ML25351A122
| ML25351A122 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/17/2025 |
| From: | Nicole Warnek Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| References | |
| IR 2025003 | |
| Download: ML25351A122 (0) | |
Text
December 17, 2025 Charles McFeaters President and Chief Nuclear Officer PSEG Nuclear, LLC - N09 P.O Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000354/2025003
Dear Charles McFeaters:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Generating Station. On November 19, 2025, the NRC inspectors discussed the results of this inspection with Eric Larson, Site Vice President, 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 make 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, 3rd 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, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
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:
C. McFeaters 2
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 Hope Creek Generating 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Nicole S. Warnek, Chief Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000354 License No. NPF-57
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV NICOLE WARNEK Digitally signed by NICOLE WARNEK Date: 2025.12.17 13:23:22 -05'00'
ML25351A122 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS RI/DORS NAME PFinney SHaney NWarnek DATE 12/15/2025 12/16/2025 12/17/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000354 License Number:
NPF-57 Report Number:
05000354/2025003 Enterprise Identifier: I-2025-003-0037 Licensee:
Hope Creek Generating Station Location:
Hancocks Bridge, NJ Inspection Dates:
July 1, 2025 to September 30, 2025 Inspectors:
J. Bresson, Project Engineer P. Finney, Senior Resident Inspector N. Harmon, Health Physicist J. Morgan, Operations Engineer R. Rolph, Senior Health Physicist Approved By:
Nicole S. Warnek, Chief Projects Branch 3 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 Hope Creek Generating Station, 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. A licensee-identified non-cited violation is documented in report section: 71111.24.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS Hope Creek began the inspection period at rated thermal power. On July 7, 2025, Hope Creek was reduced to 75 percent power in response to a main condenser 'C' North circulating water outlet through-wall leak. The leak was plugged and the unit returned to 100 percent power the next day. On July 10, 2025, Hope Creek was reduced to 85 percent power for a control rod pattern adjustment and returned to 100 percent power the next day. On July 19, 2025, Hope Creek was reduced to 84 percent power for a control rod pattern adjustment and returned to 100 percent power the next day. Between July 12 and August 17, 2025, Hope Creek was periodically lowered a few percent due to condenser backpressure limitations. On August 19, 2025, Hope Creek was reduced to 81 percent power for main condenser 'C' North waterbox leak repairs as well as 'A' North and 'A' South waterbox tube leak searches. The unit returned to 100 percent rated thermal power on August 24, 2025. On August 25, 2025, Hope Creek commenced its end-of-cycle coastdown. On September 25, 2025, Hope Creek commenced a shutdown from 87 percent power for a refueling outage.
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, 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 Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'B' residual heat removal (RHR) division during 'A' RHR pump breaker replacement and motor inspection, July 31, 2025 (2)
'B' core spray division post-maintenance walkdown, September 5, 2025 (3)
'A RHR as alternate decay heat removal method with 'B' RHR in shutdown cooling and reactor water level at the vessel flange, September 28, 2025
4 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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)
Electric access area and heating, ventilation, and air conditioning (HVAC) wing, Fire Area 3543, July 3, 2025 (2)
Diesel generator rooms, Fire Area 3531, July 21, 2025 (3)
Electric access area, Fire Area 3533, during major loss of emergency assessment capability (EN 57878), August 20, 2025 (4)
Control rod drive hydraulic control unit area, Fire Area 3435, September 18, 2025 Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)
(1)
The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on July 22, 2025.
(2)
The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on September 9, 2025.
71111.06 - Flood Protection Measures Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections in the safety auxiliaries cooling system (SACS) rooms on July 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 operations personnel during the reactor power reduction and trip for the refueling outage on September 25, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1)
The inspectors observed and evaluated annual simulator examinations on July 10, 2025.
(2)
The inspectors observed and evaluated annual simulator examinations on July 24, 2025.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample 1 Partial)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
5 (1)
(Partial)
Unresolved item (05000354/2025050-03) regarding the lantern ring and packing on emergency diesel generator lube oil heat exchanger floating heads, August 6, 2025 (2)
B2 SACS heat exchanger flange leak, effectiveness review after temporary modification completion to address all SACS heat exchanger flanges, September 29, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (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)
Elevated risk during scheduled activity on 'C' emergency diesel generator, July 7, 2025 (2)
Elevated risk during emergent trip of 'B' reactor protection system electrical protection assembly breakers, August 13, 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)
Oscillating power range monitor due to confirmation counts during power reduction, July 15, 2025 (2)
Control room HVAC due to low differential pressure on control room supply fan, on July 15, 2025 (3)
Final feedwater heating temperature reduction due to core end of life coastdown, July 29, 2025 (4)
'A' emergency diesel generator due to noise from intercooler piping during monthly surveillance, July 31, 2025 (5)
No record of standby liquid control squib valve surveillance test, August 12, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated refueling outage 26 activities from September 25 to 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:
6 Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
(1)
Barrier breach of control room envelope, July 8, 2025 (2)
Channel calibration following high pressure coolant injection relay replacement, July 9, 2025 (3)
'B' service water pump 4 kilovolt breaker replacement, July 14, 2025 (4) 480 volt motor control center starter preventive maintenance on drywell nitrogen supply motor-operated valve 1GSHV-4984B, July 17, 2025 (5)
Core spray division 2 channel discharge line flow (minimum flow bypass),
August 18, 2025 Surveillance Testing (IP Section 03.01) (3 Samples)
(1)
Refueling floor and reactor building exhaust process radiation monitoring channel time response testing, July 1, 2025 (2)
'C' main steam line flow sensor B21-N687C calibration, July 11, 2025 (3)
'C' RHR pump surveillance test, September 3, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Reactor core isolation cooling surveillance test, September 8, 2025 RADIATION SAFETY 71124.07 - Radiological Environmental Monitoring Program (REMP)
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. Partial completed in second quarter and remaining part of sample completed in third quarter.
GPI Implementation (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements.
7 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
(1)
July 1, 2024 through June 30, 2025 71153 - Follow-Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03) (2 Samples)
(1)
The inspectors evaluated the failure of the main control room master fire control panel and PSEG's performance on August 20, 2025 (EN 57878).
(2)
The inspectors evaluated the B2 SACS heat exchanger leak and emergency operating procedure entry, September 10, 2025.
INSPECTION RESULTS Licensee-Identified Non-Cited Violation 71111.24 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Hope Creek Technical Specification 6.8.1 requires that written procedures shall be implemented covering the activities referenced in Regulatory Guide 1.33, Revision 2, Appendix A which includes procedures for operation of safety-related boiling water reactor systems such as emergency core cooling systems in section 4.H. Procedure HC.IC-FT.BE-0004, "Core Spray Division 2 Channel E21-N651B Discharge Line Flow (Minimum Flow Bypass)," Revision 11, step 4.3.9 directed the technicians to notify the reactor operator that the core spray loop B minimum flow bypass valve may be positioned as required by plant conditions. Contrary to this, following notification by the technician, the reactor operator subsequently did not return the minimum flow bypass valve to an open position as required by plant conditions to restore the core spray system to an operable status. As a result, PSEG identified that from 9:41 p.m. on August 14, 2025, to 4:42 p.m. on August 15, 2025, control room operators had not returned the Division 2 core spray minimum flow valve to an open position following completion of an instrumentation and control surveillance test and was therefore inoperable until restored to an open position.
Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, the inspectors determined the finding screened to very low safety significance (Green), by answering No to all the questions in Exhibit 2A.
Corrective Action References: Notifications 20999492 and 21000111
8 EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On November 19, 2025, the inspectors presented the integrated inspection results to Eric Larson, Site Vice President, and other members of the licensee staff.
On July 17, 2025, the inspectors presented the REMP Exit/Debrief for Hope Creek and Salem inspection results to Eric Larson, Hope Creek Site Vice President, and David Sharbaugh, Salem 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 20997508 71111.05 Corrective Action Documents Resulting from Inspection 20997021 71111.11Q Corrective Action Documents Resulting from Inspection 20997872 21002528 71111.12 Corrective Action Documents Resulting from Inspection 20997578 20999301 71111.13 Corrective Action Documents Resulting from Inspection 20999638 20999469 71111.15 Corrective Action Documents 20996525 20997306 20998326 71111.20 Corrective Action Documents Resulting from Inspection 21001545 21001544 21001677 21003422 71111.24 Corrective Action Documents Resulting from Inspection 20997725 20997742 20997892 20997457 20997306
10 Inspection Procedure Type Designation Description or Title Revision or Date 20999022 21001138 Procedures HC.MD-PM.PB-0001 4.16 KV Breaker Cleaning and P.M.
31 OP-HC-103-106 Control Room Envelope Integrity 1
Work Orders 30312533 50226599 71152A Corrective Action Documents Resulting from Inspection 20997262 20997594 20998461 20998853 20999085 20999084 20999652 20999594 20999693 21000269 21000208 21000318 21000317 21000933 21000932 20998155 21000855 21000974 21000973 21000931 21001259 21001515 21003541 21003540 21003308 71153 Corrective Action Documents 21000840 21000838
11 Inspection Procedure Type Designation Description or Title Revision or Date 21000794 21000795 21000796 20999815 20999816 20999817 20999818 20999819 20999820 21000793 21000794 21000795 21000796