ML25350C078
| ML25350C078 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/18/2025 |
| From: | Wynar C NRC/RGN-IV/DORS/PBD |
| To: | Schuetz R Energy Northwest |
| References | |
| IR 2025010 | |
| Download: ML25350C078 (0) | |
Text
December 18, 2025 Robert Schuetz, Chief Executive Officer Energy Northwest MD 1023 76 North Power Plant Loop P.O. Box 968 Richland, VA 99352
SUBJECT:
COLUMBIA GENERATING STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000397/2025010
Dear Robert Schuetz:
On December 4, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Columbia Generating Station and discussed the results of this inspection with Jeremy Hauger, Acting Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.
However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight Process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
R. Schuetz 2
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
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 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Curtis J. Wynar, Acting Team Lead Inspection Program & Assessment Team Division of Operating Reactor Safety Docket No. 05000397 License No. NPF-21
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Wynar, Curtis on 12/18/25
SUNSI Review By: JV
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE SRI:DORS/PBC RI:DORS/PBD RI:DORS/PBB RI:DORS/IPAT ATL:DORS/IPAT NAME JVera JBrodlowicz CSigel SThapa CWynar SIGNATURE
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DATE 12/16/25 12/16/25 12/16/25 12/16/25 12/18/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000397 License Number:
NPF-21 Report Number:
05000397/2025010 Enterprise Identifier:
I-2025-010-0015 Licensee:
Energy Northwest Facility:
Columbia Generating Station Location:
Richland, WA Inspection Dates:
September 15, 2025, to December 4, 2025 Inspectors:
J. Brodlowicz, Resident Inspector C. Sigel, Resident Inspector S. Thapa, Reactor Inspector J. Vera, Senior Resident Inspector Approved By:
Curtis J. Wynar, Acting Team Lead Inspection Program & Assessment Team Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Columbia Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. 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.
OTHER ACTIVITIES - BASELINE 71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04) (1 Sample)
(1)
The inspectors performed a biennial assessment of the effectiveness of the licensees problem identification and resolution program, use of operating experience, self-
-assessments and audits, and safety-conscious work environment.
Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees problem identification and resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors sampled approximately 300 condition reports and their associated cause evaluations and corrective actions. The inspectors also conducted a five-year review of the standby service water system and the control room emergency chiller system. The corrective actions for the following non-cited violations and findings were evaluated as part of the assessment:
2025001-01, 2024003-01, 2024003-02, 2024003-03,2024403-01, 2024403-02, 2024401-01, 2023002-01, 2023002-02, 2023002-03 Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
Safety-Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety
-conscious work environment. The inspectors interviewed 25 station employees from various departments, interviewed the employee concerns program manager and reviewed employee concerns files.
4 INSPECTION RESULTS Assessment 71152B Corrective Action Program Effectiveness Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees performance in each of the areas of problem identification, problem prioritization and evaluation, and corrective actions adequately supported nuclear safety.
Problem Identification: Based on the samples reviewed, the team determined that the licensees performance in this area adequately supported nuclear safety. Overall, the team found that the licensee was identifying and documenting problems at an appropriately low threshold that supported nuclear safety. However, the stations risk-graded approach in the corrective action program results in many items, ranked as low risk, not having corrective actions other than to correct the observed condition and/or to close a condition report (CR) to trend. This, in effect, leaves underlying causes to be identified only when an issue worsens, or when a trend condition report recognizes the need for further investigation. The team also noted that several trend CRs were created when there were 10 to 20 trend items, a relatively high number. The team also found some examples of CRs where the information was not clearly written, such that understanding the condition and resolution path was difficult without referencing background information, other CRs, or contacting other resources.
Problem Prioritization and Evaluation: Overall, the team found that the licensee was appropriately prioritizing and evaluating issues to support nuclear safety. Of the samples reviewed, the team found that the licensee, in general, correctly characterized CRs as to whether they represented conditions adverse to quality and prioritized the evaluation and corrective actions in accordance with program guidance.
The team did identify one instance where several low consequence personnel contamination condition reports had been rated as low risk, and the resultant trend condition report was also rated as low risk. Although the sites Procedure SWP-CAP-06, Condition Report Review, Revision 30, does not strictly require upgrading of repetitive or recurring conditions to a higher risk level, it does show Repetitive/recurring conditions associated with a Low Consequence Issue as an example of a medium risk item. The team noted that not following the example indicated a tolerance for risk, specifically, the risk introduced by the multiple instances of personnel contamination events.
Corrective Actions: Overall, the team concluded that the licensee's corrective actions supported nuclear safety. The licensee generally developed effective corrective actions for the problems evaluated in the corrective action program and generally implemented these corrective actions in a timely manner commensurate with their safety significance. However, the inspectors noted one exception, that of recurring personnel contamination/uptakes. This exception is notable because of events that led to two White findings, associated root cause analyses, and corrective actions to preclude recurrence that preceded several later events.
Although the inspection team did not disposition these issues due to ongoing inspection efforts, these events demonstrated that corrective actions taken were not effective to preclude recurrence.
As part of this inspection, the team selected the standby service water system and the control room emergency chiller system for focused review within the corrective action program. For
5 these systems, the team performed sample selections of condition reports, looking at the adequacy of the licensee's evaluation process for determining which items are placed in the corrective action process, and the corrective actions taken. The team did not identify any concerns with these systems that were not already being addressed by the station's monitoring and corrective action programs.
Assessment 71152B Use of Operating Experience The team reviewed a variety of sources of operating experience including 10 CFR Part 21 notifications and other vendor correspondence, NRC generic communications, and publications from various industry groups. The team determined that the licensee is adequately screening and addressing issues identified through operational experience that apply to the station and that this information is evaluated in a timely manner once it is received.
Assessment 71152B Self-Assessment and Audits The team reviewed a sample of departmental self-assessments to assess whether performance trends were regularly identified and effectively addressed. The team also reviewed audit reports to assess the effectiveness of assessments in specific areas. Overall, the team concluded that the licensee had an adequate departmental self-assessment and audit process.
Assessment 71152B Safety-Conscious Work Environment The team conducted a reduced number of activities to evaluate the licensees safety-conscious work environment (SCWE) due to an inspection having been completed recently at Columbia Generating Station using Inspection Procedure 93100, Safety-Conscious Work Environment Issue of Concern Follow-up and having identified no significant issues per the resultant report (Agencywide Documents Access and Management System [ADAMS]
Accession No. ML25252A208). The teams activities included interviews with 25 employees from different departments that included radiation protection, engineering, operations, emergency preparedness, and security. The purpose of these interviews was (1) to evaluate the willingness of the licensees staff to raise nuclear safety issues, either by initiating a CR or by another method, (2) to evaluate the perceived effectiveness of the corrective action program at resolving identified problems, and (3) to evaluate the licensees SCWE. The team also observed interactions between employees during plant meetings.
The team found that the licensee had a SCWE where individuals felt free to raise concerns without fear of retaliation. All individuals indicated that they would not hesitate to raise safety concerns through at least one of the several means available at the station. Most expressed positive experiences when raising issues to their supervisors and after documenting issues in CRs, although a few stated that sometimes there would be lack of followup on the final disposition of an issue brought up in a CR.
The team interviewed the new employee concerns program (ECP) manager and reviewed a sampling of employee concerns files, which indicated issues brought up are being addressed.
6 However, the team noted that recently, the station had changed the process for anonymous condition reports to be routed though the ECP. Some personnel stated that they were unclear as to how the new process worked, and some opined that routing the process through ECP kept knowledge of issues from the station in general, potentially limiting the sharing of useful information and experience.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On December 4, 2025, the inspectors presented the biennial problem identification and resolution inspection results to Jeremy Hauger, Acting Site Vice President, and other members of the licensee staff.
7 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Calculations ME-02-17-03 Air flow requirements for CCH system following rebalance 2
71152B Corrective Action Documents AR ######
439019, 435686, 439462, 444743, 446167, 446169, 446662, 467647, 449784, 450492, 450493, 436464, 441249, 445630, 450484, 451357, 455276, 457823, 458501, 464140, 470757, 470969, 472564, 472745, 454585, 461511, 352668, 429109, 429895, 455233, 462139, 465541, 448718, 291250, 458389, 431146, 449901, 454626, 203953, 468270, 453228, 447420, 425452, 464885, 463495, 451792, 454803, 424457, 447254, 401129, 442417, 473890, 458173, 451231, 439130, 451639, 457589, 458139, 458155, 458167, 463621, 467311, 467450, 452817, 453337, 450088, 465202, 461805, 468289, 454795, 464125, 445902, 435148, 441283, 452449, 463707, 451191, 454800, 428895, 461820, 461822, 461817, 447971, 451500, 452267, 471180, 470380, 470395, 470470, 470501, 454942, 457449, 462203, 459014, 467525, 467900, 472702, 444330, 447592, 456280, 458834, 451398, 452163, 452298, 458930, 425629, 429785, 451229, 453321, 453345, 455378, 444083, 464431, 449475, 449584, 451924, 452413, 459250, 460330, 460062, 467153, 451184, 457500, 463170, 465087, 465822, 465824, 466476, 466478, 469874, 471394, 472509, 440273, 442840, 444045, 456373, 457410, 466447, 470350, 463961, 464670, 450319, 450452, 450792, 456177, 463833, 464216, 464487, 464658, 466122, 468526, 456622, 451559, 463171, 467888, 464513, 468049, 457830, 465625, 456237, 444245, 421883, 451216, 458066, 459817, 460420, 460617, 460894, 460975, 461127, 456968, 471349, 474746, 470238, 449621, 449899, 467731, 448156, 451361, 451784, 451803, 452196, 430719, 462907, 455203, 468588, 474060, 458526, 463332, 446557, 447511, 459415, 459936, 460740, 463980, 451426, 457815, 466948, 451035, 434877, 451251, 448688, 451559, 456001, 448073, 451149, 454448, 454802, 463450, 470545, 473958, 453061, 454880, 460519, 466490, 469274, 460431,
8 Inspection Procedure Type Designation Description or Title Revision or Date 461606, 438708, 468951, 454942, 458969, 467647, 446662, 446169, 446167, 444743, 439462, 436344, 439019, 469198, 469263, 469271, 469484, 451184, 450493, 450492, 449784, 444045, 442840, 439939, 452528, 463833, 464216, 464487, 464658, 466122, 454587, 405609, 452267, 451500, 447971, 471180, 470380, 470395, 470470, 470501, 457449, 446585, 459510, 462203, 444330, 447592, 456280, 458834, 459014, 467525, 467900, 472702, 448879, 449342, 449348, 449389, 450111, 451924, 452413, 452737, 453848, 455069, 455603, 456186, 457453, 458930, 459250, 460062, 460330, 461823, 462963, 464588, 467123, 467153, 451397, 451398, 452163, 452298, 472344, 471624, 425629, 429785, 461805, 444083, 449475, 449584, 456028, 471318, 457719, 457000, 456943, 435686, 436608, 440273, 444241, 467835, 467357, 465171 IT for 429109 Investigation Template for SW-B Leak on Piping Elbow 02/01/2022 IT for 454942 Investigation template for AR 45494245494203/12/2024 IT for 457458 WMA-CC-53B1 cooling coil low flow during OSP-CCHIST-M702 Investigation Template 05/16/2024 IT for 462203 Investigation template for AR 46220346220312/16/2024 IT for 462203 Rev. 2 Investigation template for AR 4622034622032
IT for 470395 Investigation template for AR 47039547039505/19/2025 MRT Review 9/16/2025 Daily Management CR Review 09/16/2025 PI for 468337 TRS clearance hung before being deenergized Prompt Investigation 04/16/2025 RCE for 454585 SW Leak in DMA-CC-21 Root Cause Evaluation 04/18/2024 SWP-CAP-01 Corrective Action Program 052 Work Requests (WR) 29178320, 29181059, 29182918 Engineering Evaluations RPT. NO.
38027.004-TR-001 Erosion Susceptibility Evaluation (ESE) - Post RFO-26 (2023)
Update 001 Miscellaneous 1.13 CR Counts Table showing the number of anonymous corrective action 08/20/2025
9 Inspection Procedure Type Designation Description or Title Revision or Date by Category documents initiated during each month of the inspection period RCE 447971 Root Cause Evaluation Radiological Controls during RWCU HX Project in R25 07/25/2023 RCE 451500 Root Cause Evaluation Revision 2 NRC White Findings for Radiological Controls and Uptakes during RWCU HX Project in R25 12/04/2023 RCE 454585 Root Cause Evaluation SW Leak in DMA-CC-21 04/22/2024 RCE 456014 Root Cause Evaluation NRC Radiological Controls and Uptakes during the RWCU HX Project in R25 Revision 1, Minor Revision 3 RCE 468526 Root Cause Evaluation Reactor Recirculation Valve 67B Vent Line Leak Revision 0, Minor Revision 01 RP High Risk Evolution Critique for AR 456280456280A critique covering significant gaps in radiological planning or coverage of AR 456280456280
08/10/2023 Operability Evaluations 454626 Technical Assessment Supporting Reportability (2)(1) 1.10.11 Technical Assessments Supporting Reportability and Reportability Evaluations 004 1.3.1 Operating Policies, Programs, and Practices 143 1.3.64 Plant Clearance Order 50 1.5.11 Maintenance Rule Program 017 1.5.13 Preventive Maintenance Optimization Living Program 050 10.23.7 DMA Damper Linkage Setup 006 11.2.13.1 Radiation and Contamination Surveys 050 11.2.4.5 Whole Body Counts and Daily Checks Using the Renaissance Fastscan 23 CDM-01 Cause Determination Manual 018 CDM-01 Cause Determination Manual 017 GBP-AIT-01 Asset Suite Action Tracking - Action Request Types, Technical Lead Responsibilities, and Use of Action Request Type SELF 1
Procedures GBP-CAP-03 Trending Program 005
10 Inspection Procedure Type Designation Description or Title Revision or Date GBP-ECP-01 Employee Concerns Program 3
GBP-ECP-02 Monitoring Energy Northwest's Nuclear Safety Culture and SCWE 6
GEN-RPP-04 Entry Into, Conduct In, and Exit from Radiologically Controlled Areas 037 OI-12 Clearance Order Instruction 60 OI-14 Columbia Generating Station Operational Challenges and Risk Program 017 OPEX-01 Operating Experience Program Implementation Manual 012 OQAPD-01 Operational Quality Assurance Program Description (EN-QA-004) 57 QAP-ASU-02 Procedure for developing Quality Audit Reports.
006 QAP-ASU-07 Provisions for use of the peer verification process.
010 QAP-ASU-09 Procedure for stop work steps.
000 SWP-AIT-01 Action Request - Initiation, Evaluation and Assignment Activities 008 SWP-CAP-01 Corrective action program procedure.
052 SWP-CAP-06 Condition Report Review 030 SWP-OPX-01 Operating Experience Program 002 SWP-RPP-01 Radiation Protection Program 018 SYS-4-22 Maintenance Rule Program 016 451792 Performance Assessment Review Board (PARB) 01/16/2024 AU-AD-24 2024 Document Control and Records Management Audit 05/30/2024 AU-CA-24 Corrective Action Program 11/19/2024 AU-EN-24 2024 Engineering Programs Audit 06/24/2024 AU-FP-23 2023 Fire Protection Audit 10/16/2023 AU-RP/RW-24 Radiation Protection self assessment 01/15/2025 Functional Area Scorecard 6.0 Functional Area Scorecard for Radiation Protection January 2024 January 2024 Functional Area Scorecard 6.0 Functional Area Scorecard for Training January 2024 January 2024 Self-Assessments Functional Area Scorecard 6.0 Design Engineering / Configuration Management - February 2024 February 2024
11 Inspection Procedure Type Designation Description or Title Revision or Date Functional Area Scorecard 6.0 Emergency Preparedness - January 2025 January 2025 Operational MRM 2nd quarter 2025 Operational MRM Performance Report 2025 SW SHIP Service Water System Health Improvement Plan 03/10/2025 SWP-ASU-01 Att.
3 2023 Security Program 12-Month Audit Frequency Evaluation 0
WO 02198891, 02228369, 02232293, 02222440, 02208392, 02225487, 02220392, 02235686, 29181059, 29183585, 29182918, 29178320 Work Orders