IR 05000010/2024001
| ML24366A134 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/31/2024 |
| From: | Dave Hills NRC/RGN-III |
| To: | Joseph C Constellation Energy Generation |
| References | |
| IR 2024001 | |
| Download: ML24366A134 (1) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNIT 1 - NRC INSPECTION REPORT NO. 05000010/2024001
Dear Carolyne Joseph:
On Dec 12, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Unit 1. On December 12, 2024, the NRC inspectors discussed the results of this inspection with Roger Bauman, 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.
December 31, 2024
C. Jospeh
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: 50-010 License No: DPR-2
Enclosure:
IR Nos. 05000010/2024001
REGION III==
Docket No:
50-010 License No:
DPR-2 Report No:
05000010/2024001(DRSS)
Licensee:
Constellation Energy Generation, LLC Facility:
Dresden Nuclear Power Station, Unit 1 Location:
Morris, Illinois Dates:
January 02, 2024, to December 12, 2024 Inspectors:
Peter Lee, PhD, CHP, Reactor (Decom) Inspector Approved by: David E. Hills, Chief Decommissioning, Reactor, and ISFSI HP Branch Division of Radiological Safety and Security
EXECUTIVE SUMMARY Dresden Nuclear Power Station, Unit 1 NRC Inspection Report Nos. 05000010/2024001 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 detect, control, and 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 Permit (RWP) and as low as reasonably achievable (ALARA) reviews. Radiation surveys were performed adequately to identify the hazards present.
Radioactive Waste Treatment, and Effluent and Environmental Monitoring
This program is inspected by the NRC through the Reactor Oversight Process (ROP) for Unit 2 and Unit 3.
Material Control and Accounting at Decommissioning Reactors
The licensee didnt possess any Unit 1 special nuclear materials (SNM).
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 Dresden Nuclear Power Station, Unit 1 is a permanently shut-down and defueled power reactor maintained in a Safe Storage (SAFSTOR) condition and no major decommissioning activities occurred. During this inspection period, the licensee performed routine housekeeping and maintenance activities for Unit 1. There is no fuel in the spent fuel pool and the Unit 1 is co-located with Dresden Unit 2 and Unit 3 which are currently operating.
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 The inspector reviewed the licensees 10 CFR 50.59 screening questions and the requirements of safety evaluation of facility changes. The inspector determined that there were no changes required a 50.59 safety evaluation.
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 corrective action program (CAP) since the last inspection. The inspector determined that issues were identified by the licensee at an appropriate threshold within various functional areas of the site and entered into the CAP. Issues were effectively screened, prioritized, and evaluated commensurate with safety significance. The scope and depth of evaluations were adequate in that the evaluations reviewed addressed the significance of issues and assigned an appropriate course of remedial action. The inspectors also verified that there were no 10 CFR Part 21 issues.
The inspector reviewed the condition reports (CR). In each of these CRs, the inspector reviewed the licensees corrective actions and determined the licensees corrective actions were appropriate.
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 fire protection program and walked down the facility.
The inspector confirmed that the detection and suppression equipment was located where required, was being properly maintained, and could perform its intended function.
The inspector also verified that the fire barriers were effectively maintained. The inspector also verified that firefighting equipment was properly inventoried, inspected, tested, and maintained.
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 detect, control, and 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 The inspector walked down the plant and observed that the licensee had performed the necessary routine maintenance and housekeeping activities that were necessary for safe storage condition (SAFSTOR). Currently there were no decommissioning activities that had taken place at Dresden Nuclear Power Station, Unit 1. Only the activities had taken place to support the SAFSTOR.
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 performed walkdowns of Unit 1 on December 10, 2024. The inspector found acceptable plans were established in the Unit 1 fuel, reactor, turbine, and chemistry building to reasonably prevent the creation of airborne hazards; control the spread of contamination; and to reduce workers exposures. During tours of Unit 1, radiological postings and barriers were found to be in good condition and located where required given the radiological conditions.
A review of routine radiological surveys did not identify any unusual radiological conditions. The inspector reviewed the pre-work specific surveys, the Total Effective Dose Equivalence (TEDE) As Low As Is Reasonably Achievable (ALARA) Evaluation Screening Worksheets, and Radiation Work Permits (RWP) supporting the SAFSTOR.
The inspector determined that the workers didnt receive significant exposures. The inspector reviewed the survey instruments calibration records to ensure that the worker exposures were adequately assigned and controlled.
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 effluent release program was inspected by the NRCs Reactor Oversight Process (ROP).
No findings of significance were identified.
6.3 Conclusions This program is inspected by the NRC through the ROP for Unit 2 and Unit 3.
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 licensee didnt possess any unit 1 SNM.
7.3 Conclusion The licensee didnt possess any unit 1 SNM.
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 The inspector verified radioactive waste was appropriately controlled, labeled, posted, and secured against unauthorized removal. The inspectors also reviewed the licensees sealed source inventories and the appropriate leak tests. The licensee performed the inventories and leak tests in accordance with the approved procedures.
There were two waste shipments during this year. The inspector reviewed the shipping documents and determined that the radioactive wastes were transported in accordance with the NRC and Department of Transportation (DOT) requirements.
No findings of significance were identified.
8.3 Conclusions The licensee effectively processed, handled, stored, and transported radioactive material.
9.0 Exit Meeting The inspectors presented the results of the inspection to Roger Bauman and other members of the Dresden Nuclear Power Station, Unit 1 staff at an exit meeting on December 12, 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 R. Bauman, Site Decommissioning Director J. Jaegers, Manager Radiation Protection Programs A. Hoover, Site Decommissioning Specialist 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 ADAMS Agencywide Document Access and Management System ALARA As Low As Is Reasonably Achievable CAP Corrective Action Program CFR Code of Federal Regulations CR Condition Report DRSS Division of Radiological Safety and Security IP Inspection Procedure IR
Inspection Report
MDC Minimum Detectable Concentration
NRC
U.S. Nuclear Regulatory Commission
Reactor Oversight Process
Radiation Protection
Radiation Work Permit
SAFSTOR
Safe Storage