IR 05000255/2025006
| ML26030A166 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/02/2026 |
| From: | April Nguyen NRC/RGN-III/DORS |
| To: | Mlynarek M Palisades Energy |
| References | |
| IR 2025006 | |
| Download: ML26030A166 (0) | |
Text
SUBJECT:
PALISADES NUCLEAR PLANT - RESTART INSPECTION REPORT 05000255/2025006
Dear Michael Mlynarek:
On December 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 January 20, 2026, with yourself and other members of your staff.
No findings or 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 On August 25, 2025, Palisades notified the NRC that they rescinded their 10 CFR 50.82(a)(1) certification, which removed the prohibition on operation and emplacement of fuel in the reactor (ADAMS Accession No. ML25237A317).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.
February 2, 2026 On August 25, 2025, the NRC transitioned oversight of Palisades to the Reactor Oversight Process (ROP).
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 w/ encl: Distribution via GovDelivery Signed by Nguyen, April on 02/02/26
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) performed inspection activities of the licensees performance associated with the return to an operational status. As available, the NRC monitored the licensees performance by conducting an integrated inspection at Palisades Nuclear Plant, 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
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 https://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.
As available, 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 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
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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) Pre-Fire Plan 2 / Room 224: cable spreading room, elevation 607'-6" on December 3, 2025
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Partial)
The inspectors evaluated readiness and performance of:
(1)
(Partial)
E-60B, shutdown cooling heat exchanger, on December 23, 2025 71111.08P - Inservice Inspection Activities (PWR)
Vessel Upper Head Penetration Inspection Activities (IP Section 03.02) (1 Sample)
- (1) Reactor Vessel Closure Head (RVCH) bare metal visual examination
Steam Generator Tube Inspection Activities (IP Section 03.04) (1 Sample)
- (1) Steam generators A and B chemical cleaning
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Engineering Changes (ECs) 93737, 93739, and 93766, Operability Acceptance Documents to meet Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.8.5, Right Train DC Sources - Shutdown, TS LCO 3.8.8, Right Train Inverters - Shutdown, and TS LCO 3.8.10, Right Train Distribution Systems - Shutdown during movement of irradiated fuel
- (2) EC 93743, Operability Acceptance Review to meet TS LCO 3.7.10, Control Room Ventilation Filtration for right and left train control room HVAC and TS LCO 3.7.11 Control Room Ventilation Cooling for right train control room HVAC during movement of irradiated fuel
- (3) EC 93739, Operability Acceptance Review to meet TS LCO 3.8.2 AC Sources - Shutdown for Emergency Diesel Generator 1-2 and TS LCO 3.8.3 Diesel Fuel, Lube Oil and Starting Air for Emergency Diesel Generator 1-2 during movement of irradiated fuel
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) EC 93764, Installation of portable air compressors to support compressor C-2A/B/C replacement
- (2) EC 93508, Permanent Primary Coolant System Cold Leg Safety Injection Nozzle Thermal Sleeve Removal
- (3) EC 93369, Temporary removal of component cooling water valves CV-0977B and CV-0944 to support alternate spent fuel pool cooling permanent modification
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 Sample)
- (1) Work Order (WO) 598521-01, Post-maintenance testing of diesel fire pump P-9B following alternator replacement on November 5, 2025
Surveillance Testing (IP Section 03.01) (1 Sample)
- (1) RI-59C, LTOP pressure transmitter calibrations, on December 4, 2025
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructed workers on radiological hazards and the radiation protection requirements for flushing and opening of the shutdown cooling heat exchanger.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Sample)
The inspectors evaluated the licensees control of radiological hazards for the following radiological work:
- (1) Flushing and opening of the shutdown cooling heat exchanger
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) HEPA ventilation established for the shutdown cooling heat exchanger eddy current testing Use of Respiratory Protection Devices (IP Section 03.03) (1 Partial)
(1)
(Partial)
The inspectors observed issuance and use of powered air purifying respirators for shutdown cooling heat exchanger work
71124.04 - Occupational Dose Assessment
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situations:
- (1) Lapel air sampler use for shutdown cooling heat exchanger work 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 and associated topics. 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 continued reviews of the SRTS plans for the following topics:
- Environmental qualification of components
- Reactor vessel and reactor vessel internals
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 20, 2026, 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
Fire Plans
Pre Fire Plans Manual
Corrective Action
Documents
25015224
E-60B Shutdown Heat Exchanger Channel Cover Weight
2/15/2025
Corrective Action
Documents
25-3693
Palisades RVCH: All CRDM Ext. Nozzles Having Issues
Being Installed
2/06/2025
NDE Reports
Bare Metal Visual Examination of RVCH Surface
2/15/2025
Procedures
03-9398550
Palisades Steam Generator Cleaning Sequence Control
Procedure
000
00589951-25
E-50A: Perform Steam Generator Secondary Chemical
Cleaning
10/13/2025
Work Orders
00589951-35
E-50B: Perform Steam Generator Secondary Chemical
Cleaning
11/18/2025
Corrective Action
Documents
PMCR 25014377
Frequency Change for 72-18 and 72-28
11/13/2025
System Operability Acceptance TS LCO 3.8.2, AC
Sources - Shutdown (Right Train)
System Operability Acceptance for TS LCO 3.8.5,
DC Sources - Shutdown (Right Train)
System Operability Acceptance, CRV - A/B Filtration and
B Cooling Trains
System Operability Acceptance for TS LCO 3.8.8,
Inverters - Shutdown (Right Train)
Operability
Evaluations
System
Operability
Acceptance
Emergency Diesel Generator K-6B (EDG 1-2) LCO 3.8.2 &
Fuel Oil System (FOS) LCO 3.8.3
Procedures
Admin 4.11
Safety Function Determination Program
25014179
Questions Raised Prior to CCW System Tagging
11/08/2025
Corrective Action
Documents
25014189
Component Cooling Water System Alignment
11/09/2025
PCS Cold Leg Safety Injection Nozzle Thermal Sleeve
Removal
Engineering
Changes
Temporary Installation of Portable Air Compressors to
Support Compressor C-2A/B/C
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Replacement
Procedures
03-9393324
Palisades Cold Leg Safety Injection Nozzle Thermal Sleeve
Removal
25014044
P-9B Diesel Driven Fire Pump Outside of Normal Speed
Range
11/04/2025
Corrective Action
Documents
25014926
Low Temperature Over Pressure Transmitter PT-0104B
Out of As Found Tolerance
2/04/2025
MO-7B
Fire Water Pumps P-9A, P-9B, and P-41
Procedures
RI-59C
LTOP Pressure Transmitter Calibrations
2957096-01
RI-59C LTOP Pressure Transmitter Calibrations
2/04/2025
Work Orders
598521-01
Troubleshoot CR#25010331 P-9B Diesel Fire Pump Tripped
11/05/2025
ALARA Plans
25-0574
25-2283
Flush of Shutdown Cooling Heat Exchanger
2/04/2025
25-2352
Demobilization of Shutdown Cooling Heat Exchanger Drain
Pipe
2/12/2025
Radiation
Surveys
25-2405
West Safeguards
2/22/2025
Radiation Work
Permits (RWPs)
250574
Eddy Current Inspections on E-60B Shutdown Cooling Heat
Exchanger
Engineering
Evaluations
51-9392765-000
Corrosion Evaluation for Palisades Reactor Vessel Cladding
Indications
09/08/2025