IR 05000305/2025001
| ML25108A081 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 04/30/2025 |
| From: | Dave Hills NRC/RGN-III/DRSS |
| To: | Worster R Kewaunee Solutions |
| References | |
| IR 2025001 | |
| Download: ML25108A081 (1) | |
Text
SUBJECT:
KEWAUNEE POWER STATION - NRC INSPECTION REPORT NO. 05000305/2025001
Dear Ronald Worster:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Kewaunee Power Station (KPS). On April 9, 2025, the NRC inspectors discussed the results of the inspection with you and members of your staff. The results of this inspection are documented in the enclosed report.
During the inspection, the NRC inspectors reviewed the onsite activities associated with the Occupational Radiation Exposure at Permanently Shutdown Reactors, Remedial and Final Surveys at Permanently Shutdown Reactors, Solid Radioactive Waste Management and Transportation of Radioactive Materials, Decommissioning Performance and Status Review and the Fire Protection Program. The inspection consisted of an examination of activities at the site as they related to safety and compliance with the Commissions rules and regulations.
No violations of more than minor safety significance were identified during this inspection.
April 30, 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 (CFR) 2.390.
Public Inspections, Exemptions, Requests for Withholding.
Sincerely, David E. Hills, Chief Decommissioning, Reactor, and ISFSI Health Physics Branch Division of Radiological Safety and Security Docket No.: 50-305 License No.: DRP-43
Enclosure:
IR No. 05000305/2025001
REGION III==
Docket No.:
50-305 License No.:
DRP-43 Report No.:
05000305/2025001 Licensee:
Kewaunee Solutions Facility:
Kewaunee Power Station Location:
Kewaunee, Wisconsin Inspection Dates:
March 10-14, 2025 March 18-21, 2025 March 31, 2025 Inspectors:
M. LaFranzo, Sr. Health Physicist P. Lee, Ph. D., CHP, Reactor Inspector (Decom)
Approved By:
David E. Hills, Chief Decommissioning, Reactor, and ISFSI Health Physics Branch Division of Radiological Safety and Security
EXECUTIVE SUMMARY
[Kewaunee Power Station]
NRC Inspection Report No. 05000305/2025001 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 cited violations were identified.
Occupational Radiation Exposure at Permanently Shutdown Reactors
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.
Remedial and Final Surveys at Permanently Shutdown Reactors
Adequate protection of the public health and safety from exposure to radiation and radioactive material was provided.
Solid Radioactive Waste Management and Transportation of Radioactive Materials
The licensee effectively processed, handled, stored, and transported radioactive material.
Decommissioning Performance and Status at Permanently Shutdown Reactors
The inspectors determined that decommissioning activities were in accordance with the regulations and license requirements.
Fire Protection Program at Permanently Shutdown Reactors
The NRC identified that the licensee had adequate control of combustible waste products to control and/or limit fire-induced release of radioactive material from contaminated plants area.
Report Details Summary of Facility Status The KPS is a permanently shut-down and defueled power reactor undergoing active decommissioning. During this inspection period, the licensee was conducting routine decommissioning activities.
1.0 Occupational Radiation Exposure at Permanently Shutdown Reactors (IP 83750)
1.1 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.
1.2 Observations and Findings The inspectors reviewed the Radiation Work Permit (RWPs) for dismantlement of the primary coolant system, and discussed with the licensee, especially in the areas of air monitoring and respirator protection due to the potential airborne alpha-emitters during the dismantlement. All personnel were appropriately monitored and the RWPs were followed by licensee personnel during the performance of the assigned tasks.
The inspectors discussed the air monitoring and internal dose assessments of alpha-emitters with the licensee. The inspectors reviewed the air monitoring results from the workers working on dismantlement of the primary coolant system, such as removal of reactor coolant pump casings and reactor coolant piping segmentation. The workers wore the respirator protection with a protection factor of 1000. The breathing zone air sampling results indicated that the internal exposures were well below the Part 20 limits even without the respirator protection.
No findings of significance were identified.
1.3 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.
2.0 Remedial and Final Surveys at Permanently Shutdown Reactors (IP 83801)
2.1 Inspection Scope The purpose of this portion of the inspection was to evaluate the effectiveness of the licensees remedial and final survey program to adequately protect the public health and safety from exposure to radiation or radioactive material.
2.2 Observations and Findings The licensee had been conducting pressure washing of Auxiliary Building drain piping.
The inspectors discussed with the licensee the efficiency calibration procedure of the detector used to measure the inner surface activities of the pipe. The inspectors also observed the licensee personnel performing the calibration.
The liquid wastes generated from pressure washing were currently stored in the liquid waste holding tanks and not discharged to the lake yet. The licensee planned to follow the Off Site Dose Calculation Manual (ODCM) during the releases. The inspectors reviewed the ODCM to ensure the off-site doses will meet the regulatory limits for the public.
The inspectors verified that the high purity germanium detectors used for soil sample analyses had been properly calibrated. The inspectors reviewed the results of gamma walkover and soil sampling from land surveys outside the fence of the Protected Area and interviewed licensee personnel to ensure that the characterization surveys were properly conducted in the Class 3 areas. No licensed materials were identified.
No findings of significance were identified.
2.3 Conclusions Adequate protection of the public health and safety from exposure to radiation and radioactive material was provided.
3.0 Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP 86750)
3.1 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.
3.2 Observations and Findings The licensee transported the casing of a reactor coolant pump to the Clive Disposal Site on March 24, 2025. The inspectors reviewed the manifest of the shipment. Based on the characterization of radioactive materials, this was a surface contaminated object (SCO)-II shipment. The inspectors reviewed the information provided to the qualified vendor for waste characterization, such as Part 61 analyses of the waste stream, the surface dose rates and removable contamination of the casing, etc., and interviewed the licensee personnel to ensure that the proper information was provided to the vendor for the waste characterization. The inspectors also reviewed the radiation survey of the shipment. The inspectors determined that the waste shipment was in compliance with the regulatory requirements.
No findings of significance were identified.
3.3 Conclusions The licensee effectively processed, handled, stored, and transported radioactive material.
4.0 Decommissioning Performance and Status at Permanently Shutdown Reactors (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 inspectors toured the licensees facility and noted that current work activities were conducted safely and in accordance with NRC regulations. The inspectors attended several meetings associated with decommissioning activities and noted that topics discussed identified appropriate problems and performance insights. The inspectors interviewed several staff members and noted that a sufficient amount of knowledge existed to ensure safe decommissioning operations.
4.3 Conclusions The inspectors determined that decommissioning activities were in accordance with the regulations and license requirements.
5.0 Fire Protection Program at Permanently Shutdown Reactors (IP 64704)
5.1 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.
5.2 Observations and Findings The inspectors toured the licensees plant areas where combustible waste or hot work was being performed and noted that appropriate fire watches and fire extinguishing equipment was available to identify potential fires and respond as appropriate in contaminated areas. The inspectors noted that the licensee had adequate control of combustible waste products to limit fire ignition throughout the facility. The inspectors also noted that an agreement with the local fire department was in place and the department was available, as needed.
5.3 Conclusions
The NRC identified that the licensee had adequate control of combustible waste products to control and/or limit fire-induced release of radioactive material from contaminated plants area.
6.0 Exit Meeting The inspectors presented the results of the inspection to Mr. Ronald Worster and other members of the Kewaunee Solutions and Decommissioning staff at an exit meeting on April 9, 2025. The licensee acknowledged the result presented and did not identify any of the information discussed as proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED General Manager/Project Director B. McMahon Decommissioning Plant Manager J. Lynch Regulatory Affairs Director D. Peterson Radiation Protection Manager T. Schneider Licensing Manager D. Shannon RP Technical Manager INSPECTION PROCEDURES USED IP 83750 Occupational Radiation Exposure at Permanently Shutdown Reactors IP 83801 Remedial and Final Surveys at Permanently Shutdown Reactors IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials IP 71801 Decommissioning Performance and Status at Permanently Shutdown Reactors IP 64704 Fire Protection Program at Permanently Shutdown Reactors ITEMS OPENED, CLOSED, DISCUSSED Opened Type Summary None Closed Type Summary None Discussed Type Summary None
PARTIAL LIST OF DOCUMENTS REVIEWED The following is a partial list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather that selected sections of portions of the documents were evaluated as part of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
- Defueled Safety Analysis Report Rev. 2 Dated November 7, 2022
Revision to Post-Shutdown Decommissioning Activities Report Rev. 1 Dated April 25, 2014
Offsite Dose Calculation Manual Rev. 22 Dated June 3, 2024
KS-FP-PN-001 Fire Hazard Analysis Rev 2
KS-C-TB-WKPG-0165/0194 Permit No.24-042
KS-AD-WKPG-0168 Permit No.25-003
KS-C-RB-WKPG-0236 Permit No.25-001
Large Components Reactor Building RCS Nuclide Distribution Report dated August 30, 2024
RCP Casing A and B Rad Survey Records Including Attachments
RWP 2025-0019-1 Large Component Removal Preps and RCPs - Radiation Areas LIST OF ACRONYMS USED ADAMS Agencywide Document Access and Management System CFR Code of Federal Regulations CY Calendar Year KPS Kewaunee Power Station DRSS Division of Radiological Safety and Security IP Inspection Procedure ISFSI Independent Spent Fire Storage Installation NRC U.S. Nuclear Regulatory Commission ODCM Off Site Dose Calculation Manual PSR Permanently Shutdown Reactor RWP Radiation Work Permit SCO Surface Contaminated Object