IR 05000255/2025004
| ML25260A036 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/17/2025 |
| From: | April Nguyen NRC/RGN-III/DORS |
| To: | Mlynarek M Palisades Energy |
| References | |
| IR 2025004 | |
| Download: ML25260A036 (1) | |
Text
SUBJECT:
PALISADES NUCLEAR PLANT - RESTART INSPECTION REPORT 05000255/2025004
Dear Mr. Michael Mlynarek:
On August 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Palisades Nuclear Plant. The enclosed inspection report documents the inspection results, which the inspectors discussed on September 9, 2025, with yourself and other members of your staff.
No violations of more than minor significance were identified during this inspection.
On June 13, 2022, Palisades ceased permanent power operations and subsequently removed all fuel from the reactor, as detailed in the letter from Entergy to the NRC, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel, (ADAMS Accession No. ML22164A067). On September 28, 2023, Holtec Decommissioning International, LLC (Holtec) submitted a letter to the NRC requesting exemptions from certain portions of the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.82(a)(2) to pursue the potential reauthorization of power operations at Palisades (ADAMS Accession No. ML23271A140).
On July 24, 2025, the NRC approved an exemption from the requirements of 10 CFR 50.82(a)(2), as detailed in the letter, Palisades Nuclear Plant - Exemption from the Requirements of 10 CFR 50.82(a)(2) Concerning the Prohibition to Operate and Emplace Fuel in the Reactor Vessel, (ADAMS Accession No. ML25163A182) and a set of licensing actions supporting reauthorization of Palisades Nuclear Plant. On August 25, 2025, Palisades notified the NRC that they rescinded their 10 CFR 50.82(a)(1) certification, which removed the prohibition on operation and emplacement of fuel in the reactor (ADAMS Accession No. ML25237A317). Palisades also implemented the set of licensing actions to support reimplementation of their operational licensing basis.
On August 25, 2025, the NRC transitioned oversight of Palisades to the Reactor Oversight Process (ROP).
September 17, 2025 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, April M. Nguyen, Lead Palisades Restart Team Division of Operating Reactor Safety Docket No. 05000255 License No. DPR-20 Enclosure:
As stated cc: Distribution via LISTSERV Signed by Nguyen, April on 09/17/25
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) performed inspection activities of the licensees performance associated with the return to an operational status.
List of Findings and Violations
None.
Additional Tracking Items
None.
PLANT STATUS
On August 25, 2025, Palisades notified the NRC that they rescinded their 10 CFR 50.82(a)(1)certification, which removed the prohibition on operation and emplacement of fuel in the reactor.
Palisades also implemented the set of licensing actions to support reimplementation of their operational licensing basis. On August 25, 2025, the NRC transitioned oversight of Palisades to the Reactor Oversight Process (ROP).
The NRC is conducting inspections to evaluate and assess the licensees activities for restoration to an operating status. The resident inspectors, as well as supplemental inspectors, continue to provide daily oversight of the restart activities occurring at the site.
The unit ended the inspection period in a defueled status.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the referenced 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.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01)
The inspectors evaluated system configurations during a partial walkdown of the following system/train:
- (1) emergency diesel generator (EDG) 1-2 during maintenance on EDG 1-1 on August 6, 2025
71111.07 - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01)
The inspectors observed and evaluated the licensees inspection and maintenance activities of the following heat exchanger:
- (1) component cooling water (CCW) heat exchanger E-54B from August 12, 2025 through August 22, 2025 71111.08P - Inservice Inspection Activities (PWR)
From July 1 through August 31, 2025, the inspectors observed and verified the licensees nondestructive examination (NDE) and repair/replacement activities of the reactor vessel closure head, Alloy 600 weld mitigation activities, and steam generator tube plugging, stabilization, and sleeving, conducted in accordance with the requirements of the ASME Code Section XI and other guidance documents. The purpose of these inspections was to verify that the reactor coolant system boundary, reactor vessel closure head, steam generators, and risk-significant piping system boundaries are appropriately monitored for degradation. The inspectors also verified that the examination results were thoroughly reviewed and appropriately evaluated, and that required corrective actions to address identified indications and defects are being appropriately implemented. During this quarter, the licensee conducted repair/replacement activities for the reactor vessel closure head, steam generator tubes, and Alloy 600 welds in the primary coolant system and in other areas. Further NRC inspections will monitor repair/replacement activities as they are conducted.
The inspectors verified that the following NDE and repair/replacement activities were conducted appropriately per the ASME Code or required standard, and that any potential indications and defects were identified and evaluated at the proper thresholds:
Nondestructive Examination and Welding Activities (IP Section 03.01)
- (1) reactor vessel inside surface ultrasonic examination Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
- (1) reactor head penetration Alloy 690 nozzle repair welds ultrasonic examinations
- (2) reactor head vent line repair welding Steam Generator Tube Inspection Activities (IP Section 03.04)
- (1) steam generators A and B tube sleeving and eddy current testing
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) risk management for work activities with the following equipment out of service:
EDG 1-1 maintenance outage; battery charger 1; CCW pump P-52A; fire pump P-9B; and service water pump P-7C during the work week of August 11, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)
The inspectors verified that the following outage activities important to safety were appropriately managed:
- (1) control of work activities and foreign material exclusion control during steam generator B nozzle dam installation on July 1, 2025
- (2) primary coolant pump P-50B motor heavy lift activities in containment and spent fuel pool areas during work from July 17, 2025, to August 13, 2025
- (3) main generator rotor heavy lift and installation activities on August 21, 2025 Additionally, the inspectors verified that the licensee managed fatigue by ensuring workers subject to the requirements in 10 CFR 26 Subpart 4 met all the requirements listed therein.
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)
- (1) post-maintenance testing following EDG 1-1 work window during the week of August 11, 2025 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02)
- (2) testing of FLEX pump P-1003 on August 27, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution The inspectors observed and evaluated the licensees performance during:
- (1) emergency preparedness exercise on July 29, 2025 OTHER BASELINE ACTIVITIES
71152 - Problem Identification and Resolution
System Return to Service During the inspection period, the inspectors continued reviews of Phases I and II of the licensees system return to service (SRTS) plans. The SRTS plans document licensee activities to verify that the configuration and condition of systems, structures, and components (SSCs)are consistent with the design and licensing bases to support potential restart. The inspectors reviewed Phases I and II of the SRTS plans, which include areas such as licensing and design-basis functions, system material conditions, reviewing open and deferred work prior to shutdown, and program applicability. The inspectors conducted these reviews using IP 71152, Problem Identification and Resolution, and IP 71111.21M, Comprehensive Engineering Team Inspection (CETI), as applicable.
The inspectors commenced reviews of the SRTS plans for the following systems:
- datalogger The inspectors completed initial reviews of the SRTS plans for the following systems:
- alternate shutdown panel
- containment isolations and penetrations
- containment air coolers
- digital electro-hydraulic controls
- spent fuel pool and auxiliary building HVAC These systems were selected based on the importance of the SSCs during normal and emergency plant operating conditions, risk significance and defense-in-depth of the SSCs specific functions and required work/modifications of the SSCs scheduled prior to potential restart.
The inspectors evaluated the initial SRTS plans for each system to identify if planned licensee activities will verify that the configuration and condition of the SSCs are consistent with the proposed operational design and licensing bases to support restart and verify readiness of the SSCs to support a return to service. The inspectors noted that the SRTS plans are intended to be living documents with a phased approach to SRTS. As the licensee progresses through the SRTS phases, the SRTS plans will undergo additional reviews by NRC inspectors to ensure appropriate SSC restoration and operability/functionality.
INSPECTION RESULTS
No additional inspection results.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 9, 2025, the inspectors presented the inspection results to M. Mlynarek, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SOP-22
Corrective Action
Documents
25011445
E-54B ECT Possibly Affected by Tube Cleanliness
08/20/2025
25010690
07/26/2025
CR 2024-3591
Rejectable PT Indications
2/17/2024
CR 2025-1653
Tube 105-112 (row-col) Sleeve Mid Expansion Inadvertently
Performed Twice
06/13/2025
Corrective Action
Documents
CR 2025-1661
Palisades SG A, 05H TSP Sleeve Mid Expansion
Inadvertently Performed Twice
06/11/2025
NDE Reports
180-9392377-000
Palisades Unit 1 Restart RPV ID Cladding Ultrasonic
Examination Final Report
54-ISI-619-001
Automated Ultrasonic Examination of Open Tube RPV
Closure Head Penetrations - Palisades Specific
Procedures
PAL 1 D28 ETSS
- 2
3-Coil + Point Examination Technique Specification Sheet
Corrective Action
Documents
25011236
Sinkhole Starting Near Walkway
08/14/2025
25011226
Rigging plan change for P-50B Motor installation
08/13/2025
Corrective Action
Documents
25011481
Main Generator Rotor Rigging Jacket Tear
08/21/2025
FHS-M-23
Movement of Heavy Loads in the Spent Fuel Pool Area
FHS-M-24
Movement of Heavy Loads in the Containment Building Area
MA-314
Movement of Heavy Loads in the Turbine Building
RFL-SG-2
S/G Primary Nozzle Dam Installation and Removal
Procedures
WI 00584410-06
Primary Coolant Pump Motor Receipt, Movement, and
Preoperational Checks
06/17/2025
25010759
Working Order Enhancements for FLEX Hale Pump
07/29/2025
25010942
Pin Hole Leak Found on Hale pump P-990
08/04/2025
25010946
Yr FLEX Pump Testing Not Completed
08/04/2025
25010960
Automatic Load Trip Setting Was Too Low
08/04/2025
25011229
EDG 1-1 Governor Oil Drop During SOP-22 Testing
08/14/2025
Corrective Action
Documents
25011239
DBA Load Exhaust Temperatures Missed During MO-7A-1
08/13/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
25011267
This CR is to Document the Replacement of EMB-0116D
(Q1) with a Q4 motor
08/14/2025
25011274
CK-DE412 OUTLET FITTING HAS LEAK
08/14/2025
25011278
XJ-802 Small Leak ~ 5 Drops A Minute
08/14/2024
25011286
Unexpected Alarm EK-0515
08/14/2025
OPS-201
Diverse and Flexible Coping Strategies (FLEX)
Program Document
OPS-203
Palisades FLEX Program Document
Procedures
SOP-22
00583510
FLEX Standby PM: K-1 FLEX Three Year Load Test (FSB A)
08/11/2025
00583511
FLEX Standby PM: K-2 FLEX Three Year Load Test
08/11/2025
00583512
FLEX Standby PM: P-990 Three Year Performance Test
(FSB B)
08/11/2025
Work Orders
00583513
FLEX Standby PM: P-1003 Three Year Performance Test
(FSB A)
08/27/2025
25010825
EP Graded Exercise Objective Unsatisfactory
07/30/2025
25010827
EP Graded Exercise Evaluation Criteria, N.2.3, Needs
Improvement
07/30/2025
25010828
EP Graded Exercise Objective Unsatisfactory
07/30/2025
25010830
EP Graded Exercise Evaluation Criteria Needs Improvement
07/30/2025
25010833
EP Graded Exercise Evaluation Criteria B.3.2 Needs
Improvement
07/30/2025
25010834
EP Graded Exercise Evaluation Criteria Needs Improvement
07/30/2025
25010835
EP Graded Exercise Evaluation Criteria I.1.5 Needs
Improvement
07/30/2025
Corrective Action
Documents
25010837
EP Graded Exercise Objective, K.2 Needs Improvement
07/30/2025
PLP-SRTSP-ASP
Alternate Shutdown Panel
PLP-SRTSP-CIS
Containment Isolations and Penetrations (Airlocks)
PLP-SRTSP-CRS
Containment Air Coolers System
PLP-SRTSP-DEH
Digital Electro-Hydraulic Controls
PLP-SRTSP-DTA
Datalogger
PLP-SRTSP-ELU
Miscellaneous
PLP-SRTSP-VAS
Spent Fuel Pool and Auxiliary Building HVAC
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