IR 05000482/2025003
| ML25345A432 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/15/2025 |
| From: | Ami Agrawal NRC/RGN-IV/DORS/PBB |
| To: | Reasoner C Wolf Creek |
| Sigel C | |
| References | |
| IR 2025003 | |
| Download: ML25345A432 (0) | |
Text
December 15, 2025
SUBJECT:
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2025003
Dear Cleve Reasoner:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On November 18, 2025, the NRC inspectors discussed the results of this inspection with Eric Carlson, Plant Manager, 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 1, 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.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be Severity Level IV is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Wolf Creek Generating Station. 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, Ami N. Agrawal, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier:
I-2025-003-0005
Licensee:
Wolf Creek Nuclear Operating Corp.
Facility:
Wolf Creek Generating Station
Location:
Burlington, KS
Inspection Dates:
July 1, 2025, to September 30, 2025
Inspectors:
C. Henderson, Senior Resident Inspector
C. Sigel, Resident Inspector
Approved By:
Ami N. Agrawal, Chief
Reactor Projects Branch B
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Wolf Creek 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. A licensee-identified non-cited violation is documented in report section: 71114.0
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Wolf Creek Generating Station began the inspection period at full power. On September 23, 2025, the unit commenced power coast down for refueling outage 27, which was scheduled to start on October 2,
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 onsite 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)train B residual heat removal system on July 14, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)switchboard and battery rooms 2 and 4, fire area C-15, on July 16, 2025 (2)circulatory water and service water building, fire area CW/SW, on July 16, 2025 (3)upper cable spreading room, fire area C-22, on July 22, 2025 (4)reactor coolant pump A seal chiller temporary modification, fire areas A-8, A-12, and A-25, on July 31, 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 between July 14, 2025, and September 9, 2025.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the annual dynamic exam for licensed operator requalification on July 29, 2025, and just-in-time training for reactor shutdown for refueling outage 27 on September 15, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
(1)essential service water and service water system maintenance effectiveness review on September 30, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)rod control logic cabinet power supply failure emergent work and risk review on July 16, 2025 (2)refueling outage 27 schedule and risk assessment review on September 18, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)train A motor-driven auxiliary feedwater pump outboard seal leak off degraded trend operability determination on July 17, 2025 (2)containment spray and centrifugal charging pump room cooler operability determination on July 21, 2025 (3)emergency boration path during planned maintenance of motor-operated valve BGHV8104 operability determination on August 21, 2025 (4)train A offsite circuit and component cooling water system with two pumps running for normal operation operability determination on August 22, 2025
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)rod control power supply temporary modification for a failed power supply on July 18, 2025 (2)temporary chiller for reactor coolant pump A seal injection on August 7, 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) (3 Samples)
(1)train B control room air conditioning system technical specification equipment outage post-maintenance testing on August 29, 2025 (2)train B control room emergency ventilation system technical specification equipment outage post-maintenance testing on September 30, 2025 (3)emergency diesel generator A technical specification equipment outage post-maintenance testing on September 30, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)emergency boration and alternate boration paths on August 14, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (2 Samples)
The inspectors evaluated:
(1)licensed operator response to a natural event and loss of service water and essential service water on August 6, 2025 (2)licensed operator response to an independent spent fuel storage facility event on August 13,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures Sample (IP Section 02.04)===
- (1) July 1, 2024, through June 30, 2025
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) July 1, 2024, through June 30, 2025
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)off normal procedure for loss of safety-related inverters
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71114.04 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Paragraph 50.54(q)(3) of 10 CFR states, in part, the licensee may make changes to its emergency plan without NRC approval only if the licensee performs and retains an analysis demonstrating that the changes do not reduce the effectiveness of the plan. Contrary to the above, Wolf Creek made changes to its emergency plan without NRC approval but failed to perform and retain an analysis demonstrating that the changes do not reduce the effectiveness of the plan. Specifically, Procedure APF 06-002-02, "Emergency Action Level Technical Bases," Revision 3, was put into effect December 4, 2024, and a report of the changes was made to the NRC on December 12, 2024. Additional changes were added to Procedure APF 06-002-02 which had not been evaluated to ensure that they do not reduce the effectiveness of the plan and were not on the report of the changes made to the NRC.
The inspectors determined that changes to Procedure APF 06-02-002 did not reduce the effectiveness of the emergency plan.
Significance/Severity: Severity Level IV. Using the NRC Enforcement Policy, dated August 23, 2024, Section 6.6.d.1, because it involves the licensees ability to meet or implement a regulatory requirement not related to assessment or notification such that the effectiveness of the emergency plan is reduced.
Corrective Action References: Condition Report
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 18, 2025, the inspectors presented the integrated inspection results to Eric Carlson, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Report
(CR)
10042607
Procedures
CKL EJ-120
RHR System Lineup
47A
Calculations
XX-X-004
Combustible Fire Loading for Each Room in the Various Fire
Areas at WCNOC
Corrective Action
Documents
Condition Report
(CR)
10042302, 10042589
Drawings
KD-7496
One Line Diagram
E-1F9905
Fire Hazard Analysis
PT115374
Scaffolds Blocking Spray Pattern On Aux 2000 Hallways
PT116227
Fire Permit
PT116616
Breach GLD0098 for Temp A RCP Cooling
PT116621
Combustible Materials to Support TMO 25-003-BG
WCNOC-PSA-
067
Internal Fire - Qualitative Screening, Quantitative Screening
and Quantification Notebook
Miscellaneous
WCNOC-PSA-
076
Wolf Creek Generating Station PRA Internal Fire -
Qualitative Screening, Quantitative Screening and
Quantification Notebook
ALR KC-888
Fire Protection Panel KC-008 Alarm Response
AP 10-102
Control of Combustible Materials
AP 10-103
Fire Protection Impairment Control
AP 10-104
Breach Authorization
AP 10-106
Fire Preplans
OFN KC-016
Fire Response
SYS FP-012
Operation of the CWSH Fire Protection Panel
Procedures
WCRE-35
Boundary Matrix
Corrective Action
Documents
Condition Report
(CR)
10039173, 10039177, 10041227, 10041250, 10041364,
10042465
Corrective Action
Documents
Resulting from
Inspection
Condition Report
(CR)
10041810
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-0022
P&ID Plant Service Water System (WS)
M-12EA01
Piping and Instrumentation Diagram Service Water System
M-12EA02
Piping and Instrumentation Diagram Service Water System
M-12EF01
Piping Instrumentation Diagram Essential Svc Water System
Drawings
M-12EF02
Piping and Instrumentation Diagram Essential Service Water
System
Procedures
ALR 00-008B
Serv Wtr Press HI LO
18A
Corrective Action
Documents
Condition Report
(CR)
10042383, 10043305, 10043310, 10043341, 10043602,
10043606, 10043652
Miscellaneous
ODMI 2025-02
Rod Control Logic Cabinet Power Supply Failure
ALR 00-081A
Two/More Rods at Bottom
Outage Risk Management
BD-EMG E-0
Reactor Trip or Safety Injection
EMG E-0
Reactor Trip or Safety Injection
EMG E-1
Loss of Reactor or Secondary Coolant
2A
EMG E-2
Faulted Steam Generator Isolation
EMG ES-03
SI Termination
OFN SF-011
Realignment of Dropped, Misaligned Rod(s) and Rod Control
Malfunctions
STS IC-740A
RHR Switchover to Recirc Sump Test - Train A
STS PE-154
LLRT Valve Lineup for Penetration 54
Procedures
SYS NN-332
Deenergizing NN Buses
AN-07-009
Gothic Model for CCW Pump Room Temperature
GL-03-W
Auxiliary Building HVAC
GL-M-007
Calculate cooling loads in SR pump rooms post LOCA
Calculations
GL-M-007
Calculate Cooling Load in SR Pump Rooms Post LOCA:
1107, 1108, 1109, 1110, 1111, 1112, 1113, 1114, 1401,
1406
Corrective Action
Documents
Condition Report
(CR)
10042197, 10042295, 10043589
Corrective Action
Documents
Resulting from
Condition Report
(CR)
10042627, 10043597, 10043600
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
E-13AL08
Schematic Diagram Instrumentation and Alarms (SH 3)
M-12BB01
Piping and Instrumentation Diagram Reactor Coolant System
M-12BB02
Piping and Instrumentation Diagram Reactor Coolant System
M-12BG01
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BG02
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BG03
Piping and Instrumentation Diagram and Volume Control
System
M-12BG05
Piping and Instrumentation Diagram Chemical and Volume
Control System
Drawings
M-12EM02
Piping and Instrumentation Diagram High Pressure Coolant
Injection System
E-012.2-00124
General Electric Component Cooling Water Pump 700 HP
1185 PRM 4000 V 1.0 SF Model 5K821167C31
W01
Miscellaneous
ODMI 2025-03
Elevated A RCP #1 Seal Leak Off Rate
ALR 00-129A
MD AFP A Trouble
Operability Determinations and Functionality Assessments
BD-EMG E-0
Reactor Trip or Safety Injection
EMG E-0
Reactor Trip or Safety Injection
EMG E-1
Loss of Reactor or Secondary Coolant
2A
EMG ES-02
Reactor Trip Response
EMG ES-04
Natural Circulation Cooldown
24A
OFN BG-009
Emergency Boration
28A
OFN KA-019
Loss of Instrument Air
16A
OFN NB-030
Loss of AC Emergency Bus NB01 (NB02)
STS AL-101
MDAFW Pump A Inservice Pump Test
STS KJ-001A
Integrated D/G and Safeguards Actuation Test - Train A
73A
SYS BG-200
Reactor Makeup Control System Normal Operation
Procedures
SYS EG-120
Component Cooling Water System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
WO 20102, 47048, 48843, 56720, 74952, 83580, 92070,
21-471822-000, 21-476639-000, 22-477654-000,
2-478391-000, 22-479779-000, 22-480431-000,
2-481688-000, 22-482296-000, 22-483479-000
Calculations
SA-90-056
Reactor Protection System/Engineered Safety Features
Actuation System Channel Error Allowances
Corrective Action
Documents
Condition Report
(CR)
10042365, 10042383, 10042915, 10042983
M-12BB03
Piping and Instrumentation Diagram Reactor Coolant System
M-12BG01
Piping and Instrumentation Diagram Chemical and Volume
Control System
Drawings
M-763-00369
Power Supplies, Phase Sense and Multiplex Control
Engineering
Changes
DECP 25-002-SF
Rod Control Temporary Power Supply
M-763-00872
Westinghouse Rod Control System Corrective Maintenance
Guide
ODMI 2025-03
Elevated A RCP #1 Seal Leak Off Rate
PT116615
Temp Mod for RCP A Seal Cooling - 8-inch Pen Seals
P131W1309 and P131W1310
PT116702
Breach Door 13322 to Run a Fill Hose for RCP Seal Temp.
Chiller
Westinghouse Rod Control System Corrective Maintenance
Guide
Miscellaneous
Westinghouse Setpoint Methodology as Applied to the Wolf
Creek Generating Station
AP 05-005
Design, Implementation, and Configuration Control of
Modifications
Temporary Configuration Changes
16B
OFN BB-005
RCP Malfunctions
TMO 25-003-BG
A RCP #1 Seal Injection Heat Exchanger
Procedures
TMP 25-005
Temporary Chiller for RCP A Seal Injection
0, 1
Work Orders
WO 133185, 135106, 135110, 137150, 137153
Corrective Action
Documents
Condition Report
(CR)
10042790, 10043792
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
Condition Report
(CR)
10043582, 10043625
E-13GK10A
Schematic Diagram Control Room Pressurization Fan and
Supply Dampers
M-12BG01
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BG02
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12BG03
Piping and Instrumentation Diagram and Volume Control
System
M-12BG05
Piping and Instrumentation Diagram Chemical and Volume
Control System
M-12EF01
Piping and Instrumentation Diagram Essential SCV Water
System
M-12EM02
Piping and Instrumentation Diagram High Pressure Coolant
Injection System
Drawings
M-12GK01
Piping and Instrumentation Diagram Control Building HVAC
Heat Exchanger Program
Operability Determinations and Functionality Assessments
CKL EF-120
Essential Service Water Valve, Breaker and Switch Lineup
EMG E-0
Reactor Trip or Safety Injection
EMG E-1
Loss of Reactor or Secondary Coolant
2A
EMG ES-02
Reactor Trip Response
EMG ES-04
Natural Circulation Cooldown
24A
MPE GK-003
Control Room and Class 1E A/C Units Preventive
Maintenance Activity
MPE GK-004
GK Unit Preparation for Work
OFN BG-009
Emergency Boration
28A
STN PE-037B
ESW Train B Heat Exchanger Flow and DP Trending
26B
STS GK-001B
Control Room Emergency Vent System Train B Operability
Test
Procedures
STS GK-002B
Control Room A/C Unit Operability Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SYS BG-200
Reactor Makeup Control System Normal Operation
SYS BG-206
Boric Acid System Operation
WCRE-08
WCGS Fuse List
Work Orders
WO 89326, 102014, 102016, 102022, 128458, 132840, 132455,
340653, 15-404306-016
Miscellaneous
WCNOC-163
Mitigating System Performance Index (MSPI) Basis
Document
On-Line Nuclear Safety and Generation Risk Assessment
Procedures
SYS KJ-123
Post Maintenance Run of Emergency Diesel Generator A
71151
Work Orders
Corrective Action
Documents
Condition Report
(CR)
10039304
E-11NK01
Class 1E 125V DC System Meter and Relay Diagram
E-11NK02
Class 1E 125V DC System Meter and Relay Diagram
Drawings
E-13AB29
Schematic Diagram Main Steam Isolation Valves Control -
Part 2
ALR 00-025C
NK01 Trouble
13A
ALR 301
24 VDC Class 1E Switchboard NK01
EMG C-0
Loss of All AC Power
46A
EMG E-0
Reactor Trip or Safety Injection
OFN NB-030
Loss of AC Emergency Bus NB01 (NB02)
OFN NK-020
Loss of Vital125 VDC Bus NK01 NK02 NK03 NK04
OFN NK-021
Loss of Vital 120 VAC Instrumentation Bus
31A
SYS GK-122
Manual CRVIS Line-Up
Procedures
SYS NN-332
Deenergizing NN Buses
18