IR 05000331/2025002
| ML25345A204 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/11/2025 |
| From: | April Nguyen NRC/RGN-III/DORS |
| To: | Wheaton R NextEra Energy Duane Arnold |
| References | |
| IR 2025002 | |
| Download: ML25345A204 (0) | |
Text
SUBJECT:
DUANE ARNOLD ENERGY CENTER - RESTART INSPECTION REPORT 05000331/2025002
Dear Ray Wheaton:
On August 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed inspections at Duane Arnold Energy Center. The enclosed inspection report documents these inspection results, which the inspectors discussed on September 10, 2025, with Justin Both and other members of your staff.
Due to the temporary cessation of government operations, which commenced on October 01, 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 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
No violations of more than minor significance were identified during this inspection.
December 11, 2025 On August 27, 2020, Duane Arnold ceased permanent power operations as detailed in the letter from NextEra to the NRC, Certification of Permanent Cessation of Power Operations, (Agencywide Document Access and Management System (ADAMS) Accession No. ML20240A067). On October 12, 2020, NextEra removed all fuel from the reactor, as detailed in the letter from NextEra to the NRC, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center, (ADAMS Accession No. ML20286A317). On January 23, 2025, NextEra 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 Duane Arnold (ADAMS Accession No. ML25023A270). The NRCs initial acceptance to review Duane Arnolds request for exemptions was documented in ADAMS at Accession No. ML25056A149 on February 27, 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. 05000331 License No. DPR-49 Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Nguyen, April on 12/11/25
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) performed inspections of the licensees activities to verify radiation safety activities were appropriately performed, work activities were appropriately planned and executed with safety measures in place for heavy lifts, and preliminary onsite in-vessel visual inspection (IVVI) activities.
List of Violations No violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
The Duane Arnold Energy Center ceased power operations and subsequently removed all fuel from the reactor, as certified in a letter to the NRC on October 12, 2020. On January 23, 2025, NextEra submitted a letter to the NRC requesting exemptions from certain portions of the requirements of 10 CFR 50.82(a)(2) to pursue the potential reauthorization of power operations.
The NRC is conducting inspections to evaluate and assess the licensees activities for potential restoration to an operational 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
CORNERSTONES
71111.08G - Inservice Inspection Activities (BWR)
Nondestructive Examination and Welding Activities (IP Section 03.01)
From June 2 to June 27, 2025, the inspectors observed and verified Duane Arnolds nondestructive examination (NDE) activities of the reactor pressure vessel (RPV) conducted in accordance with the requirements of the American Society of Mechanical Engineers (ASME)
Code Section XI and BWRVIP-03, BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines, Revision 21. The purpose of these inspections was to verify that the reactor coolant system boundary, reactor vessel internals, and risk-significant piping system boundaries are appropriately monitored for degradation. The NRC inspectors also verified that the examination results were thoroughly reviewed and appropriately evaluated, and that required corrective actions to address identified indications and defects will be appropriately implemented. During this inspection period, Duane Arnold completed the NDE activities and evaluation of the data. Further NRC inspections will occur as additional activities are conducted.
The inspectors verified that the following nondestructive examination 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:
BWRVIP Reactor Internals Exams
- visual examination (VT) of core spray header piping welds, core spray header piping brackets, core spray sparger brackets, and upper and lower core spray sparger welds (BWRVIP-18)
- VT of upper and lower guide rod brackets and feedwater sparger end bracket attachment welds (Cat. B-N-2, Item B13.30)
- dye penetrant examination (PT) of control rod drive housing welds (Cat. B-O, Item B14.10)
71111.20 - Refueling and Other Outage Activities
Heavy Lifts (IP Section 03.01)
From March 25 to March 26, 2025, inspectors reviewed the licensees control of heavy loads program to ensure that lifts were performed in accordance with regulatory requirements and applicable industry standards. Since fuel has been removed from the facility, the licensee has eliminated their previous licensing basis requirements associated with the control of heavy loads program. However, the inspectors observed that the licensee generally continued to perform critical lifts in accordance with the previously established control of heavy loads program. Specifically, the inspectors reviewed documents associated with the inspection and testing of the reactor building overhead crane, slings, and special lifting devices for critical lifts within the reactor building.
The licensee identified one deviation from the previously established procedure.
However, the control of heavy loads requirements was not applicable in the current plant configuration. Specifically, there is no longer heating within the reactor building. The reactor building crane had a previously established minimum operating temperature for single failure proof lifts. During this evolution, the lift was going to be performed at a temperature below the cranes previously established limit. The licensee recognized this gap and implemented the required action to re-perform NDE on critical areas of the crane prior to any critical lifts associated with controlling heavy loads in the future. The licensee documented this observation in Condition Report CR 2510971, RB Crane Operation at Lower Temperatures, dated March 20, 2025.
From March 31 to April 2, 2025, inspectors observed on-site activities and preparations for the licensees lift of the RPV head. The inspectors assessed the RPV head lift operations via direct observation on the refuel floor. The inspectors attended the pre-job brief prior to the evolution, observed the rigging of the RPV head, and the load lift from the reactor cavity to the refuel floor.
RADIATION SAFETY
CORNERSTONE From March 25 through July 18, 2025, the inspectors conducted on-site inspection activities to assess the radiological protection program. These inspections were conducted during several radiological activities that utilized various aspects of the licensees radiation protection program.
These activities included entry into the drywell, reactor vessel disassembly, in-vessel inspections, and removal of several control rod mechanisms.
The inspectors performed walkdowns of the facility to assess radiological controls, including posting and labeling of radioactive material storage areas, High Radiation Areas (HRAs), and contamination areas. The inspectors noted that the labels for containers holding radioactive material had not been updated to reflect reduced dose rates and contamination levels based on 5 years of decay. In addition, the inspectors identified the door that had held the radiation area sign for the reactor building had been removed, and no new sign was posted at the access.
The inspectors concluded this was a minor violation of 10 CFR 20.1902(a), which requires that licensees post each radiation area with a conspicuous sign or signs bearing the radiation symbol and the words CAUTION, RADIATION AREA. The licensee immediately placed an appropriate posting to correct the issue. In addition, the inspectors observed workers monitoring out of the Radiologically Controlled Area (RCA). Although workers generally adhered to site procedures, the inspectors observed one instance in which an individual used a monitor to release a drill, contrary to site procedures. However, this drill had not been used on any equipment in the RCA, and the inspectors determined the survey that was performed was adequate and that no violation of NRC requirements occurred. The inspectors shared this observation with the licensee as an example of establishing clear expectations for the workforce.
The inspectors also observed and reviewed various radiological surveys that were conducted to support activities. The surveys observed included dose rate measurements, contamination surveys, and airborne radioactivity surveys. In addition to the observation of radiological surveys, the inspectors reviewed calibration records and routine source checks of various radiation detection instrumentation.
The inspectors observed several evolutions that included the use of temporary ventilation systems and respiratory protection to limit the intake of airborne radioactive material. The inspectors assessed whether breathing air systems provided respirable air, that individuals were qualified to wear respirators, and that the respirators were utilized appropriately. The inspectors noted that although the sites procedure discussed establishing breathing air pressure for airline respirators, none of the pressures in the procedure were above the minimum pressure that the vendor manual stated was required for the make/model being used. The inspectors brought this concern to the attention of the licensee. After reviewing the information, the licensee assessed the capability of their breathing air system to ensure it could accommodate the higher pressure and performed an emergent change to their procedure to increase the required pressure to align with the vendor manual prior to use of these respirators. The licensee also initiated an action to review the respiratory protection procedure in full.
In addition to observing activities to limit the intake of radioactive material, the inspectors observed many aspects of the program designed to control the amount of external radiation exposure received. This included observation of real-time, remote monitoring of accumulated dose via a telemetry system, use of routine electronic dosimetry monitoring, and use of extremity dosimetry.
In addition to observing activities related to occupational radiation safety, the inspectors reviewed aspects of gaseous effluent releases. In preparation for entering the drywell, the facility reinitiated the standby gas treatment (SBGT) system, which had been removed from service since the shutdown, and revised the decommissioning offsite dose assessment manual (DODAM) to reflect this change. The inspectors reviewed the changes to the DODAM and walked down accessible portions of the SBGT system, including the filter trains, to verify the system was in-tact and functioning. In addition, the inspectors reviewed effluent sampling results and subsequent dose calculations performed for periods in which SBGT was in operation. The inspectors also reviewed a routine liquid effluent release sample and analysis.
The inspectors conducted these reviews using IP 71124.01, Radiological Hazard Assessment and Exposure Controls, 71124.03, Airborne Radioactivity, 71124.04, Occupational Dose Assessment, 71124.05, Radiation Monitoring Instrumentation, and 71124.06, Radioactive Gaseous and Liquid Effluent Treatment, as applicable.
INSPECTION RESULTS
No violations of more than minor significance were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On September 10, 2025, the inspectors presented the inspection results to Justin Both, Director of Restart Construction, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NDE Reports
180-9394693-000
Duane Arnold Energy Center Unit 1 Restart Project IVVI
Final Report Summer 2025
08/19/2025
NDE Reports
GARN1-RFO25-
29970
In Vessel Visual Inspection (IVVI) of Reactor Pressure
Vessel Internal Components Duane Arnold Energy Center:
Refueling Outage (RFO) 25
10/20/2016
Procedures
BWRVIP Administrative Document
Procedures
Augmented Inspection Administrative Document
Procedures
54-ISI-173-008
ASME Section XI Examination Coverage
Procedures
54-ISI-30-030
Written Practice for the Qualification and Certification of NDE
Personnel for ASME BPVC Section XI
Procedures
54-ISI-363-011
Remote Visual Examination of Reactor Pressure Vessel
Internals, Components, and Associated Repairs in Boiling
Water Reactors
Procedures
54-ISI-650-002
ASME Section XI Flaw Characterization
Procedures
ACP 1211.36
Reactor Pressure Vessel Inspection Procedure 71111.20
Corrective Action
Documents
2510971
RB Crane Operation at Lower Temperatures
03/20/2025
Work Orders
41002152-01
Reactor Building Crane Periodic Inspection and Lubrication
03/26/2025
Work Orders
41002152-02
Perform NDE on Critical Welds on Bridge
03/20/2025
Work Orders
41002152-03
Tool E189 Five-Year QC NDE and Dimensional Examination
03/26/2025
Work Orders
41002152-04
Tool-E190A: Five-year QC NDE and Dimensional
Examination
03/20/2025
Work Orders
41002152-05
Tool-E195 Inspect Remote Shield Block Lifting Device
03/20/2025
Work Orders
41002152-06
Tool E199: Perform Five-year QC NDE of Critical Welds
03/20/2025
Work Orders
41002152-07
Tool E198: Five-Year QC NDE and Dimensional
Examination
03/20/2025
Work Orders
41002152-08
Inspect Slings
2/24/2025
ALARA Plans
IVVI, Blade Inspection, OD and ID, Unlatching Drives
ALARA Plans
Under Vessel Work to Include PIPs, De-Torque, Drive Pull,
Blank Flange and All Support Activities
Corrective Action
Documents
2517240
NRC Identified: Missing Radiation Area Posting
06/11/2025
Resulting from
Inspection
Corrective Action
Documents
Resulting from
Inspection
2517354
Worker Used SAM/TEM to Free Release Tool
06/12/2025
Miscellaneous
Work Checklist for CRD Removal
05/28/2025
Procedures
ACP 1411.23
Equipment and Material Controls in Radiologically Controlled
Areas
Procedures
Alpha Monitoring
Radiation
Surveys
DA-M-20250319-
Dry well
03/19/2025
Radiation
Surveys
HP048
Air Sample Record for Reactor Cavity
03/26/2025
Radiation
Surveys
PDA-M-
201005-7
Reactor Cavity
10/05/2020
Radiation
Surveys
PDA-M-
201006-3
Reactor Cavity
10/06/2020
Radiation
Surveys
PDA-M-
250319-2
Drywell
03/19/2025
Radiation
Surveys
PDA-M-
250326-1
Reactor Cavity Initial Entry
03/26/2025
Radiation
Surveys
PDA-M-
250326-2
Reactor Cavity After Drywell Head Removal
03/26/2025
Radiation
Surveys
PDA-M-
250611-1
RB5 Routine
06/11/2025
Radiation Work
Permits (RWPs)
25-0008
Routine Security and Firewatch Entries
Radiation Work
Permits (RWPs)
25-0051
Routine Work and Inspections
Radiation Work
Permits (RWPs)
25-0112
Refuel Floor Work
Radiation Work
Permits (RWPs)
25-3016
Restart: Refuel Pool Work
Radiation Work
Permits (RWPs)
25-4009
DFO-All Drywell Work Activities
Radiation Work
Permits (RWPs)
25-4040
Restart: CRD Project Support
Corrective Action
Documents
Resulting from
Inspection
2519722
NRC Inspector Found a Respiratory Protection Procedure
Error
07/17/2025
Miscellaneous
Honeywell North Air-Fed Suits - Mururoa MTH2 Technical
Information
N/A
Miscellaneous
NRC Approval of Request From L-HU-05-010
2/28/2005
Miscellaneous
Approval for Use of Delta Protection Mururoa V4F1 R
Supplied Air Suites Requested in L-2009-072
08/31/2009
Miscellaneous
CC8414X2T-US
Mururoa MTH2 US Ventilated Protective Clothing
User Guide
G
Miscellaneous
Request for Use of Delta Protection Mururoa V4F1 R
Supplied Air Suites
04/28/2009
Miscellaneous
Request for Approval of Use of Delta Protection Respiratory
Protection Equipment
10/20/2005
Procedures
ACP 1411.20
Respiratory Protection
Procedures
HPP 3106.05
Breathing Air Quality Assurance Test
Calibration
Records
Calibration record for Canberra Sirius-5PBG
Serial Number 2502-034-SRC5PGB
03/25/2025
Calibration
Records
Calibration record for Canberra Sirius-5PBG
Serial Number 2502-035-SRC5PGB
03/25/2025
Calibration
Records
Calibration of the Mirion Fastscan WBC System
04/25/2025
Calibration
Records
Dosimeter 082373 Calibration Report
09/05/2025
Calibration
Records
Dosimeter 097860 Calibration Report
09/05/2024
Calibration
Records
Dosimeter 840570
Calibration Report
06/04/2024
Calibration
Records
Dosimeter 968669
Calibration Certificate
01/15/2025
Calibration
Records
Dosimeter 969048
Calibration Certificate
01/15/2025
Calibration
AMS-4 IES HP1115 Certificate of Calibration
03/18/2025
Records
Corrective Action
Documents
Resulting from
Inspection
2517240
HPP 3110.87 - Calibration of the ARGOS 5AB Personnel
Monitor
06/11/2025
Procedures
HPP 3110.87
Calibration of the ARGOS 5AB Personnel Contamination
Monitor
Miscellaneous
Defueled Offsite Dose Assessment Manual
Work Orders
40988324
Gaseous Effluent Sampling and Analysis
06/11/2025
Work Orders
40989742
Effluent Tritium Sampling and Analysis
06/23/2025
Work Orders
41008685
In-Leakage Liquid Effluent Release Through Dilution
Structure
03/12/2025