee loaded the first CBS design variant and failed to maintain records of changes in the spent fuel storage cask design made pursuant to 10 CFR 72.48(c) that include a written evaluation which provided the bases for the determination that the change did not require a CoC amendment. The licensee failed to request that the certificate holder obtain a CoC amendment, prior to implementing a proposed change, if the change would: (viii) result in a departure from an MOE described in the FSAR used in establishing the design bases or in the safety analyses. Further, the licensee failed to ensure each cask conformed to the terms, conditions, and specifications of a CoC or amended CoC listed in 10 CFR 72.214.
Basis for Discretion: When a general licensee chooses to adopt a CoC holder-generated change, and that change results in a non-conforming cask, there is a violation of 10 CFR 72.48 and certain provisions of 10 CFR 72.212 by the general licensee, in addition to a CoC holder violation of 10 CFR 72.48. And, when a general licensee chooses to adopt a CoC holder-generated change without performing a separate 10 CFR 72.48 analysis, the general licensee is in violation of 10 CFR 72.48. These requirements could lead to enforcement actions being issued against both the general licensees 10 CFR 72.48 program (as well as certain 10 CFR 72.212 violations) and the CoC holder's 10 CFR 72.48 program for changes that originated with the CoC holder. The NRC concluded that this enforcement approach would be inconsistent with efficiency, which is one of the NRC's principles of good regulation and NRC's mission of efficient and reliable oversight.
Since this violation meets the conditions of the NRC's Enforcement Policy, Section 9.4, titled Enforcement Discretion for General Licensee Adoption of Certificate of Compliance Holder -Generated Changes under 10 CFR 72.48 (25224A097), and the licensee has entered the noncompliance into the corrective action program, the NRC is exercising enforcement discretion by not issuing an enforcement action for this violation.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On July 30, 2025, the inspectors presented the radiological environmental monitoring program inspection results to Katie Brown, Nuclear Regulatory Affairs Supervisor, and other members of the licensee staff.
- On September 26, 2025, the inspectors presented the ISFSI license renewal and ISFSI operations inspection results to TJ Martinez, Maintenance Manager, and other members of the licensee staff.
- On December 1, 2025, the inspectors presented the integrated inspection results to Melisa Krick, Regulatory Affairs/Performance Improvement Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
M-149
Susquehanna SES Unit 1 P&ID Reactor Core Isolation
Cooling
Revision 54
Miscellaneous
CL-150-0012
INST
Unit 1 Reactor Core Isolation Cooling System
Revision 26
CL-150-0012
VALV
Unit 1 Reactor Core Isolation Cooling System
Revision 26
Corrective Action
Documents
CR-2025-13778
Fire Plans
Control Structure Digital Prefire Plan
Revision 2
FP-1-CS-714
Susquehanna SES Prefire Plan Unit 1 Control Structure
El. 714
Revision 2
FP-1-CS-741
Susquehanna SES Prefire Plan Unit 1 Control Structure
El. 741
Revision 2
FP-1-TB-656-1
Susquehanna SES Prefire Plan Unit 1 El. 656 Start Up and
Test
Revision 0
Unit 1 Turbine Building Prefire Plan
Revision 2
FP-2-TB-656-1
Susquehanna SES Prefire Plan Unit 2 El. 656 Start Up and
Test
Revision 0
Unit 2 Turbine Building Prefire Plan
Revision 2
Procedures
SO-013-020
Three-Year ESS Transformer 201 (0X203) and ESS
Transformer 111 (0XC211) Deluge System DS-017 Full Flow
Test
Revision 18
Corrective Action
Documents
CR-2025-14055
Corrective Action
Documents
CR-2025-12000
CR-2025-12146
CR-2025-12151
Work Orders
RTSV 2664221
WO 2667338
71111.11Q Drawings
M-2191
Susquehanna SES Unit 2 P&ID Main Turbine EHC System
Revision 19
Corrective Action
Documents
CR-2025-08867
Drawings
M-152
Susquehanna SES Unit 1 P&ID Core Spray
Revision 44
Miscellaneous51-001
Core Spray Div 1 SOW
09/29/2025
Corrective Action
Documents
CR-2025-09847
CR-2025-10059
CR-2025-10591
CR-2025-11993
CR-2025-12218
CR-2025-12766
CR-2025-13751
Drawings
E-259 Sheet 9C
Susquehanna SES Schematic Diagram Diesel Generator
Engine Control
Revision 8
M130-124 Sheet
13C
Susquehanna SES Common DG Control Schematic Starting
Sequence Control Panel
Revision 6
M30-124 Sheet
3C
Susquehanna SES Common DG Control Schematic Starting
Sequence
Revision 7
Procedures
SO-255-002
Quarterly SDV Vent and Drain Valve Operability Check
Revision 30
Work Orders
RTSV 2823519
Corrective Action
Documents
CR-2025-10667
CR-2025-10668
Procedures
SO-150-002
Quarterly RCIC Flow Verification
Revision 65
Work Orders
RTPM 2637959
Corrective Action
Documents
CR-2025-11237
CR-2025-11673