IR 05000285/2025001
| ML25058A024 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/27/2025 |
| From: | Jeffrey Josey NRC/RGN-IV/DRSS/DIOR |
| To: | Via T Omaha Public Power District |
| References | |
| IR 2025001 | |
| Download: ML25058A024 (1) | |
Text
February 27, 2025
SUBJECT:
FORT CALHOUN STATION - NRC INSPECTION REPORT 050-00285/2025-001
Dear Troy Via:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) decommissioning inspection conducted February 3-5, 2025, at the Fort Calhoun Station near Blair, Nebraska. The NRC inspectors discussed the results of the decommissioning inspection with members of your staff at the conclusion of the inspection on February 13, 2025. The inspection results are documented in the enclosure to this letter.
The NRC inspection examined activities conducted under your license as they relate to public health and safety, the common defense and security, and compliance with the Commissions rules and regulations, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observation of activities, and interviews with personnel. Specifically, the inspectors reviewed your decommissioning performance, safety reviews, and occupational radiation exposure. No violations were noted, and no response to this letter is required.
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter, its enclosure, and your response if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html.To the extent possible, your response, if you choose to provide one, should not include any personal privacy or proprietary information so that it can be made available to the public without redaction. If you have any questions regarding this inspection report, please contact Christian Dennes at (817) 200-1529 or the undersigned at (817) 200-1249.
Sincerely, Jeffrey E. Josey, Chief Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Docket No. 050-00285 License No. DPR-40 Enclosure:
Inspection Report 050-00285/2025-001 Electronic Distribution via Listserv Signed by Josey, Jeffrey on 02/27/25
ML25058A024 SUNSI Review By: CRD ADAMS:
Yes No Sensitive Non-Sensitive Non-Publicly Available Publicly Available Keyword NRC-002 OFFICE HP:DRSS:DIOR SHP:DRSS:DIOR BC:DRSS:DIOR NAME CDennes SAnderson JJosey SIGNATURE
/RA/
/RA/
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DATE 02/27/25 02/27/25 02/27/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.
050-00285 License No.
DPR-40 Report No.
050-00285/2025-001 Licensee:
Omaha Public Power District Facility:
Fort Calhoun Station Location:
9610 Power Lane Blair, Nebraska Inspection Dates:
February 3-5, 2025 Exit Meeting Date:
February 13, 2025 Inspectors:
Christian R. Dennes, Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Stephanie G. Anderson, Senior Health Physicist Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Accompanied By:
Jeffrey E. Josey, Chief Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Approved By:
Jeffrey E. Josey, Chief Decommissioning, ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Attachment:
Supplemental Inspection Information
EXECUTIVE SUMMARY Fort Calhoun Station NRC Inspection Report 050-00285/2025-001 This U.S. Nuclear Regulatory Commission (NRC) inspection was a routine, announced inspection of decommissioning activities being conducted at the Fort Calhoun Station. In summary, the inspectors concluded that the licensee was conducting activities in accordance with site procedures, license requirements, and applicable NRC regulations.
Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors
The inspectors observed decommissioning work in progress and concluded that the work was being conducted with an emphasis on industrial and radiological safety. Critical positions in the organizational structure were staffed. The licensee continued to identify problems and implement its corrective action program in accordance with quality assurance program requirements. (Section 1.2)
Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors
The licensee was prepared to implement the safety review program in accordance with site procedures and regulatory requirements. (Section 2.2)
Occupational Radiation Exposure at Permanently Shutdown Reactors
The licensee adequately implemented its occupational radiation protection program in accordance with their procedures and applicable regulatory requirements. (Section 3.2)
Report Details Summary of Site Status Fort Calhoun Station permanently ceased power operations in 2016. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.82(a)(9), an application for a license termination must be accompanied or preceded by the license termination plan (LTP). The licensee submitted its proposed LTP to the NRC in August 2021. The NRC conducted an acceptance review and submitted two requests for additional information to the licensee. The licensee subsequently submitted a revised LTP to the NRC in December 2023 (ML23346A152).
The NRC approved the LTP by license amendment dated January 31, 2024 (ML24019A167).
Since the previous inspection, the licensee continues to conduct radiological assessments of the interior of containment and the auxiliary building. The licensee started demolition of the mausoleum and continues to transport demolition rubble for offsite disposal.
Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors (IP 71801)
The inspectors observed site activities, reviewed documents, and interviewed site personnel to:
Evaluate the status of decommissioning and verify whether the licensee was conducting decommissioning and maintenance activities in accordance with regulatory and license requirements.
- Maintain awareness of work activities to assess licensee control and conduct of decommissioning.
- Evaluate select licensee decommissioning staffing, personnel qualifications, and training requirements, including that of the contracted workforce, to ensure that license requirements were met, as applicable to the current decommissioning status.
1.2 Observations and Findings a.
Status of Decommissioning The inspectors attended a daily site status meeting to ensure that the licensee and its decommissioning contractor continued to plan and implement decommissioning in a controlled manner. The inspectors conducted site tours, in part, to observe decommissioning activities in progress. The inspectors toured inside of containment which only the outer shell of the structure remained with the ventilation system in service. All material from inside of the containment had been removed and shipped offsite for disposal. The inspectors conducted a tour of the Waste Processing Structure (WPS) to observe the process of the loaded railcars for shipment filled with debris to an out-of-state disposal site. The inspectors also observed the demolition of the mausoleum. The inspectors noted good industrial safety controls in all locations.
The inspectors conducted independent radiological assessments during site tours using a hand-held survey meter, a Radeye G gamma survey meter (Serial Number 13421, calibration due date 11/26/25). The inspectors confirmed that radiological postings and survey results were consistent with regulatory requirements.
b.
Decommissioning Operations The inspectors performed a plant tour to assess field conditions and decommissioning activities by assessing material condition of structures, housekeeping, and worker level of knowledge of procedure use. The inspectors attended a pre-job briefing for the Final Status Survey (FSS) decommissioning activities, to understand the work in progress at the site. The inspectors noted that the FSS pre-job briefing provided adequate information about the field conditions, decommissioning activities, and overall safety for the staff. The inspectors observed FSS group conducting In Situ Object Counting System (ISOCS) surveys below ground level inside of containment. The inspectors noted no presence of debris and adequate housekeeping inside of containment. Outside of containment, the FSS group were also conducting ISOCS surveys in the first level of the auxiliary building according to procedure. The inspectors interviewed staff in those corresponding areas and found the selected staff to be proficient in implementing their procedures.
c.
Decommissioning Staffing and Training The inspectors reviewed the organizational chart and confirmed that all critical positions had been filled.
d.
Problem Identification and Resolution The inspectors reviewed section 16 of the Quality Assurance Topical Report, revision 18, that requires the licensee to implement a corrective action program. The inspectors as well reviewed the most recent list of Condition Reports (CR) issued since the last inspection. The inspectors found that the licensee is identifying problems and implementing its corrective action program in accordance with quality assurance program requirements.
1.3 Conclusions The inspectors observed decommissioning work in progress and concluded that the work was being conducted with an emphasis on industrial and radiological safety.
Critical positions in the organizational structure were staffed. The licensee continued to identify problems and implement its corrective action program in accordance with quality assurance program requirements.
Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors (IP 37801)
2.1 Inspection Scope The inspectors independently gathered sufficient information to determine whether licensee performance meets the following objectives:
To verify the licensees safety review process is in accordance with the requirements of 10 CFR 50.59, Changes, tests, and experiments.
- To provide assurance that required license amendments have been obtained.
2.2 Observations and Findings a.
Decommissioning Safety Review Program The inspectors reviewed the licensees safety review process and procedures, specifically FCSI-RA-203, 50.59 Review Process, revision 6 and FCSI-RA-203-1, 50.59 Resource Manual, revision 4. Title 10 CFR 50.59 allows a licensee to make changes to the facility or procedures and conduct test or experiments without prior NRC approval. The inspectors determined that the procedures and work processes provided adequate quality instructions to assure proper implementation, review, and approval related to design changes, and activities of regulator concerns involving decommissioning. Additionally, select qualifications and training for personnel who to prepare, review, and approve safety evaluations were reviewed for adequacy.
It was noted by the inspectors through document review and interviews that cognizant licensee personnel were knowledgeable and appeared to be appropriately trained.
b.
Design Changes, Tests, Experiments, and Modifications No design changes, tests, experiments, or modifications requiring screening or review were conducted during the sample period from February 2024 to present. No licensee safety review committee meetings were performed during the time of the inspection.
2.3 Conclusions The licensee was prepared to implement the safety review program in accordance with site procedures and regulatory requirements.
Occupational Radiation Exposure at Permanently Shutdown Reactors (IP 83750)
3.1 Inspection Scope The inspectors gathered sufficient information to determine whether licensee performance met the following objectives:
To ensure adequate protection of worker health and safety from exposure to radiation or radioactive material at permanently shutdown reactors.
- To evaluate whether the licensee adequately identifies problems and implements appropriate and timely corrective actions related to occupational radiation safety.
3.2 Observations and Findings a.
Organization, Changes, and Training The inspectors reviewed major changes since the last inspection in organization, personnel, facilities, radiation instrumentation, equipment, programs, and procedures that may affect occupational radiation protection. The inspectors determined that the major changes since the last inspection were adequate to assure proper implementation of the radiation protection program and were in accordance with regulatory requirements. Additionally, the inspectors reviewed the qualifications and training of selected radiation protection technician. The inspectors noted that the reviewed radiation protection technician had required qualifications and training to implement their duties.
b.
Radiological Work Planning and Observation The inspectors attended FSS start of shift meeting to go over the work activities that were occurring during the onsite inspection. Discussions included the amount of ISOCS surveys that remained at the site and the changes made in Task Hazard Assessment/Project Safety Plan to incorporate elevation name change to 973 elevation and safety protocol for the harsh weather that week. Additionally, the FSS start of shift meeting discussed the planning of the ISOCS surveys with risk of the work and identified appropriate radiation protection controls. The inspectors conducted observations of the work activities at the site to verify that the licensee is identifying the extend of radiological hazards and radiation protection technician are implementing adequate radiological controls. The inspectors concluded that radiological work activities were being conducted adequately and according to procedures and regulatory requirements.
c.
Dosimetry The inspectors reviewed the National Voluntary Laboratory Accreditation Program (NVLAP), to verify that the licensees personnel dosimeters are processed by a NVLAP accredited processor. Additionally, to verify that the approved radiation test categories for each type of personnel dosimeter are consistent with the types and energies of radiation present and method of dosimeter use. The inspectors noted that the NVLAP certification for Ionizing Radiation Dosimetry was up to date and demonstrated compliance with regulatory requirements.
The inspectors observed the onsite storage of dosimeters before their issuance, during use, and before processing to verify adequate storage and handling of the dosimeters.
The inspectors concluded that the onsite storage and handling of the dosimeters was adequate.
The inspectors reviewed the licensees program and capability to monitor workers for unplanned intakes, including dose assessments based on methods such as derived air concentration (DAC)-hour tracking monitoring and air sampling for related work. The inspectors. The inspectors reviewed the licensees procedure for collection and analysis of lapel samples, specifically FCSD-RP-224, Information Use Personnel Air Monitoring and DAC-hour Tracking, revision 6. The inspectors determined that the procedure and work processes provided adequate quality guidance for use, collection and analysis of lapel samples. Additionally, the procedure covers the radiological lapel air samples performed to support the FCS internal dose monitoring program were reviewed for adequacy.
d.
Airborne and Contamination Controls The inspectors reviewed work activities, observe the work activities, and assessed the adequacy of the licensees air monitor program, practices, and dose assessments based on air sampling, and DAC monitoring. The inspectors reviewed airborne radioactivity calculation sheets and lapel sample records from the laboratory to verify that the procedures and regulatory requirements were being met. The inspectors determine that the program and practices were being accomplished adequately.
The inspectors conducted a walk down inside and outside of containment, and WPS to observe air monitors in service to determine whether they were appropriately positioned relative to the area they were intended to monitor. Portable air samplers were being used inside containment, and the WPS to monitor the general areas for airborne contamination. Recent results of 2025 indicated that the air contained radionuclides were adequate and below regulatory requirements. The licensee also utilized portable effluent air samplers to monitor the airborne concentrations in outdoor areas around the site. The inspectors observed the samplers and confirmed that the samplers were in good working order and maintained adequately at the time of the inspection. The inspectors reviewed selected general area air sample results that were collected one week before the inspection and noted that the sample results indicate that there were no widespread problems with ambient air concentrations that negatively impacted workers.
e.
Problem Identification and Resolution The inspectors observed and reviewed that the licensee was identifying problems related to radioactive waste storage, and processing at an appropriate threshold and entering them into the corrective action program. The inspectors reviewed the most recent list of CRs issued since the last inspection, as well as the two CRs written during the inspection. The inspectors determined that the licensee in general, is adequately following their procedures and regulatory requirements.
3.3 Conclusions The licensee in general, adequately implemented its occupational radiation protection program in accordance with their procedures and applicable regulatory requirements.
Exit Meeting Summary The inspectors presented the preliminary inspection results to the licensees management and other members of the licensees staff at the conclusion of the inspection exit meeting on February 13, 2025. The inspectors asked if any materials examined were proprietary. No proprietary information was removed from the site.
Attachment SUPPLEMENTAL INSPECTION INFORMATION KEY POINTS OF CONTACT Licensee and Contractor Personnel B. Pearson, Regulatory Assurance & Emergency Planning Manager K. Daughenbaugh, ISFSI Shift Supervisor T. Uehling, Director Site Decommissioning R. Hugenroth, Nuclear Oversight Manager A. Hansen, Regulatory Assurance C. Heimes, Manager ISFSI Site Security A. Kodra, Project Manager FSS, EnergySolutions J. Layton, Planning & Scheduling Supervisor T. Maine, Plant Manager B. Bishop, Energy Solutions LTP/FSS Manager J. Nowak, Project Director, EnergySolutions D. Whisler, RP & Chemistry Specialist J. Hoffman, Chemistry Specialist ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None PARTIAL LIST OF DOCUMENTS REVIEWED Procedures FCSD-RP-100, Radiation Protection Program Description, revision 1 FCSD-RP-101, Radiation Protection Processes and Operation, revision 1 FCSD-RP-108, Unescorted Access to and Conduct in Radiologically Controlled Areas, revision 1 FCSD-RP-224, Personnel Air Monitoring and DAC-hr Tracking, revision 6 FCSD-RP-280, Occupational Exposure Reporting, revision 2 FCSD-RP-301, Discrete Radioactive Particle Control, revision 4 FCSD-RP-310, Radiological Air Sampling, revision 4 FCSD-RP-350, Personnel Contamination Monitoring, Decontamination and Reporting, revision
FCSD-RP-376, Radiological Posting, Labeling and Marking, revision 4 FCSD-RP-410, Selection, Use and Control of Protective Clothing, revision 0 FCSD-RP-460, Controls for High and Locked High Radiation Areas, revision 3 FCSD-RP-503, Unconditional Release Survey Method, revision 7 FCSI-RA-203, 50.59 Review Process, revision 6 Condition Reports Generated from Inspection CR-2025-00011
CR-2025-00012 Licensing Bases Documents Fort Calhoun 1 Technical Specification, Amendment 299 License Termination Plan, January 31, 2024 Miscellaneous Qualification Group Qualified Employees, February 5, 2025 Fort Calhoun Plan of The Day, February 4, 2025 RWP-24-0301, Waste Processing Structure Activities, revision 2 Procedures/Forms TQ-DC-FC-201-1005, ANSI Supplemental Radiation Protection Technician, revision 13 INSPECTION PROCEDURES USED IP 71801 Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors IP 37801 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors IP 83750 Occupational Radiation Exposure at Permanently Shutdown Reactors LIST OF ACRONYMS ADAMS Agencywide Documents Access and Management System CFR Code of Federal Regulations CR Condition Report DAC derived air concentration FCS Fort Calhoun Station FSS Final Status Survey ISOCS In Situ Object Counting System IP Inspection Procedure LTP License Termination Plan NRC Nuclear Regulatory Commission NVLAP National Voluntary Laboratory Accreditation Program RP Radiation Protection RWP Radiological Work Permit WPS Waste Processing Structure