IR 05000397/2026013

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Age-Related Degradation Inspection Report 05000397/2026013
ML26084A531
Person / Time
Site: Columbia 
(NPF-021)
Issue date: 03/30/2026
From: Wes Cullum
NRC/RGN-IV/DORS/EB1
To: Schuetz R
Energy Northwest
Shared Package
IR 2026013 List:
References
IR 2026013
Download: ML26084A531 (0)


Text

March 30, 2026

SUBJECT:

COLUMBIA GENERATING STATION - AGE RELATED DEGRADATION INSPECTION REPORT 05000397/2026013

Dear Robert Schuetz:

On February 26, 2026, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station and discussed the results of this inspection with Alex Javorik 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, Wes L. Cullum, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket No. 05000397 License No. NPF-21

Enclosure:

As stated

Inspection Report

Docket Number:

05000397

License Number:

NPF-21

Report Number:

05000397/2026013

Enterprise Identifier:

I-2026-013-0004

Licensee:

Energy Northwest

Facility:

Columbia Generating Station

Location:

Richland, WA

Inspection Dates:

February 23, 2026 to February 26, 2026

Inspectors:

D. Bryen, Reactor Inspector

R. Kumana, Senior Project Engineer

J. Talavera, Resident Inspector

Approved By:

Wes L. Cullum, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.

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.

REACTOR SAFETY

71111.21N.04 - Age-Related Degradation Age-Related Degradation (6 Samples)

(1) HPCS Battery B1
(2) Startup Transformer E-TR-S
(3) Reactor Core Isolation Cooling turbine & lube oil heat exchanger
(4) Diesel Generator fuel oil storage tanks
(5) Condensate Storage Tanks
(6) Service Water Spray Ponds

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On February 26, 2026, the inspectors presented the inspection results to Alex Javorik and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Calculations

5.32.10

Standby Service Water System - Piping Schedule

Calculations

Corrective Action

Documents

CR-

255826, 00336352, 00346741, 00358771, 00365921,

00366167, 00404166, 00408717, 00410392, 00410610,

00410803, 00410823, 00412987, 00413335, 00413987,

00415234, 00429681, 00433271, 00435503, 00440099,

00445850, 00446701, 00452699, 00457153, 00462457,

00463961, 00465226, 00467559, 00471984, 00474641

Corrective Action

Documents

Resulting from

Inspection

CR-

00481209, 00481250

2-204-00-88-1

Condensate Storage Tank

6/12/1975

2-204-00-89-1

Condensate Storage Tank

6/11/1975

Drawings

M527-1

Flow Diagram Condensate Supply System

104

03312

Review of Minimum Wall Thickness for Replacement

Stainless Steel Piping Required Per AR 6271

06653

Calc 5.32.10 Rev. 2, Provide Wall Thickness Justification for

SW(35)-2 (Siphon Line)

Engineering

Changes

10678

Installation of backup control power transformers/transfer

switches for E-TR-Ml, M2, M3, M4 and E-TR-S

ACE-AR 366167

Apparent Cause Evaluation:

Broken Vane on RCIC Turbine Wheel

AR-EVAL

00366867

Evaluate FME Left in RCIC-DT-1

Engineering

Evaluations

TM-2192

Acceptance Criteria for Structural Evaluation of

Erosion/Corrosion Thinning in Piping Systems

71111.21N.04

Miscellaneous

AMPBD-BPTI

Aging Management Program Basis Document - Buried

Piping and Tanks Inspection Program

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AMPBD-ESMP

Aging Management Program Basis Document - External

Surfaces Monitoring Program

AMPBD-FOC

Aging Management Program Basis Document - Fuel Oil

Chemistry Program

AMPBD-OCCW

Aging Management Program Basis Document - Open-Cycle

Cooling Water Program

AMPBD-RCIC

Aging Management Program Basis Document - Preventive

Maintenance - RCIC Turbine Casing

FSAR

Final Safety Analysis Report

Amendment

(June

25)

LRAMR-M18

License Renewal Aging Management Review: Aging

Management Review of the Reactor Core Isolation Cooling

System

PMID 25000

ASHE-INSULATORS, TEST AND CLEAN 230KV

INSULATORS

06/24/2021

PMID 27405-01

RCIC-HX-2, Inspect, Clean and Eddy Current Test (Shell)

21

PMID 27405-02

RCIC-HX-2, Seating Surface and Tube Corrosion Inspection

(Shell)

21

PMID 9636-09

RCIC-DT-1, Overhaul RCIC Turbine

2004

TS

TECHNICAL SPECIFICATIONS

Amendment

27 (July

25)

TSB

TECHNICAL SPECIFICATIONS BASIS

Revision 144

(July 2025)

OSP-INST-H101

Shift and Daily Instrument Checks

103

PPM 10.1.13

Foreign Materials Controls for Systems and Components

ENG-PRG-03

License Renewal Implementation

ENG-PRG-09

License Renewal Structures Monitoring Program Inspections 2

Procedures

OSP-SW-S101

SW Spray Pond Average Sediment Depth Measurement

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

PPM 10.7.1

RCIC Turbine (RCIC-DT-1) Inspection/Repair/Overhaul

PWTP-2

Underground Piping and Tanks Integrity Program

SWP-CAP-01

Corrective Action Program

SYS-4-23

Maintenance Rule Structural Baseline Inspections

Work Orders

WO- 2012204, 02043228, 02043305, 02105750, 02134544,

2140807, 02140808, 02145878, 02163709, 02165217,

2167558, 02183335, 02185493, 02189150, 02189416,

2198835, 02202278, 02210413, 02211774, 02222660,

263590