IR 05000285/2026001
| ML26044A135 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/18/2026 |
| From: | Natasha Greene NRC/RGN-IV/DRSS/DIOR |
| To: | Via T Omaha Public Power District |
| References | |
| IR 2026001 | |
| Download: ML26044A135 (0) | |
Text
February 18, 2026
SUBJECT:
FORT CALHOUN STATION - NRC INSPECTION REPORT 05000285/2026001
Dear Troy Via:
On January 22, 2026, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fort Calhoun Station near Blair, Nebraska. The inspectors discussed the results of this inspection with Ben Pearson, Regulatory Assurance and Emergency Planning Manager, at the conclusion of the inspection. The results of this inspection are documented in the enclosed report. No findings or violations of more than minor significance were identified during this inspection.
This inspection examined activities conducted under your license as they relate to public health and safety, and to confirm compliance with the Commission's rules and regulations, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.
In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedures, 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 and from the NRCs ADAMS, accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary information so that it can be made available to the public without redaction.
Sincerely, Natasha A. Greene, PhD, Branch Chief Decomm., ISFSI, and Operating Reactor Branch Division of Radiological Safety and Security Docket No. 050-00285 License No. DPR-40 Enclosures:
Inspection Report No. 05000285/2026001 with Attachment, Fort Calhoun Station Records Request Distribution via GovDelivery Subscriber Signed by Greene, Natasha on 02/18/26
ML26044A135 SUNSI Review ADAMS:
Non-Publicly Available Non-Sensitive Keyword:
By: ESM Yes No Publicly Available Sensitive NRC-002 OFFICE HP:DRSS/DIOR HP:DRSS/DIOR SHP:DRSS/DIOR C:DRSS/DIOR NAME EMcManus CDennes LGersey NGreene SIGNATURE
/RA/
/RA/
/RA/
/RA/
DATE 02/17/26 02/17/26 02/17/26 02/18/26
Enclosure U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket No.
05000285
License No.
Report No.
Enterprise Identifier:
I-2026-001-0077
Licensee:
Facility:
Location:
Inspection Dates:
Inspectors:
Approved By:
Omaha Public Power District
Fort Calhoun Station
9610 Power Lane
Blair, Nebraska
January 21-22, 2026
E. McManus, Health Physicist
C. Dennes, Health Physicist
Natasha A. Greene, PhD, Branch Chief
Decommissioning, ISFSI, Operating Reactor Branch
Division of Radiological Safety and Security
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) conducted an inspection of decommissioning activities in progress at the Fort Calhoun Station in Blair, Nebraska.
List of Findings of Significance and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
SITE STATUS Since the previous inspection conducted in September 2025 (ADAMS Accession No.
ML25267A135), the licensee completed removal of the liquid waste processing system with its associated equipment and completed shipment of the containment structure material to a disposal site in Clive, Utah. At the time of the inspection, the licensee was demolishing the Waste Processing Structure (WPS), decontaminating heavy equipment in the Flex Building, and conducting Final Status Surveys (FSS) at multiple locations on the site. Radiological survey activities focused on accessible open areas, former structure footprints, material handling locations, and pathways associated with the movement of potentially contaminated materials.
INSPECTION SCOPES
The inspection was conducted using the appropriate portions of the inspection procedures (IPs).
Currently approved IPs are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. The inspection was declared complete when the objectives of the IP were met, consistent with Inspection Manual Chapter (IMC) 2561, Decommissioning Power Reactor Inspection Program.
IP 83750 - Decommissioning Occupational Radiation Control Radiological Work Planning and Execution (Section 03.01)
The inspectors evaluated the licensees radiological work planning and execution to verify that radiological hazards were identified, evaluated and controlled during decommissioning activities.
The inspectors:
- (1) Attended the licensees plan of the day meeting
- (2) Observed a waste and transportation group pre-job brief
- (3) Toured the WPS and Flex Building to verify the areas were controlled and posted in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 20 regulations
- (4) Reviewed Survey Record Package M-20260121-2, Pre-Decon Survey of JD 470 License Condition Excavator S/N: 108121, dated January 21, 2026, to verify equipment was surveyed for release in accordance with licensees procedures and 10 CFR 20 requirements
- (5) Observed radiation protection (RP) technician actions in response to whole body portal monitor alarm when exiting the Flex Building contaminated area
- (6) Observed work activities at the WPS pad, including in-process contamination surveys and oversight of work by RP personnel
- (7) Observed RP instrumentation to verify instruments had valid calibration and were operational checked prior to use.
- (8) Inspected portable temporary ventilation and portable air samplers to verify instruments positioned adequately and were within calibration
- (9) Interviewed the RP manager to discuss the radiological risk evaluation for changing scope of work on site.
- (10) Reviewed licensees self-assessment FCSI-RA-303-F-01, Radiation Protection 2025 Self-Assessment, dated December 5, 2025 (11)
- (12) Reviewed licensees procedures for performing radiological work, including:
a.
WI-2021-109, Waste Packaging Plan Debris & Crushed Concrete (<4)/Soil, revision 3 b.
FC-21-008, Radiological Controls in Support of Open-Air Demolition, revision 5
- (13) Reviewed Radiological Work Permits (RWP):
a.
22-0329, Open Air Demolition of the Auxiliary, Fuel, Radwaste Buildings and Support Buildings, revision 3 b.
24-0301, Waste Processing Structure Activities, revision 4 c.
26-0101, Decommissioning Miscellaneous Activities, revision 0 d.
26-0201, Regulatory Activities, revision 0 e.
26-0402, IOF Emergency Response Activities, revision 0 f.
26-0401, IOF Surveillance and Minor Maintenance, revision 0 Occupational Radiation Exposure Topical Areas (Section 03.02)
The inspectors verified the licensee was implementing the occupational radiation exposure program by evaluating the airborne monitoring, respiratory protection, contamination control, instrumentation, and source term topical areas. The inspectors:
- (1) Observed operation of air samplers located near the WPS
- (2) Observed use of dosimeters by personnel working in radiological areas
- (3) Inspected RP instruments in use to verify they were correct for the surveys performed and the radionuclides of concern
- (4) Reviewed records for calibration and response checks for radiation survey instrumentation
- (5) Reviewed the licensees 2025 Annual Programmatic Assessment and Review report, dated December 8, 2025
- (6) Reviewed the licensees source term evaluation: FC-22-002, Evaluation of Instrument Response to Measured Plant Radionuclide Mix, revision 2
- (7) Reviewed As Low As Reasonably Achievable (ALARA) Plan Number 24-0301-1, Waste Processing Structure (WPS), dated December 13, 2023
- (8) Reviewed RWPs:
a.
FCSD-RP-202, Exposure Control and Authorization, revision 4 b.
FCSD-RP-224, Personnel Air Monitoring and DAC-hr Tracking, revision 6 c.
FCSD-RP-300, Radiological Survey Program, revision 5 d.
FSCD-RP-302, Determination of Alpha Levels and Monitoring, revision 3 e.
FCSD-RP-310, Radiological Air Sampling, revision 4 f.
FCSD-RP-376, Radiological Posting, Labeling and Marking, revision 4 g.
FCSD-RP-401, ALARA Planning and Control, revision 2 h.
FCSD-RP-403, Administration of the Radiation Work Permit Program, revision 2 i.
FCSD-RP-503, Unconditional Release Survey Method, revision 7 Problem Identification and Resolution (Section 03.03)
The inspectors reviewed Condition Report CR-2025-0119, Radioactive material outside posted RCA, dated September 24, 2025, and discussed the corrective actions with the RP manager.
IP 83801 - Inspection of Remedial and Final Surveys at Permanently Shutdown Reactors Remediation Activities and Final Status Surveys (IP Section 02.01)
The inspectors evaluated remediation activities and implementation of the FSS to assess the radiological surveys conducted. The inspectors:
- (1) Observed the FSS morning briefing to evaluate communication of survey scope, radiological conditions, and controls.
- (2) Interviewed the licensees program manager for FSS/License Termination Plan (LTP) to assess knowledge of survey requirements and implementation.
- (3) Reviewed selected FSS plans to verify consistency with site conditions, LTP commitments, and regulatory requirements
- (4) Reviewed two survey unit sampling plans and survey plan requirements
- (5) Verified that radiological instruments used to support FSS activities were appropriately selected, calibrated and capable of detecting radionuclides of concern at the required minimum detectable concentrations Verification and Confirmatory Surveys (IP Section 02.02)
The inspectors performed independent verification surveys, such that the NRC could effectively assess the adequacy of the licensee's survey results. The inspectors:
- (1) Conducted qualitative verification surveys of the WPS surroundings, focusing on accessible surfaces
- (2) Conducted qualitative verification surveys of farmland on the south side of the site in survey unit No.8309
- (3) Conducted qualitative verification surveys of a back-filled area that resides in the northwest portion of the decommissioning area in survey unit No.7404
- (4) Conducted qualitative verification surveys of the haul road used for movement of contaminated materials The inspectors utilized a Ludlum Model 3003i survey kit (serial number 25038457, calibration due date of 02/11/2026) to perform independent gamma radiation surveys in areas where ongoing decommissioning and radiological survey activities were in progress. The inspectors determined that the gamma survey readings obtained were in agreement with the licensees radiological survey measurements.
Problem Identification and Resolution (IP Section 02.03)
The inspectors reviewed the following Condition Reports and discussed the significance of the events with the RP manager and program manager of FSS/LTP:
- (1) Condition Report CR-2025-0122, Radioactive Material Identified in Survey Unit 8312, dated October 15, 2025
- (2) Condition Report CR-2025-0129, Open Land Survey Result 8310, dated October 4, 2025 IP 86750 - Decommissioning Solid Radioactive Waste Management, Demolition, and Transportation of Radioactive Materials Radioactive Material Storage, Control, and Processing (IP Section 03.01)
The inspectors conducted site tours and reviewed selected records to observe decommissioning activities in progress. The inspectors:
- (1) Toured the Flex Building to observe if radioactive material was being stored in accordance with 10 CFR Part 20 requirements
- (2) Toured the WPS and Flex Building to determine if ventilation systems and monitoring equipment were controlled and marked in accordance with 10 CFR Part 20 and Part 50 ventilation and monitoring requirements
- (3) Reviewed the licensees procedures for generation and control of radioactive waste:
a.
FCSD-RW-PG-100, Waste Management Program, revision 0 b.
FCSD-RW-PG-101, Radwaste Process Control Program, revision 2
- (4) Reviewed the sealed source inventory record, dated October 1, 2025 Transportation of Radioactive Materials (IP Section 03.02)
The inspectors observed containers staged for shipment and reviewed selected records to verify shipments containing radioactive material were prepared and shipped in accordance with regulatory and licensee requirements. The inspectors:
- (1) Observed the waste and transportation groups pre-job brief
- (2) Observed the placarding for shipping containers on rail cars to determine if containers were marked and labelled in accordance with 10 CFR Part 20, 49 CFR Part 172, and 10 CFR Part 71.5 requirements
- (3) Reviewed two completed shipping packages to determine if container radiation levels were in accordance with 49 CFR Part 173 limits and documentation was in accordance with 49 CFR Part 172
- (4) Reviewed two completed Class A shipping packages to determine if the packages were complete and determine if the drivers were provided with all documentation required in accordance with 49 CFR Part 172 requirements
- (5) Reviewed a sample of personnel training records to determine if personnel who packaged, labeled, and signed for waste packages were trained in accordance with 10 CFR Part 71.5 and 49 CFR Part 172.704 requirements
- (6) Reviewed certificate of disposal for Class A waste shipments received at the disposal site from December 30-31, 2025
- (7) Reviewed the licensees procedures implemented for disposition and transportation of radioactive materials, including:
a.
WI-2021-109, Waste Packaging Plan, Debris & Crushed Concrete
(<4)/Soil, revision 3 b.
NVNC-RW-401; Radioactive Shipping Procedure for Shipment NVNC-2025-027, revision 0 c.
FCSD-RW-PN-202, Transportation Incident and Emergency Response Plan, revision 3 d.
FCSD-RW-PR-303, Waste Characterization and Classification, revision 0 e.
FCSD-RW-PR-307, RADMAN' Suite Software Package, revision 2 f.
FCSD-RW-PR-308, Packaging Solid Radioactive Waste, revision 0 g.
FCSD-RW-PR-309, Waste Package Certification, revision 1 h.
FCSD-RW-PR-310, Container Receipt and Inspection, revision 3 i.
FCSD-RW-PR-315, Training and Qualification of Waste Management Personnel, revision 3 j.
FCSD-RW-PR-320, Radioactive Material Shipments, revision 0 k.
FCSD-RW-PR-320-F-04, Radioactive Material Shipment Checklist, revision 0 Demolition and Disposition of Radiologically Impacted Structures (IP Section 03.03)
The inspectors:
- (1) Toured the WPS to determine if the disposition of demolition waste was conducted in accordance with the licensees procedures
- (2) Toured the location where the containment building was located prior to demolition and interviewed RP manager regarding the containment footprint surveys and remediation
- (3) Interviewed the work control manager regarding completed demolition and plans to remove the WPS and its associated ventilation components. Discussion included structures to be evaluated for free release, decontamination prior to demolition, contamination control during demolition, and disposition of material after demolition.
- (4) Reviewed FC-RP-20-194, VSDS Itemized Survey Report, Survey I-20250717-1, dated July 10, 2025
- (5) Reviewed FC-21-008, Radiological Controls in Support of Open-Air Demolition, revision 4
- (6) Reviewed ALARA Plans to verify implementation of licensees procedures and 10 CFR Part 20 regulations:
a.
FCSD-RP-401-F-01, ALARA Plan 24-0301-1, revision 1 b.
FCSD-RP-401-F-01, ALARA Plan 24-0302-03, revision 1
- (7) Reviewed RWPs:
a.
24-0301, Waste Processing Structure Activities (WPS), revision 4 b.
24-0302, Containment Internal Demolition, revision 4 c.
24-0365, Containment External Demolition, revision 0 d.
FCSD-RP-380-F-01, Containment Verification Survey Area Release for Demolition, revision 0 e.
FCSD-RP-380-F-02, CVS Area Turnover, Acceptance and Access Control, revision 0 f.
FCSD-RP-380-F-03, Radiological Survey Instructions for Contamination Verification Survey, revision 0 Problem Identification and Resolution (IP Section 03.04)
The inspectors reviewed Condition Report CR-2026-00003, WPS Scale #1 Display Box Character Errors, dated January 6, 2026, to determine if the licensee was identifying problems related to solid radioactive waste management, demolition, and transportation of radioactive materials at an appropriate threshold and was entering problems into its corrective action program.
INSPECTION RESULTS
No findings or violations of more than minor significance were identified during this inspection.
EXIT MEETING The inspectors verified that no proprietary information was retained or documented in this report.
- On January 22, 2026, the inspectors presented the inspection results to Ben Pearson, Regulatory Assurance and Emergency Planning Manager.
ADDITIONAL
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calibration
Records
FCSD-RP-
800-F-01
Source Program Records Coversheet
FCSD-RP-
210
Information Use Dosimetry Issue, Usage,
and Control
FCSD-RP-
20
Information Use Bioassay Program
FCSD-RP-
301
Information Use Discrete Radioactive
Particle Control
Procedures
FCSD-RP-
400
Information Use ALARA Program
25-0302
Containment External Demolition
Radiation
Work
Permits
(RWPs)
25-0365
Containment External Demolition
83750-
Cat8
Self-
Assessments
FCSI-RA-
303-F-01
Self-Assessment
83801
Procedures
FCSD-RA-
LT-200
Characterization Survey Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FCSD-RA-
LT-201
Characterization Sample Plan
Development
FCSD-RA-
LT-301
Survey Unit Classification
FCSD-RA-
LT-302
Final Status Survey Sample Plan
Development
FCSD-RA-
LT-303
Final Status Survey Isolation and Control
Measures
FCSD-RA-
LT-304
Final Status Survey Data Assessment
FCSD-RA-
LT-305
Final Status Survey Data Reporting
FCSD-RA-
LT-306
Radiological Assessments and Remedial
Action Support Surveys
FCSD-RA-
LT-307
Unconditional Release Surveys
FCSD-RA-
LT-308
Radiation Survey with Pipe Detectors
FCSD-RA-
LT-302-F-01
FSS Sample Plan Cover Sheet Survey
Unit No.: 7404
Radiation
Surveys
FCSD-RA-
LT-302-F-01
FSS Sample Plan Cover Sheet Survey
Unit No.: 8309
CR-2025-
00119
Condition Report Summary with
Attachments
11/03/2025
CR-2025-
00122
Condition Report Summary with
Attachments
10/16/2025
86750-
Cat8
Corrective
Action
Documents
CR-2025-
00129
Condition Report Summary with
Attachments
11/05/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FCSD-RW-
PN-201
Waste Management Interfaces and
Organizational Responsibilities
FCSD-RW-
PN-203
Hazardous Material Transportation
Security Plan
FCSD-RW-
PR-300
Hazardous Waste Management
FCSD-RW-
PR-302
Waste Material Control and Tracking
FCSD-RW-
PR-304
Sampling of Hazardous Materials and
Wastes
FCSD-RW-
PR-305
Waste Management Permitting and
Compliance
FCSD-RW-
PR-313
Shipment of Hazardous Materials
FCSD-RW-
PR-316
Blocking and Bracing Rail Packages
FCSD-RW-
PR-321
Rail Safety and Operations
FCSD-RW-
PR-322
Training and Qualification of Rail Workers
Procedures
WI-2021-109 Waste Packaging Plan
ATTACHMENT
Fort Calhoun Station Records Request, dated December 18, 2025
The following items are requested for inspection
at Fort Calhoun Station
January 21-22, 2026
Inspection Report 2026-001
Inspection Procedures (IP) to be implemented:
1.
IP 83750 Decommissioning Occupational Radiation Exposure
2.
IP 86750, Solid Radioactive Waste Management, demolition, and Transportation of
Radioactive Materials
3.
IP 83801, Inspection of Remedial and Final Surveys at Permanently Shutdown Reactors
Please have the requested documents uploaded to the FCS Certrec site no later than
January 9, 2026.
Inspectors:
1.
Eric McManus (Lead)
2.
Christian Dennes
If there are any questions, please contact Eric McManus, 808-264-1878, or via email at
eric.mcmanus@nrc.gov.
1.
IP 83750 - Decommissioning Occupational Radiation Exposure
a) Copy of Annual Exposure Results for 2025; TLD and Electronic Dosimetry returns
since October 1, 2025; and 2026 exposure totals to date.
b) Copy of the last 2 ALARA Committee meetings
c)
Exposure budget for 2026
d) List of HRA and VHRA locations
e) Copies of the following site procedures:
f)
ALARA Program
g) Internal Dosimetry Program
h) External Dosimetry Program
i)
Radiation Surveys and/or Routine Surveys
j)
Air Sample Collection and analysis
k)
Contamination survey including alpha monitoring and hard-to-detect isotopes
l)
Surveying and Releasing of Material from an RCA for unrestricted use.
m) Radiological Posting, labelling, and marking.
n) Copies of Audits and Self-Assessments of the ALARA and Exposure Monitoring
programs/ Radiation Protection Programs since October 1, 2025
o) Copy of Annual Radiation Protection Program evaluation for 2025, under 10 CFR 20.1101(c)
p) List of RWPs that have been generated for 2026
q) List of CAP entries for this program area, since October 1, 2025
r)
Source term evaluation, including alpha/beta gamma ratios
s)
Sealed source inventory and leak test records since October 1, 2025
2.
IP 86750: Decommissioning Solid Radioactive Waste Management, Demolition,
and Transportation of Radioactive Materials
a) Copy of procedures and implementing documents for processing, storage, and
disposal of solid radioactive waste produced during decommissioning activities
b) Demolition work plans and associated radiological controls for waste segregation
c)
List of shipments made since September 25, 2025
d) Copies of 2 most recent completed shipping packages.
e) Training and qualifications records for personnel performing radioactive waste
handling, packaging, and transportation activities
f)
List of CAP entries for this program area, since September 25, 2025
3.
IP 83801: Inspection of Remedial and Final Surveys at Permanently Shutdown
Reactors
a) Copy of Final Status Survey (FSS) procedure for conducting final status surveys (if
different than provided in the LTP)
b) Copy of maps or diagrams identifying the land areas surveyed, including survey
units, boundaries, and classifications
c)
List of FSS radiological surveys completed since April 16, 2025, in-progress and
planned
d) Documentation describing radiological controls, survey requirements, and release
criteria applied during and following demolition of the containment building, including
controls used to prevent the spread of contamination during demolition activities
e) Pre-and post-demolition radiological survey results for the containment footprint and
surrounding soils, including remedial actions performed
f)
Soil sampling results and analyses associated with containment demolition, including
comparison to LTP-derived DCGLs
g) Instrumentation calibration, source check, and MDA documentation for instruments
used to support FSS
Regulatory Basis
Licensees are reminded that records required to demonstrate compliance with NRC
requirements must be maintained in accordance with:
Title 10 of the Code of Federal Regulations 50.75(G) - Records of decommissioning
Title 10 of the Code of Federal Regulations 20.2103 - 20.2108 - Recordkeeping
requirements for radiation protection, effluents, surveys, and waste disposal
Documentation should be complete, current, and clearly identify revisions and effective dates.
Proprietary or sensitive information should be appropriately marked in accordance with 10 CFR 2.390 (Public inspections, exemptions, requests for withholding).
PAPERWORK REDUCTION ACT STATEMENT
This letter contains voluntary information collections that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget
(OMB) approved these information collections (approval number 3150-0011). The
burden to the public for these information collections is estimated to average 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />
per response. Send comments regarding this information collection to the FOIA, Library
and Information Collection Branch, Office of the Chief Information Officer, Mail Stop: t6-
A10M,
- U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email
to Infocollects.Resource@nrc.gov, and to the Desk Officer, Officer of Information and
Regulatory Affairs, NEOB-10202, (3150-0011) OMB, Washington, DC 20503.