IR 05000397/2025004
| ML26033A038 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/04/2026 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Schuetz R Energy Northwest |
| Sanchez A | |
| References | |
| IR 2025004 | |
| Download: ML26033A038 (0) | |
Text
February 03, 2026
SUBJECT:
COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2025004
Dear Robert Schuetz:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On January 22, 2026, the NRC inspectors 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.
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, John L. Dixon Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Docket No. 05000397 License No. NPF-21
Enclosure:
As stated
Inspection Report
Docket Number:
05000397
License Number:
Report Number:
Enterprise Identifier:
I-2025-004-0010
Licensee:
Energy Northwest
Facility:
Columbia Generating Station
Location:
Richland, WA
Inspection Dates:
October 1, 2025, to December 31, 2025
Inspectors:
P. Breidenbach, Operations Engineer
J. Brodlowicz, Resident Inspector
N. Hernandez, Senior Operations Engineer
C. Highley, Senior Resident Inspector
Approved By:
John L. Dixon Jr., Chief
Reactor Projects Branch D
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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
Type Issue Number Title Report Section Status LER 05000397/2025-001-00 Pressure Boundary Leakage Resulting in a Technical Specification Required Plant Shutdown, Degraded Condition, and Condition Prohibited by Technical Specifications 71153 Closed
PLANT STATUS
The unit began the inspection period at full rated thermal power. On December 12, 2025, the unit was down powered to 61 percent for a control rod sequence exchange and adjustable speed drive maintenance. The unit was returned to full rated thermal power on December 14, 2025. On December 28, 2025, the unit was down powered to 95 percent for a failed module in the main generator voltage regulator. The unit was returned to full rated thermal power on December 29, 2025, and remained at or near full rated thermal power for the remainder of the inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)125 Vdc bus, S1-2 electrical system, on November 11, 2025
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the emergency core cooling system pump rooms, on November 11, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)drywell cooling coils and reactor component cooling water supply heat exchanger, on November 4, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on October 10, 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on the week of September 1, 2025, and the week of September 15, 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during planned down power for a rod pattern adjustment on December 12, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated training in the simulator during an emergency preparedness scenario on October 20, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Maintenance rule periodic assessment for the period January 2023 to December 2024, on October 24, 2025 (2)open phase detection system (OPDS), on November 17, 2025 (3)control air system maintenance rule a(1) to a(2) status change, on December 3, 2025
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)commercial grade dedication of conduit to Q class 2 component, on October 30, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessment:
(1)auto scram timer failure to communicate during initial rod scrammed, on December 30, 2025
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (7 Samples)
(1)reactor heat removal loop B operability test following replacement of the pump start and minimum flow valve open time delay relay, on October 30, 2025 (2)standby liquid control squib valve continuity checks following relay lamp and holder replacement, on October 30, 2025 (3)semiannual test of emergency diesel generator 1 following Engineering Change 20228, on November 11, 2025 (4)annual battery inspection following cell 41 replacement in the 250 V batteries, on November 11, 2025 (5)intermediate range monitor F channel calibration after emergent troubleshooting and repair, on November 11, 2025 (6)fire pump 1 battery testing following refilling and equalizing, on November 28, 2025 (7)main steam isolation valve closure scram functional test after main steam line A outboard isolation valve (MS-V-28A) not full open position relays 3A and 3B failed to energize, on December 19, 2025
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) October 1, 2024, through September 30, 2025
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) October 1, 2024, through September 30, 2025
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000397/2025-001-00, Pressure Boundary Leakage Resulting in a Technical Specification Required Plant Shutdown, Degraded Condition, and Condition Prohibited by Technical Specifications (ADAMS Accession No. ML25161A146). The inspection conclusions associated with this LER are documented in Inspection Report 05000397/2025002 (ML25213A155) under Inspection Results Section 71111.15 as Severity Level IV NCV 05000397/2025002-01. This LER is Closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 18, 2025, the inspectors presented the biennial requalification inspection results to Michael Davis, Training Director, and other members of the licensee staff.
- On January 22, 2026, the inspectors presented the integrated inspection results to Jeremy Hauger, Acting Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SOP-ELEC-DC-
LU
DC Electrical Distribution System Breaker Lineup
Corrective Action
Documents
00476189
Engineering
Evaluations
ME-02-02-02
Calculation for Reactor Building Flooding Analysis
Procedures
15.4.6
Essential Fire Rated Penetration Seal and Essential Fire and
Flood Barrier Operability Inspection
M525-1
Closed Cooling Water System Reactor Building
Drawings
M607-2
Steam and Liquid Sampling Reactor Building
2072439
Containment Cooling Coil 2A Clean and Inspect
05/23/2019
2072440
Containment Cooling Coil 2B Clean and Inspect
05/23/2019
2109606-01
Containment Cooling Coil 1B Clean and Inspect
05/22/2019
2109607-01
Containment Cooling Coil 1C Clean and Inspect
05/19/2019
Work Orders
2109615-01
Containment Cooling Coil 1A Clean and Inspect
05/19/2019
Miscellaneous
Table 03.03-1
Results Table for Annual Exam
2/11/2025
CGS AR-460431460431Emergent Paragon Orange Condition Unrecognized
07/24/2024
CGS AR-466159466159Entry into PPM 5.3.1 Low SFP Level
01/28/2025
Corrective Action
Documents
CGS AR-473511473511T.S. Equipment Removed from Service without Proper
Tracking
07/10/2025
CGS AR-473511473511Align the Station to the Standard of "Rapid" Power Reduction
for Consistency
Corrective Action
Documents
Resulting from
Inspection
TREQ 25-0097
Training Recommended for Aligning the Station on the
Standard of "Rapid" Power Reduction for Consistency
License Operator Medical Records (Total of 6)
25 LOCT
Biennial Written
Exam "A"
SRO "A" Crew Written Exam Questions
Miscellaneous
25 LOCT
Biennial Written
Exam "C"
RO and SRO "C" Crew Written Exam Questions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LE000006
Annual Exam Scenario
LE000007
Annual Exam Scenario
LEA00022
LEA00033
Corrective Action
Documents
00401326, 00403929, 00475048, 00475050, 00475817,
00476781
00310273-12
OPDS Performance Criteria Form
00462907
CAS-SYSTEM (a)(1) Performance Improvement Plan (PIP)
and Goals
10/10/2024
Engineering
Evaluations
00476781
CAS a(1) Evaluation
11/05/2025
Maintenance Rule Program Documentation of Periodic
Assessment for the Period January 2023 - December 2024
2/24/2025
Standard Procurement and Use Policy
OPDS-01
Maintenance Rule Function Basis Document for Open Phase
Detection System
Miscellaneous
Receipt Number
83894
Report of Analysis for Cable Tie for Safety Systems
2/28/2022
MOT-RELAY-1
Maintenance Optimization Template for: Protective Relays
11/05/2024
SPES-1.6.5
Commercial Grade Dedication Spare Parts Engineering
Standard
Procedures
SWP-PUR-02
Site Wide Procedure Procurement Technical Reviews
Work Orders
2192934
Corrective Action
Documents
00478738
Corrective Action
Documents
00475080, 00477812, 00478670
Miscellaneous
15.2.1
Fire Pump Battery Testing
Month Battery Inspection of 250 VDC E-B2-1
Accident Monitoring Instrument Channel Checks
OSP-RHR/IST-
Q703
RHR Loop B Operability Test
Procedures
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Standby Liquid Control Valve Alignment and Squibb Valve
Continuity Check
Work Orders
207859, 02215220, 02215473-01, 02216185, 02225068,
229297, 02237469, 02239030