IR 05000331/2024001
| ML24319A145 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/15/2024 |
| From: | Dave Hills NRC/RGN-III/DRSS |
| To: | Both J NextEra Energy Duane Arnold |
| References | |
| IR 2024001 | |
| Download: ML24319A145 (1) | |
Text
SUBJECT:
DUANE ARNOLD ENERGY CENTER - NRC INSPECTION REPORT NO. 05000331/2024001
Dear Justin Both:
On October 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Duane Arnold Energy Center (DAEC). On October 31, 2024, the NRC inspectors discussed the results of this inspection with Justin Both, Decommissioning Director, and other members of your staff. The results of this inspection are documented in the enclosed report.
During the inspection period, the NRC inspector reviewed the following aspects of onsite activities: safety reviews, design changes and modifications; problem identification and resolution; fire protection; decommissioning performance; occupational radiation exposure; radiological surveys; radioactive waste treatment, effluent, and environmental monitoring; material control and accounting; and waste management and transportation. The inspection consisted of an examination of activities at the site as they relate to safety and compliance with the Commissions rules and regulations.
No violations of more than minor safety significance were identified during this inspection.
November 15, 2024 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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, David E. Hills, Chief Decommissioning, Reactor, and ISFSI HP Branch Division of Radiological Safety and Security Docket No: 50-331 License No: DPR-49
Enclosure:
IR Nos. 05000331/2024001
REGION III==
Docket No:
50-331 License No:
DPR-49 Report No:
05000331/2024001 Licensee:
NextEra Energy Duane Arnold, LLC Facility:
Duane Arnold Energy Center (DAEC)
Location:
Palo, IA Dates:
March 26, 2024, to October 31, 2024 Inspectors:
Peter J. Lee, Ph.D., CHP, Reactor Inspector Approved by:
David E. Hills, Chief Decommissioning, Reactor, and ISFSI HP Branch Division of Radiological Safety and Security
EXECUTIVE SUMMARY Duane Arnold Energy Center NRC Inspection Report No. 050000331/2024001 This U.S. Nuclear Regulatory Commission (NRC) inspection was a routine, announced inspection of decommissioning activities being conducted at the facility. A brief summary of the areas reviewed are described below. Based on the results of the inspection no violations of more than minor safety significance were identified.
Safety Reviews, Design Changes, and Modifications
The licensee had not performed any changes to the decommissioning facility that warranted a safety evaluation per Title 10 of the Code of Federal Regulations (CFR) 50.59.
Problem Identification and Resolution
Issues were identified by the licensee at appropriate thresholds and entered into the Corrective Action Program (CAP). Issues were screened and prioritized commensurate with safety significance. Licensee evaluations determined the significance of issues and included appropriate remedial corrective actions.
An effective decommissioning Fire Protection Program was maintained and implemented that reasonably prevented fires; provided the capability to rapidly extinguish fires that could result in radiological hazards; and ensured the risk of fire-induced hazards to the public, environment, and plant personnel were minimized.
Decommissioning Performance and Status Review
The inspectors determined that decommissioning activities were in accordance with the regulatory requirements.
Occupational Radiation Exposure Adequate protection of worker health and safety from exposure to radiation and radioactive material was provided. Decommissioning activities were executed in general alignment with planning documents and as provided in Radiation Work Permits (RWPs) and As Low As Is Reasonably Achievable (ALARA) reviews. Radiation surveys were performed adequately to identify the hazards present.
Radioactive Waste Treatment, and Effluent and Environmental Monitoring
The liquid and gaseous effluent sampling program was effective at quantifying radioactive effluent releases and the radiological environmental monitoring program (REMP) and groundwater protection initiative (GPI) were implemented in accordance with applicable procedures.
Material Control and Accounting at Decommissioning Reactors
The licensees program was intended to control and account for all special nuclear material (SNM) on-site, as well as detect any loss or unauthorized diversion of SNM in a timely manner. The licensee had implemented an adequate program to inventory and control the SNM on-site. Overall, the licensee had implemented the Material Control and Accounting (MC&A) program in accordance with the regulations.
Solid Radioactive Waste Management and Transportation of Radioactive Materials
The licensee effectively processed, handled, stored, and transported radioactive material.
Report Details Summary of Plant Activities Duane Arnold Energy Center (DAEC) is a permanently shut-down and defueled power reactor maintained in a Safe Storage (SAFSTOR) condition and no major decommissioning activities occurred. Since the last NRC inspection of DAEC, the licensee continued to conduct the effluent release monitoring and ground water monitoring.
1.0 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors (IP 37801)
1.1 Inspection Scope The purpose of this portion of the inspection was to verify that the licensees safety review process was in accordance with the requirements of 10 CFR 50.59, Changes, tests, and experiments such that license amendments were obtained when required.
1.2 Observations and Findings During the inspection, the inspector confirmed there were no changes to the decommissioning facility that required a safety evaluation according to the provisions of 10 CFR 50.59.
No findings of significance were identified.
.
1.3 Conclusions The licensee had not performed any changes to the decommissioning facility that warranted a safety evaluation per 10 CFR 50.59.
2.0 Problem Identification and Resolution at Permanently Shutdown Reactors (IP 40801)
2.1 Inspection Scope The purpose of this portion of the inspection was to evaluate 1) the effectiveness of licensee controls to identify, resolve, and correct issues, 2) the audit and assessment programs, and 3) management reviews of the safety conscious work environment.
2.2 Observations and Findings The inspector reviewed all issues entered into the licensees CAP since the last inspection. The issues reviewed were found to be appropriately addressed by the licensee. There were no issues requiring reporting under 10 CFR Part 21. Audits were performed consistent with a prepared schedule and in accordance with the Quality Assurance Topical Report and NRC requirements. The inspectors interviewed station personnel during walkdowns and did not encounter any concerns with safety culture.
No findings of significance were identified.
2.3 Conclusions Issues were identified by the licensee at appropriate thresholds and entered into the CAP. Issues were screened and prioritized commensurate with safety significance.
Licensee evaluations determined the significance of issues and included appropriate remedial corrective actions.
3.0 Fire Protection Program at Permanently Shutdown Reactors (IP 64704)
3.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the effectiveness of the fire protection program to ensure adequate protection from fire-induced release of radioactive material.
3.2 Observations and Findings The inspector reviewed the record of monthly and annual testing of fire extinguishing equipment to verify the location and integrity of all fire extinguishers at the facility. The inspector confirmed during walkdowns that the fire extinguishers were available, maintained, and located as indicated in the approved pre-fire plans. The personnel were provided training on the use of fire extinguishers.
No findings of significance were identified.
3.3 Conclusions An effective decommissioning Fire Protection Program was maintained and implemented that reasonably prevented fires; provided the capability to rapidly extinguish fires that could result in radiological hazards; and ensured the risk of fire-induced hazards to the public, environment, and plant personnel were minimized.
4.0 Decommissioning Performance and Status Review (IP 71801)
4.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the status of decommissioning and to verify the decommissioning activities are in accordance with regulatory and license requirements.
4.2 Observations and Findings During the period of inspection, the inspector performed walkdowns of the plant. The general condition of the facility was found to be well maintained and consistent with good housekeeping practices. The postings and boundaries for the contamination control were well maintained. The inspector observed that the effluent filtration and monitoring systems were in working condition.
No findings of significance were identified.
4.3 Conclusions The inspectors determined that decommissioning activities were in accordance with the regulations and license requirements.
5.0 Occupational Radiation Exposure at Permanently Shutdown Reactors (IP 83750)
5.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the effectiveness of the licensees occupational radiation safety program to adequately protect worker health and safety from exposure to radiation or radioactive material.
5.2 Observations and Findings The inspector reviewed the licensees dosimetry records, As Low As Is Reasonably Achievable (ALARA) Plans, and Radiation Work Permit (RWPs). All personnel were appropriately monitored and the RWPs were followed by licensee personnel during the performance of the assigned tasks.
The inspector reviewed the calibration records of all radiation survey instruments and observed the source check of calibration. The inspector also interviewed the licensee personnel to discuss the calibration procedures. The licensee performed the source check of calibration in accordance with the approved procedures.
No findings of significance were identified.
5.3 Conclusions Adequate protection of worker health and safety from exposure to radiation and radioactive material was provided. Decommissioning activities were executed in general alignment with planning documents and as provided in RWPs and ALARA reviews.
Radiation surveys were performed adequately to identify the hazards present.
6.0 Radioactive Waste Treatment, and Effluent and Environmental Monitoring (IP 84750)
6.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the effectiveness of the licensees liquid and gaseous effluent sampling program to quantify radioactive effluent releases and to verify that the radiological environmental monitoring program and groundwater protection initiative were effectively implemented.
6.2 Observations and Findings The inspector noted during a review of past annual radiological effluent release and environmental monitoring reports that no anomalous results, unexpected trends, or abnormal releases were identified in association with plant activities.
The inspector performed calibration check of the germanium detector used to analyze samples collected from effluent releases.
The licensees calculations for assessing doses to a member of the public were consistent with approved Defueled Offsite Dose Assessment Manual (DODAM)
methodologies. The inspector assessed the isotopic analysis of the contents discharged, and independently performed calculations in accordance with the DODAM to verify the licensees results.
The review of sampling results of gaseous effluent release of 2024 did not indicate any licensed materials. The liquid waste was only generated from the ground water leaking into the contaminated floor drains in the plant and collected in the collection tanks. The licensee was recirculating the liquid waste in the collection tank through filtration system until the concentrations met the DODAM dose criteria prior to release through dilution flow path to the river. During the inspection, the inspector reviewed the analytical results of water samples from collection tanks and determined that the concentrations met the DODAM dose criteria for the effluent release.
No findings of significance were identified.
6.3 Conclusions The liquid and gaseous effluent sampling program was effective at quantifying radioactive effluent releases and the radiological environmental monitoring program (REMP) and groundwater protection initiative (GPI) were implemented in accordance with applicable procedures.
7.0 Material Control and Accounting at Decommissioning Reactors (IP 85103)
7.1 Inspection Scope The inspectors reviewed the licensees Material Control and Accounting (MC&A)
program to determine whether the licensee implemented and maintained an adequate and effective program to control and account for the special nuclear material (SNM) in its possession. The inspectors review included assessment of the licensees ability to detect loss or theft of SNM in a timely manner.
7.2 Observations and Findings The inspectors verified that physical inventories of SNM were conducted every 12 months and examined the content of the most recent inventory report. The fuel SNM was contained in dry shield canister stored at ISFSI facility. The inspector verified that the non-fuel SNM were securely stored in low level waste building item control area.
The amount of non-fuel SNM on-site is 0.067 grams, which is below the one gram reportable quantity requirement as per 10 CFR 70. This amount of SNM includes the neutron detectors that are in storage, and plutonium sources for health physics instrument calibration purposes.
No findings of significance were identified.
7.3 Conclusions The licensees program was intended to control and account for all SNM on-site, as well as detect any loss or unauthorized diversion of SNM in a timely manner. The licensee had implemented an adequate program to inventory and control the SNM on-site.
Overall, the licensee had implemented the MC&A program in accordance with the regulations 8.0 Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP 86750)
8.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the effectiveness of the licensees programs for processing, handling, storage, and transportation of radioactive material.
8.2 Observations and Findings During the period of inspection, the inspectors toured the Radwaste Processing and Storage Facility and found the radiological postings to be accurate and the material in storage was labeled appropriately.
The inspector reviewed the sealed source inventory and verified the sources were secured and located in the plant as indicated by records. The licensee performed the inventories and leak tests in accordance with the approved procedures, and no leakage was detected.
The licensee transported the TriNuclear filtration system to Seabrook Nuclear Station.
The inspector reviewed the manifest of the shipment. Based on the characterization of the radioactive materials, this was a surface contaminated object (SCO)-II shipment. The inspector also reviewed the radiation survey of the shipment.
No findings of significance were identified.
8.3 Conclusions The licensee effectively processed, handled, stored, and transported radioactive material.
9.0 Exit Meeting The inspector presented the results of the inspection to Justin Both and other members of the DAEC staff at an exit meeting on October 31, 2024. The licensee acknowledged the results presented and did not identify any of the information discussed as proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED J. Both, Decommissioning Director T. Weaver, Licensing Manager M. Casey, Radiation and Chemistry Manager INSPECTION PROCEDURES (IPs) USED IP 37801 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors IP 40801 Problem Identification and Resolution at Permanently Shutdown Reactors IP 64704 Fire Protection Program at Permanently Shutdown Reactors IP 71801 Decommissioning Performance and Status Reviews at Permanently Shutdown Plants IP 83750 Occupational Radiation Exposure IP 84750 Radioactive Waste Treatment, and Effluent and Environmental Monitoring IP 85103 Material Control and Accounting at Decommissioning Reactors IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials ITEMS OPENED, CLOSED, AND DISCUSSED Opened Type Summary None Closed Type Summary None
PARTIAL LIST OF DOCUMENTS REVIEWED Licensee documents reviewed and utilized during the course of this inspection are specifically identified in the Report Details LIST OF ACRONYMS USED ALARA As Low As Is Reasonably Achievable CAP Corrective Action Program CFR Code of Federal Regulations DAEC Duane Arnold Energy Center DRSS Division of Radiological Safety and Security DODAM Defueled Offsite Dose Assessment Manual MC&A Material Control and Accounting NRC U.S. Nuclear Regulatory Commission PCM Personnel Contamination Monitor PSDAR Post Shutdown Activities Report REMP Radiological Environmental Monitoring Program RWP Radiation Work Permit SCO Surface Contaminated Object SAFSTOR Safe Storage SNM Special Nuclear Material